Letter Sequence Response to RAI |
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EPID:L-2023-LLE-0086, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation (Approved, Closed) |
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MONTHYEARML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation Project stage: Request ML24045A0272024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule Project stage: RAI CNL-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation Project stage: Response to RAI ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting Project stage: Approval 2024-02-14
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Category:Letter type:CNL
MONTHYEARCNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-013, Cycle 22 Reload Analysis Report2024-03-14014 March 2024 Cycle 22 Reload Analysis Report CNL-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 CNL-24-011, Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology2024-01-22022 January 2024 Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology 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 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 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 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 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 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 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 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) 2024-09-24
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 CNL-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 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 CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-007, Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2022-04-0606 April 2022 Supplement to Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) CNL-22-028, Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-03-18018 March 2022 Response to Request for Additional Information Regarding License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-052, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531)2021-07-21021 July 2021 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.8.6, Battery Cell Parameters (TS-531) CNL-21-033, Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components2021-04-28028 April 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components CNL-21-017, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099)2020-12-29029 December 2020 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099) CNL-20-089, Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518)2020-12-21021 December 2020 Response to RAI Re Application for Tech. Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-518) CNL-20-059, Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals2020-08-10010 August 2020 Response to Request for Additional Information Regarding Proposed Alternative Request No. 0-ISI-47 for the Third, Fifth, and Fourth 10-Year Inservice Inspection Intervals CNL-19-122, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights2019-12-17017 December 2019 Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...2019-08-0808 August 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water... CNL-19-052, Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second2019-07-19019 July 2019 Response to NRC Request for Additional Information Regarding Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information2019-01-25025 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information CNL-19-007, Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus2019-01-16016 January 2019 Supplement 5, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus CNL-19-011, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results2019-01-16016 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results CNL-18-139, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information2018-12-14014 December 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 42018-12-13013 December 2018 Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4 CNL-18-117, Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-462018-10-17017 October 2018 Response to Request for Additional Information Regarding Browns Ferry Units 1, 2, and 3: Code Case N-702 for Alternative Request ISI-46 CNL-18-120, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ..2018-10-11011 October 2018 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant Unit 1, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-year ... ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-0342018-07-23023 July 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034 CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-032, Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program2018-03-27027 March 2018 Tennessee Valley Authority Response to NRC Request for Additional Information (Set 2) Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program CNL-18-011, Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)2018-02-0505 February 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to BFN Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) CNL-17-130, Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For..2017-10-23023 October 2017 Update to Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection For.. CNL-17-109, Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Genera2017-09-18018 September 2017 Response to NRC Request for Additional Information for License Amendment Request to Revise Modifications and an Implementation Item Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generati CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-039, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory..2017-03-10010 March 2017 Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory.. CNL-17-035, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information2017-03-0303 March 2017 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate(Epu) - Supplement 38, Spent Fuel Pool Criticality Safety Analysis - Updated Information CNL-17-017, Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects2017-02-0303 February 2017 Proposed Technical Specifications (TS) Change TS-505 Request for License Amendments - Extended Power Uprate (EPU) - Supplement 37, Transmission System Update - Environmental Aspects CNL-17-015, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects2017-01-20020 January 2017 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf2017-01-20020 January 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safe CNL-16-196, Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-12-19019 December 2016 Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-16-161, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional..2016-10-13013 October 2016 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 33, Revised Response to Request for Additional.. CNL-16-145, Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 302016-09-23023 September 2016 Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30 CNL-16-150, Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 312016-09-21021 September 2016 Revised Response to Requests for Additional Information Proposed Technical Specifications Change TS-505 - Request for License Amendment - Extended Power Uprate - Supplement 31 CNL-16-133, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 72016-09-15015 September 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 7 CNL-16-152, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information2016-09-12012 September 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 32, Revised Responses to Requests for Additional Information CNL-16-126, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)2016-08-24024 August 2016 Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) 2024-03-14
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Text
1101 Market Street, Chattanooga, Tennessee 37402
CNL-24-026
March 14, 2024
10 CFR 73.5
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, 50-296, and 72-052
Subject:
Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation (EPID L-2023-LLE-0086)
References:
- 1. TVA Letter to NRC, CNL-23-065, Tennessee Valley Authority (TVA) -
Browns Ferry Nuclear Plant Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation, dated December 21, 2023 (ML23355A206)
- 2. NRC electronic mail to TVA, Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule (EPID L-2023-LLE-0086), dated February 14, 2024 (ML24045A027)
In Reference 1, Tennessee Valley Authority (TVA) submitted a request for exemption from the specific requirements in Title10 of the Code of Federal Regulations (10 CFR) Part 73, Subpart T, Security Notifications, Reports, and Recordkeeping, 10 CFR 73.1200(a) through 10 CFR 73.1200(t), Notification of physical security events, 10 CFR 73.1205(a)(1) through 10 CFR 73.1205(e), Written follow-up reports of physical security events, 10 CFR 73.1210(a)(1) through10 CFR 73.1210(h), Recordkeeping of physical security events, and 10 CFR 73.1215(a) through 10 CFR 73.1215(f), Suspicious activity reports.
In Reference 2, the Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI) and requested that TVA respond no later than March 15, 2024. As part of the Reference 2 RAI, the NRC provided TVA the option of revising the Reference 1 exemption U.S. Nuclear Regulatory Commission CNL-24-026 Page 2 March 14, 2024
request. Therefore, Enclosure 1 to this letter provides the TVA response to the RAI and provides the revised TVA Browns Ferry Nuclear Plant Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation. Enclosure 2 replaces the Reference 1 exemption request in its entirety and includes revision bars to facilitate review of the changes.
There are no new regulatory commitments in this letter. Please address any questions regarding this submittal to Stuart L. Rymer, Senior Manager, Fleet Licensing, at slrymer@tva.gov.
Respectfully,
Kimberly D. Hulvey Director, Nuclear Regulatory Affairs
Enclosures:
- 1. TVA Response to Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule
- 2. Revised TVA Browns Ferry Nuclear Plant Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant
Enclosure 1
TVA Response to Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule
CNL-24-026 Enclosure 1
=
Background===
By letter dated December 21, 2023, Tennessee Valley Authority (TVA) requested an exemption for the Browns Ferry Nuclear Plant, Units 1, 2, and 3, and the independent spent fuel storage installation (ML23355A206). In particular, TVA requested an exemption from using the definitions for Contraband and Time of Disco very, until the implementation date of rulemaking to disposition the underlying technical issues for these definitions.
Technical Basis for Request
In the exemption request, TVA stated that the new definition for Time of Discovery expands the pool of personnel previously used by licensees to determine T=0 for an event, and that because of this, TVA will be required to expand its current security programs to incorporate expanded and revised training modules for general plant employees and implementation of the expanded training across a broad spectrum of personnel at the station. TVA also expressed a desire to not have to train personnel twice -- once to come into compliance with its own interpretation of the final rule (without the benefit of the additional guidance being developed by NRC), and again once the additional guidance is issued. However, TVA did not provide an estimated timeframe for how long it would take to complete the revisions to its security programs and complete the training (e.g., 300 days after publication of final regulatory guidance). Additionally, the TVA exemption request for Time of Discovery was tied to a future rulemaking that may not include a change for this term.
Request
Provide additional justification for delaying im plementation of the definition for Time of Discovery until the implementation date of a potential rule revising certain provisions in the current 10 CFR Part 73. Include information regarding the expected time needed to revise the security programs, procedures, and training for personnel in order to support TVAs requested duration for the exemption. Additionally, explain why TVA cannot comply with the definition for Time of Discovery until the 10 CFR Part 73 rule is revised. As an alternative, TVA may revise its exemption request relative to implementation date for the definition of Time of Discovery.
TVA Response to RAI
As a result of the Nuclear Regulatory Commission request for additional information, TVA has elected to revise the Browns Ferry Nuclear Plant (BFN) exemption request relative to the implementation date for the term Time of Discovery. The revised BFN request proposes exemption from the definition of the term "Time of Discovery" as recently added to 10 CFR 73.2 until December 31, 2024, or 300 days after publication of the applicable Regulatory Guides, whichever is later. BFN will continue to apply the definition of the term "Time of Discovery" as provided in Regulatory Guide 5.76, Revision 1, "Physical Protection Programs at Nuclear Power Reactors," and in the BFN physical security programs, procedures, and training for personnel until that time. The remainder of the exemption request remains unchanged.
The revised BFN exemption request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation is provided in Enclosure 2.
CNL-24-026 E1 1 of 1 Enclosure 2
Revised TVA Browns Ferry Nuclear Plant Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
CNL-24-026 Enclosure 2
Revised TVA Browns Ferry Nuclear Plant Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
BACKGROUND
On March 14, 2023, the Nuclear Regulatory Commission (NRC) issued a Final Rule entitled Enhanced Weapons, Firearms Background Checks, and Security Event Notifications. 1 This final rule became effective April 13, 2023, with a compliance date of January 8, 2024. The final rule contains several new elements such as:
New terminology and associated requirements covering conditions adverse to security New definitions of the terms contraband and time of discovery in 10 CFR 73.2 New point of contact requirements with the Federal Aviation Administration (FAA)
Changes reporting requirements applicable to security events from:
o 1-hour notifications and 24-hour recording of security events, to 1-hour, 4-hour, 8-hour notifications and 24-hour recording of security events.
o Codifies the accelerated call to the NRC from NRC Bulletin 2005-02 to a new 15-minute notification.
Concurrently with the publication of the final rule, the NRC issued the following Regulatory Guides to support the implementation requirements set forth in the final rule:
5.62, Physical Security Event Notifications, Reports, and Records, Revision 2 5.86, Preemption Authority, Enhanced Weapons Authority, and Firearms Background Checks, Revision 0 5.87, Suspicious Activity Reports Under 10 CFR Part 73, Revision 0
During the May and August 2023, public workshops, the NRC recognized there are ambiguities and inconsistencies contained by the final rule language and associated guidance. The discussed revision date for clarifying guidance publication was April 2024, which is 3 months after the compliance date of January 8, 2024. Additionally, the NRC recognized the need for rulemaking to address the issues with the final rule language.
On December 5, 2023, NRC issued Enforcement Guidance Memorandum (EGM) 23-001 (Reference 2), Interim Guidance for Dispositioning Violations Associated with the Enhanced Weapons, Firearms Background Checks, and Security Event Notification Rule. As discussed in the EGM, following publication of the rule in March 2023 and subsequent public workshops, rule language was identified that created implementation challenges. It was also identified that aspects of the regulatory guidance associated with the rule warranted clarification. Based on the implementation challenges created by the above issues, it was noted that additional time might be needed for licensees to implement the rule and that exemption requests would be pursued for the rule compliance date.
Accordingly, Browns Ferry Nuclear Plant (BFN) is requesting an exemption from the specific requirements in 10 CFR Part 73, Subpart T, "Security Notifications, Reports, and Recordkeeping," 10 CFR 73.1200(a) through 10 CFR 73.1200(t), "Notification of physical security events," 10 CFR 73.1205(a)(1) through 10 CFR 73.1205(e), "Written follow-up reports of physical security events," 10 CFR 73.1210(a)(1) through10 CFR 73.1210(h), "Recordkeeping
1 Enhanced Weapons, Firearms Background Checks, and Security Event Notifications; Final rule and guidance, 88 Fed. Reg. 15864 (March 14, 2023).
CNL-24-026 E2 1 of 9 Enclosure 2
of physical security events," and 10 CFR 73.1215(a) through 10 CFR 73.1215(f), "Suspicious activity reports," until December 31, 2024, or 300 days after publication of the final Regulatory Guides, whichever is later.
BFN is requesting a new compliance date of December 31, 2024, or 300 days after publication of final Regulatory Guides, whichever is later. The 300-day period is consistent with the initial implementation period associated with the March 2023 publication of the rule and guidance documents. The 300-day period also provides adequate time for TVA to revise the corresponding procedures and implement the c hange management process, including training per the established training cycles, once the NRC publishes the revised Regulatory Guides.
BFN is requesting an exemption from using the definition of the term "Time of Discovery" as recently added to 10 CFR 73.2 until December 31, 2024, or 300 days after publication of the applicable Regulatory Guides, whichever is later. BFN will continue to apply the definition of the term "Time of Discovery" in Regulatory Guide 5.76, Revision 1, "Physical Protection Programs at Nuclear Power Reactors," and in the BFN physical security programs, procedures, and training until that time.
BFN is requesting an exemption from using the definition for the term Contraband, as recently added to 10 CFR 73.2, Definitions, until the implementation date of rulemaking to disposition the underlying technical issues with this definition. BFN will continue to apply the definition of the term Contraband in Regulatory Guide 5.76, Revision 1, Physical Protection Programs at Nuclear Power Reactors, and in the BFN physical security plans and procedures.
BFN is not requesting an extension to the compliance date for specific requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 73, Subpart B, Enhanced Weapons, Preemption, and Firearms Background Checks, described in 10 CFR 73.15, Authorization for Use of Enhanced Weapons and Preemption of Firearms Laws, and 10 CFR 73.17, Firearm Background Checks for Armed Security Personnel, as these requirements are not applicable to BFN.
Basis for Exemption Request
10 CFR 73.5 allows the Commission to grant exemptions from the requirements of Part 73 as it determines are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. As explained below, this exemption request meets the criteria provided in section 73.5.
BFN has identified several issues in the final rule and the supporting Regulatory Guides that require clarification from the NRC in order for BF N to successfully implement the requirements.
As mentioned above, the NRC is currently devel oping a resolution for code language issues and addressing guidance revisions. The NRC plans to issue additional guidance in April 2024, three months after the compliance date of January 8, 2024. Without additional guidance and the approval of this exemption, it is likely that BFN would need to make changes to its physical security plans and processes twice - once to come into compliance with its own interpretation of the final rule (without the benefit of the additional guidance being developed by NRC), and again once the additional guidance is issued. The ambi guity and conflict created by the final rule language and existing guidance, which is described below, could result in unnecessary confusion and distraction that detract from the current high level of assurance provided by BFNs existing physical security program. Thus, implementation of the final rule prior to issuance of additional clarifying guidance, at a minimum, is not in the best interest of the public.
The following are several issues that have been identified as examples:
CNL-24-026 E2 2 of 9 Enclosure 2
- 1. CONDITIONS ADVERSE TO SECURITY
The introduction of the term conditions adverse to security within 10 CFR 73.1210 is undefined, and ambiguous. BFN has established, as required, a formal Corrective Action Program in accordance with 10 CFR Part 50 Appendix B, Criterion XVI. Nuclear Energy Institute (NEI) 16-07, Improving the Effectiveness of Issue Resolution to Enhance Safety and Efficiency, provided recommended approaches to the industry to enhance corrective actions, and facilitate a better organizational focus on conditions affecting safety and reliability. As a result, BFN has developed procedures/processes to determine conditions adverse to quality as it relates to the security organization.
Procedure NPG-SPP-22.300, Corrective Action Program, defines specific events, situations or occurrences that result in a condition adverse to quality.
Security-related items are included.
Given the robust nature of the Corrective Action Program, the additional duplication of procedures and/or revision of procedures to accommodate a new term is unnecessary, adds burden, and provides no increased value, safety margin or improvements to security programs or the Corrective Action Program.
- 2. DEFINITIONS IN 10 CFR 73.2
New definitions in § 73.2 expand existing definit ions provided in NRC endorsed, NEI 03-12, Template for the Security Plan, Training and Q ualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 7 and RG 5.76, Physical Protection Programs at Nuclear Power Reactors. BFN has used the existing definitions to design its Security Plan and associated programs and procedures. Examples of the issues include:
Contraband: Specifically, the exempli gratia or e.g. parenthetical describing other dangerous materials as specifically including disease causing agents requires licensees to protect against circumstances beyond the current Design Basis Threat (DBT) as described in 10 CFR 73.1. The application of this expanded definition will require changes to BFNs methods of compliance with the requirements of 10 CFR 73.55(g)(1)(ii)(B). Paragraphs (g)(1)(ii)(B) requires (emphasis added):
§ 73.55(g) Access controls.
(1) Consistent with the function of each barrier or barrier system, the licensee shall control personnel, vehicle, and material access, as applicable, at each access control point in accordance with the physical protection program design requirements of § 73.55(b).
(ii) Where vehicle barriers are established, the licensee shall:
(B) Search vehicles and materials for contraband or other items which could be used to commit radiological sabotage in accordance with paragraph (h) of this section.
CNL-24-026 E2 3 of 9 Enclosure 2
§ 73.55(h) Search programs.
(1) The objective of the search program is to detect, deter, and prevent the introduction of firearms, explosives, incendiary devices, or other items which could be used to commit radiological sabotage. To accomplish this the licensee shall search individuals, vehicles, and materials consistent with the physical protection program design requirements in paragraph (b) of this section, and the function to be performed at each access control point or portal before granting access.
(2) Owner controlled area searches.
(iv) Vehicle searches must be accomplished through the use of equipment capable of detecting firearms, explosives, incendiary devices, or other items which could be used to commit radiological sabotage, or through visual and physical searches, or both, to ensure that all items are identified before granting access.
(3) Protected area searches. Licensees shall search all personnel, vehicles and materials requesting access to protected areas.
(i) The search for firearms, explosives, incendiary devices, or other items which could be used to commit radiological sabotage shall be accomplished through the use of equipment capable of detecting these items, or through visual and physical searches, or both, to ensure that all items are clearly identified before granting access to protected areas. The licensee shall subject all persons except official Federal, state, and local law enforcement personnel on official duty to these searches upon entry to the protected area. Armed security officers who are on duty and have exited the protected area may re-enter the protected area without being searched for firearms.
§ 73.55(g) uses the term contraband, while § 73.55(h) uses terminology consistent with that found in the definition of contraband in NEI 03-12 (and RG 5.76). The specific inclusion of disease causing agents in the new regulatory definition of contraband will require BFN to modify its programs and procedures describing the methods of compliance with paragraph
§ 73.55(g). BFN understands that the NRC is looking at potential resolutions for this issue, but until rulemaking occurs, BFN is unable to come into compliance with this requirement as written without making significant changes to its physical security program.
Time of Discovery: Specifically, the term cognizant individual and is considered anyone who, by position, experience, and/or training, is expected to understand that a particular condition or event adversely impacts security.
Currently, security plans incorporate the definition for Time of Discovery, that is found in NEI 03-12 and RG 5.76, being a supervisor or manager makes a determination that a verified degradation of a security safeguards measure or a contingency situation exists, to establish T=0 for a security related event.
The new definition expands the pool of personnel previously used by licensees to determine T=0 for an event, due to the undefined nature of position, experience, and/or training.
Additionally, the broader nature and lower threshold for recognition of something that simply adversely impacts security, versus recognition of verified degradation of a security safeguards
CNL-24-026 E2 4 of 9 Enclosure 2
measure or a contingency situation contributes to the expansion of pool of personnel. BFN is confident, the definition of the term in NEI 03-12 and RG 5.76, is the appropriate threshold for T=0 for security related events. The application of this expanded definition will require BFN to expand current security programs to incorporate the expanded and revised training modules onsite for general plant employees, (potentially with INPO and the NANTeL course they facilitate), and the responsibility for implementation of the expanded training across a broad spectrum of personnel at the station.
- 3. FEDERAL AVIATION ADMINISTRATION (FAA) LOCAL CONTROL TOWER POINT OF CONTACT
10 CFR 73.1215 establishes reporting requirements for suspicious activities involving aircraft to a licensees FAA local control tower. Specifically, licensees are required to:
Establish a point of contact with their local FAA control tower, and Document the point of contact in written communication procedures.
The code language is very specific in regard to establishing a point of contact with the local control tower. Based on current documentation, BFN has direction to contact FAA points of contact other than a local control tower depending on the day and time of day.
The requirement of establishing and documenting a FAA local control tower point of contact does not add additional safety margin to the protection or operation of BFN and adds difficulty for compliance due to the lack of participation from our local control tower.
- 4. REGULATORY GUIDES
Examples of clarification needed in the supporting Regulatory Guide 5.62, Revision 2, Physical Security Event Notifications, Reports, and Records include:
4-hour vs. 15-minute notification requirement:
§ 73.1200(e)(1)(iii) and (iv) requires a 4-hour notification for contraband attempted or actual introduction of contraband into a Protected Area (PA),
Vital Area (VA), or Material Access Area (MAA).
o The definition of contraband contains the term incendiaries.
§ 73.1200(a) required a 15-minute notification for hostile actions.
o RG 5.62, Rev 2, Section 7.1, page 24, provides examples of hostile actions:
(4) The discovery of unauthorized explosive materials, incendiary materials, or an improvised explosive device within the licensees site boundary.
The code language requires a 4-hour notification for an incendiary device at or inside the PA, VA, or MAA. The regulatory guide drives licensee to a 15-minute notification for an incendiary device at the site boundary, which is further away from safety related equipment.
The notification conflict the regulatory guide introduced between a 15-minute and 4-hour notification is burdensome, confusing, and makes the consistency and success for this notification unpredictable. Station personnel routinely reference published Regulatory
CNL-24-026 E2 5 of 9 Enclosure 2
Guides and other guidance documents, as a best practice, when implementing station procedures to support the accuracy of determination of notification events.
The inconsistency created by RG 5.62 unnecessarily creates the potential for confusion and human performance error.
4-hour notification vs. 24-hour recording of lost or uncontrolled weapon:
§ 73.1200(e)(1)(v) requires a 4-hour notification for a lost or uncontrolled weapon.
§ 73.1210(f) requires recording within 24-hours physical security events or conditions that decreases the effectiveness of the physical security program.
o RG 5.62, Rev 2, Section 18.2, page 38, provides examples of the Recordable Events and Conditions Regarding Decreases in Effectiveness, that 73.1210(f) requires. The regulatory guide includes an event involving the loss of control of an authorized security weapon within a PA, VA, MAA, or Controlled Access Area (CAA).
The conflict between the notification and recording of a lost or uncontrolled weapon only exists because of the regulatory guidance in RG 5.62. As a best practice, and to support accurate determination of notification events, station personnel are trained in referencing published Regulatory Guides, station procedures and guidance, and other industry documents. Additional clarity is needed in order to support the implementation of notifications and recordkeeping in a consistent and successful manner.
Malevolent intent discussion:
10 CFR 73.1200 only refers to the term malevolent intent in
§ 73.1200(q)(2) as exempli gratia or e.g. parenthetical describing a circumstance where a licensee may desir e to retract a previous physical security event notification.
o RG 5.62, Rev 2, Section 2, page 21, titled, Malevolent Intent and Credible Bomb Threat Considerations, states the NRCs position that only government officials have the necessary resources and qualifications to determine whether malevolent intent was present in a security event.
o During the May 2023, and August 2023, public meetings, the NRC was unable to consistently describe when licensees were capable of this determination, and when licensees were required to have government officials make this determination.
o Within the NRC Response to Public Comments, ML16264A004, 2 comment K-21 contains the discussion regarding credible, and puts into context, the circumstances of the NRCs position, as it relates to the determination of malevolent intent.
It is clear, that as of the publication date of March 2023, the discussion revolves around the 15-minute notification
2 NRC Response to Public Comments, Enhanced Weapons, Firearms Background Checks, and Security Event notifications Rule, NRC-2011-0018; RIN 3150-AI49
CNL-24-026 E2 6 of 9 Enclosure 2
requirements, and not blanketly across all security related events.
BFN is aligned that in certain circumstances, external government agencies would be the most appropriate to determine malevolent intent, (e.g., credible bomb threat, credible threat). However, BFNs position on the capability to determine intent as it relates to identifying Human Performance errors, as well as determining Trustworthy and Reliability for Access purposes remains with BFN.
The lack of clarity of the scope and/or intent of when it is appropriate for external government officials to determine malevolent intent creates ambiguity. Final clarity is needed to prevent BFN having to unnecessarily change security programs and procedures, such as access authorization, to incorporate a process to await investigation results from a Federal, State, or local law enforcement agency.
Considerations for Exemption
As highlighted in the selected examples above, BFN moving towards a compliance date of January 8, 2024, without full clarity on key parts of the final rule, would result in an inadequate implementation. Unknown success path towards co mpliance of the final rule, as written, in current code language; along with the conflict and confusion the published, publicly available, stated positions of the NRC, are key elements for this request. BFN would find themselves in a situation where the modification to security plans and procedures would be required at least twice, based on interpretation of this new rule. BFN is requesting the following considerations be taken into account during review of this request:
BFNs current site security plan implements the requirements of 10 CFR 73.71, Reporting of Safeguards Events for reporting the suspension of security measures.
BFN will continue to comply with security event reporting, as previously required in 10 CFR 73.71, Reporting of Safeguards Events and Appendix G to Part 73, Reportable Safeguards Events.
BFN will use the definitions for the terms "Contraband" and "Discovery (time of)," in its current site Security Plan consistent with how these terms are currently defined in Regulatory Guide 5.76, Revision 1, "Physical Protection Programs at Nuclear Power Reactors."
BFN is currently implementing a formal Corrective Action Program and has identified Conditions Adverse to Quality as they relate to Security Programs.
BFN can currently contact the FAA, in general, at various numbers depending on the day and time of day.
BFN is currently capable of making voluntary reports of suspicious activities, and this will not change in the interim until the new compliance date and allow for final revised regulatory guidance issuance.
The burden associated with rework for BFN is unnecessary while awaiting final clarity with publication of associated Regulatory Guides. Several examples of where rework will be required are:
o Revisions of associated procedures/processes, job aids, training materials and lesson plans that are used to describe and elaborate on reporting requirements.
o Coordination of work management and resources to align with station outage schedule(s).
CNL-24-026 E2 7 of 9 Enclosure 2
o The re-training of impacted station personnel with updated information contained within the revised guidance documents:
Security - BFN Security conducts training on a trimester basis, typically in January, May and September. If guidance is made available in April 2024, the earliest security training would be conducted (allowing time for modification of procedures and associated training material) would be September. However, if guidance is not published until later in the year then security training would likely not begin until January 2025.
Regulatory/Compliance Emergency Response Radiation Protection Operations - Accredited Training Program, requiring the use of the Systematic Approach to Training process. Examples of elements that drive the number of available weeks to train operators within a year are:
BFN executes six cycles of requalification training per year.
BFN requires six weeks for each cycle of training, based on the number of operating crews, and licensed operators we have.
BFN is required to administer an exam cycle for our licensed operators each year.
BFN is required to incorporate certain elements within our 2-year training cycle, that include outage applicable objectives, (including, but not limited to: core changes, plant modifications, Lower Mode operations).
Justification for Exemption
BFN is requesting an exemption from the specific requirements in 10 CFR Part 73, Subpart T, Security Notifications, Reports, and Recordkeeping, 10 CFR 73.1200(a) through 10 CFR 73.1200(t), Notification of physical security events, 10 CFR 73.1205(a)(1) through 10 CFR 73.1205(e), Written follow-up reports of physical security events, 10 CFR 73.1210(a)(1) through10 CFR 73.1210(h), Recordkeeping of physical security events, and 10 CFR 73.1215(a) through 10 CFR 73.1215(f), Suspicious activity reports, until of December 31, 2024, or 300 days after publication of the final Regulatory Guides, whichever is later.
BFN is requesting a new compliance date of December 31, 2024, or 300 days after publication of final Regulatory Guides, whichever is later. The 300-day period is consistent with the initial implementation period associated with the March 2023 publication of the rule and guidance documents. The 300-day period also provides adequate time for TVA to revise the corresponding procedures and implement the c hange management process, including training per the established training cycles, once the NRC publishes the revised Regulatory Guides.
BFN is requesting an exemption from using the definition of the term "Time of Discovery" as recently added to 10 CFR 73.2 until December 31, 2024, or 300 days after publication of the final Regulatory Guides, whichever is later. BFN will continue to apply the definition of the term "Time of Discovery" in Regulatory Guide 5.76, Revision 1, "Physical Protection Programs at Nuclear Power Reactors," and in the BFN physical security programs, procedures, and training until that time.
CNL-24-026 E2 8 of 9 Enclosure 2
BFN is requesting an exemption from using the definition for the term Contraband, as recently added to 10 CFR 73.2, Definitions, until the implementation date of rulemaking to disposition the underlying technical issues with this definition. BFN will continue to apply the definition of the term Contraband in Regulatory Guide 5.76, Revision 1, Physical Protection Programs at Nuclear Power Reactors, and in the BFN physical security plans and procedures.
As stated above, BFN will continue to implement the Security Plan as documented. Because it has been reviewed and approved by the NRC, the BFNs Security Plan provides reasonable assurance of safety and security. The delay in implementation of the final rule will not impact proper implementation of the current Security Plan and will ensure that the final rule is effectively implemented. Thus, granting of this exemption will not endanger the life or property or common defense and security.
Implementation of the final rule without further interface, clarity, and refined guidance may result in unintended consequences which could reduce the effectiveness of the current Security Plan.
Therefore, it is in the publics interest that BFNs Security Plan and associated procedures/processes comprehensively and accurately implement the regulation and guidance documents once resolution is obtained of identified issues.
The granting of this exemption would not violate the Atomic Energy Act (AEA), as the compliance date for the final rule is not required nor specified in the AEA as amended, any provisions of the Commissions regulations, or any other legally binding requirements imposed by the Commission.
Thus, issuance of this exemption request would be consistent with 10 CFR 73.5 because it is authorized by law and will not endanger life or property or the common defense and security and [is] otherwise in the public interest.
Environmental Assessment
BFN is requesting an exemption from the specific requirements for the 2023 Security Rule, "Enhanced Weapons, Firearms Background Checks, and Security Event Notifications," effective as of April 13, 2023. The following information is provided in support of an environmental assessment and finding of no significant impact for the proposed exemption. BFN has determined that the exemption involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite; that there is no significant increase in individual or cumulative public or occupational radiation exposure; that there is no construction impact; and there is no significant increase in the potential for or consequences from a radiological accident. Accordingly, the proposed one-time exemption meets the eligibility criteria for categorical ex clusion set forth in 10 CFR 51.22(c)(25). Pursuant to 10 CFR 51.22(b), no environmental impact st atement or environmental assessment need be prepared in connection with the issuance of this proposed exemption request.
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