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Category:Exemption from NRC Requirements
MONTHYEARML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1382024-07-16016 July 2024 Exemption from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - FRN ML24172A1352024-07-15015 July 2024 Exemption ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24172A1372024-07-15015 July 2024 Exemption ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML20343A3632020-12-15015 December 2020 Exemption from Annual Force-on-Force Exercise Requirement of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Subsection VI.C.3(I)(1) (EPID L-2020-LLE-0233 (COVID-19)) CNL-20-095, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force Exercises, Due to COVID-19 Pandemic2020-12-0808 December 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force Exercises, Due to COVID-19 Pandemic ML20175A1982020-07-0606 July 2020 Exemption Request from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria from Security Personnel, Section VI CNL-20-050, CNL-20-050 BFN Exemption to Annual Force-on-Force Drill Via Email2020-06-19019 June 2020 CNL-20-050 BFN Exemption to Annual Force-on-Force Drill Via Email NRC-2010-0030, FRN: General Notice. Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Federal Register Notice - Exemption from the Requirements of 10 CFR Part 73, Section 73.55 (TAC Nos. ME2595, ME2596, and ME2597)2010-03-11011 March 2010 FRN: General Notice. Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Federal Register Notice - Exemption from the Requirements of 10 CFR Part 73, Section 73.55 (TAC Nos. ME2595, ME2596, and ME2597) ML1000507372010-03-11011 March 2010 FRN: General Notice. Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Federal Register Notice - Exemption from the Requirements of 10 CFR Part 73, Section 73.55 ML1000507362010-03-11011 March 2010 Exemption from the Requirements of 10 CFR Part 73, Section 73.55 ML0903301732009-01-27027 January 2009 Proposed Request for Exemption from 10 CFR 50, Appendix R, Paragraph III.G.2, Fire Protection of Safe Shutdown Capacity ML0705900632007-03-29029 March 2007 Exemption from the Requirements of 10 CFR Part 50.48 and Appendix R ML0622601412006-09-26026 September 2006 Exemption, 10 CFR Part 60, Appendix J - MSIV Leakage ML0419802222004-07-0909 July 2004 Technical Specification 436 - Increased Main Steam Isolation Valve Leakage Rate Limits and Exemption from 10CFR50, Appendix J ML0320404832003-07-11011 July 2003 Exemption Request from the Requirements of 10 CFR 50 Appendix a General Design Criteria (GDC)-41 in Support of Technical Specifications Change (TS-405) - Alternative Source Term (AST) 2024-07-22
[Table view] Category:Letter type:CNL
MONTHYEARCNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement CNL-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-23-027, 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-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report 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-23-019, 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 2024-09-24
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-20-050 June 19, 2020 10 CFR 73.5 To: Michael Wentzel, Project Manager ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 cc: NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant 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, and 50-296
Subject:
Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request for Exemption from the Annual Force on Force Training Requirements of 10 CFR 73, Appendix B, Section VI, Due to the COVID-19 Public Health Emergency
Reference:
NRC Letter from H. Nieh and J. Lubinski to NEI, U.S. Nuclear Regulatory Commission Planned Actions Related to the Requirements for Part 73, Appendix B,Section VI During the Coronavirus Disease 2019 Public Health Emergency, dated April 20, 2020 On January 31, 2020, the U.S. Department of Health and Human Services declared a public health emergency (PHE) for the United States to aid the nations healthcare community in responding to the Coronavirus Disease 2019 (COVID-19). On March 13, 2020, the Governor of the State of Alabama declared a state of emergency. In addition, on March 11, 2020, the World Health Organization characterized the COVID-19 outbreak as a pandemic and, on March 13, 2020, the President of the United States of America declared the Coronavirus (COVID-19) pandemic a national emergency. In response to these declarations and in accordance with the Tennessee Valley Authority (TVA) corporate pandemic response plan, TVA has postponed some site activities due to isolation activities (for example, social distancing, group size limitations, self-quarantining, and so on) and also anticipates the possibility of isolation of required station personnel to maintain necessary staffing levels.
U. S. Nuclear Regulatory Commission CNL-20-050 Page 2 June 19, 2020 In accordance with the provisions of 10 CFR 73.5, and consistent with the conditions specified in the Enforcement Guidance Memorandum 20-002 and the Reference letter, TVA BFN is requesting temporary exemption from the requirements of Appendix B to Part 73,Section VI, C.3.(l)(1). As a result of the Coronavirus Disease 2019 (COVID-19) public health emergency (PHE), Tennessee Valley Authority (TVA), expects that Browns Ferry Nuclear Power Plant (BFN), Units 1, 2 and 3, will no longer be able to comply with the requirements of the specified regulation, and will implement site specific COVID-19 PHE training requalification controls consistent with those conditions outlined in the enclosure to the referenced letter.
This temporary exemption supports the isolation restrictions (e.g., social distancing, group size limitations, self-quarantining, etc.) necessary to protect required site personnel in response to the COVID-19 virus. These restrictions are needed to ensure personnel are isolated from the COVID-19 virus and remain capable of maintaining plant security. BFN implemented proactive isolation restrictions for site personnel on March 23, 2020.
This exemption is specific to security personnel who have previously demonstrated proficiency and are currently qualified in accordance with 10 CFR Part 73, Appendix B, Section VI, Nuclear Power Reactor Training and Qualification Plan for Personnel Performing Security Program Duties. Additionally, because of the rigorous nature of BFN security personnel training programs, which consists of regularly scheduled training activities to include weapons training, contingency response drills and exercises, and demonstrated acceptable performance of day-to-day job activities (for example, detection and assessment, patrols, searches, and defensive operations), it is reasonable to conclude that security personnel will continue to maintain their proficiency, even though the requalification periodicity is temporarily exceeded.
BFN requests a temporary exemption from the following specific force-on-force (FOF) exercise requirements of 10 CFR 73, Appendix B, VI.C.3.(l)(1):
Each member of each shift who is assigned duties and responsibilities required to implement the safeguards contingency plan and licensee protective strategy participates in at least one (1) tactical response drill on a quarterly basis and one (1) force-on-force exercise on an annual basis.
BFN will implement the following controls to ensure impacted security personnel maintain the knowledge, skills, and abilities required to effectively perform assigned duties and responsibilities:
BFN will maintain a list of the names of the individuals who will not meet the requalification requirements and will include the dates of the last qualification.
BFN will ensure contingency response readiness of security personnel not participating in an annual FOF exercise, by conducting the following scenario-based evolution:
o Continue to conduct quarterly tactical response drills, including tabletop exercises, to ensure the security force maintains response readiness.
U. S. Nuclear Regulatory Commission CNL-20-050 Page 3 June 19, 2020 The FOF annual exercise will be completed within 90 days after the PHE is ended or by December 31, 2020, whichever occurs first. However, should unforeseen circumstances arise that would inhibit resuming these activities, TVA will provide an updated request for exemption with as much advance notice as practicable.
BFN will begin implementing its site-specific COVID-19 PHE controls for managing personnel performing Security Program duties at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Eastern Daylight Time (EDT) on July 15, 2020, which is when the annual exercise grace period expires.
Part 73.5 of 10 CFR, Specific exemptions, states that the NRC may grant exemptions from the requirements of the regulations of this part provided three conditions are met. They are:
(1) The exemptions are authorized by law, (2) The exemptions will not endanger life or property or the common defense and security, and (3) The exemptions are otherwise in the public interest.
TVA has evaluated the requested exemption against the criteria of 10 CFR 73.5 and determined the criteria are satisfied as described below.
- 1. This exemption is authorized by law.
The requested exemption is authorized by law in that no law precludes the activities covered by this exemption request. Granting of the request does not result in a violation of the Atomic Energy Act of 1954, as amended.
- 2. This exemption will not endanger life or property or the common defense and security.
The requested exemption will not endanger life or property or the common defense and security. The requested exemption is a one-time exemption to allow deferring of security training requalification requirements. TVA had scheduled these requalification activities to comply with the regulation. However, these activities must be rescheduled to allow implementation of the TVA pandemic plan mitigation strategies. These strategies serve the public interest by ensuring adequate staff isolation and maintaining staff health to perform their job function actions during the COVID-19 pandemic.
The proposed exemption is related to training requalification and does not change physical security plans or the defensive strategy. Security personnel impacted by this exemption are currently satisfactorily qualified on all required tasks. In addition, security personnel are monitored regularly by supervisory personnel and have implemented controls as identified above. Therefore, granting the requested temporary one-time exemption will not endanger or compromise the common defense or security, or safeguarding of BFN.
- 3. This exemption is otherwise in the public interest.
U. S. Nuclear Regulatory Commission CNL-20-050 Page 4 June 19, 2020 The TVA pandemic response plan is based on NEI 06-03, Nuclear Sector Coordination Council, Influenza Pandemic Threat Summary and Planning, Preparation, and Response Reference Guide, which recommends isolation strategies such as sequestering, use of super crews or minimum staffing as well as social distancing, group size limitations and self-quarantining, in the event of a pandemic, to prevent the spread of the virus to the plant.
NEI 06-03 provides other mitigation strategies that serve the public interest during a pandemic by ensuring adequate staff is isolated from the pandemic and remains healthy to perform their job function.
Keeping BFN in operation during the pandemic will help to support the public need for reliable electricity supply to cope with the pandemic. As the US Departments of Homeland Security and Energy have stated in their guidance, the electric grid and nuclear plant operation make up the nation's critical infrastructure similar to the medical, food, communications, and other critical industries. If the plant operation is impacted because it cannot comply with the security training requalification requirements while isolation activities are in effect for essential crew members, the area electrical grid would lose this reliable source of baseload power. In addition, BFN personnel could face the added transient challenge of shutting down their respective plant and possibly not restarting it until the pandemic passes. This does not serve the public interest in maintaining a safe and reliable supply of electricity.
TVA 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. Furthermore, the requirements for which an exemption is being requested involve security training requalification requirements.
Accordingly, the proposed exemption meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(25). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this proposed exemption request.
The period during which the exemption is necessary is not currently known, but will be in effect until 90 days after the PHE is ended, or until December 31, 2020, whichever occurs first.
There are no new regulatory commitments associated with this submittal. Please address any questions regarding this request to Gordon Williams, Senior Manager, Fleet Licensing (Acting) at 423-751-2687.
Respectfully, Kimberly D. Hulvey Director, Nuclear Regulatory Affairs (Acting) cc: See Page 1