ML24304A982
| ML24304A982 | |
| Person / Time | |
|---|---|
| Issue date: | 10/30/2024 |
| From: | Leach T NRC/NSIR/DPCP/RPPB |
| To: | |
| References | |
| ML24304A980 | |
| Download: ML24304A982 (21) | |
Text
1 Travis Ryan Leach Security Specialist, Reactor Physical Protection Branch Office of Nuclear Security and Incident Response
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Outline
3 Safety, Security, and Safeguards by Design Safety Prevent accidents or mitigation of accident consequences Protect workers, the public and the environment from undue radiation hazards Security Protect against malicious acts that could result in unacceptable radiological consequences, including the theft and diversion of radioactive material and radiological sabotage Safeguards Deterrence and timely detection of theft or diversion of special nuclear material to prevent misuse (Material Control and Accounting (MC&A)
4 Policy Statement on the Regulation of Advanced Reactors 73 FR 60612; October 14, 2008 Designs that include considerations for safety and security requirements together in the design process such that security issues (e.g., newly identified threats of terrorist attacks) can be effectively resolved through facility design and engineered security features, and formulation of mitigation measures, with reduced reliance on human actions.
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11 (ML24178A369)
Eliminates requirements for a minimum number of onsite armed responders to interdict and neutralize Design Basis Threat (DBT) adversary, (2) Law enforcement or other offsite responders can be used to interdict and neutralize the DBT adversary, (3) Allows for alternative means for accomplishing delay other than with physical barriers, (4) Allows for an offsite secondary alarm station, (5) Allows for removal of designation of offsite secondary alarm station or its secondary power supply as vital areas
12 Status: Sent out for Public Comment on October 31st with a 60-day comment period.
Guidance: DG-5075, Establishing Cybersecurity Programs for Commercial Nuclear Plants Licensed Under 10 CFR Part 53 (ML23286A278), DG-5076, Guidance for Technology Inclusive Requirements for Physical Protection of Licensed Activities at Commercial Nuclear Plants (ML23286A282)
Applicability: All new reactor licensees and types (would need to meet the requirements in the proposed new regulation 10 CFR 73.100 or the existing power reactor security rule). 10 CFR 53.860 would require the licensee to meet the cybersecurity requirements under parts 10 CFR 73.54 or 73.110.
13 Highlights:
Covers a broad range of technologies and source terms Performance-based, graded approach versus prescriptive requirements Includes physical security, cybersecurity, fitness for duty, and access authorization Leverages experience from research and test reactors, large light water reactors, fuel cycle facilities, CAT 1 facilities, and medical isotope facilities Proposes a class of reactors that would not be subject to the DBT Supports security by design through proposed 10 CFR 53.440 Considerations for risk-informed approaches to accommodate various advanced reactor technologies and designs (such as autonomous operation, remote operations, and remote monitoring)
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Title:
SECY-24-0008 (ML23207A250), Micro-reactor Licensing and Deployment Considerations:
Fuel Loading and Operational Testing at a Factory
Purpose:
Provides the Commission with options for regulating certain aspects of fuel loading and operational testing of commercial factory-fabricated micro-reactors. The NRC staff developed options related to three policy issues which micro-reactor developers have requested near-term clarity that will likely affect their proposed deployment models:
(1) the use of features to preclude criticality to determine whether a reactor is considered to be in operation, (2)the type of license(s) that would be required to enable loading fuel at a factory, and (3)licensing approaches to enable operational testing at a factory.
Status:
With the Commission for consideration
Mobile Micro-reactors Timeframe for Authorization to Operate Storage of Fuel after Irradiation Replacement of Factory Fabricated Modules Decommissioning Process Autonomous and Remote Operation Siting in Densely Populated Areas 15 Considerations: Enclosure 1 (ML23207A251) includes various topics related to the licensing and deployment of factory-fabricated micro-reactors as well as NRC staffs near-term strategies and next steps for addressing each topic Transportation of Fueled Factory Fabricated Modules Commercial Maritime Applications Other Considerations:
Nth of A Kind Standardization of Operational Programs (Security and EP)
16 Standardization of Operational Programs (Security and Emergency Preparedness) for Nth of a Kind (NOAK) Micro-reactors Maximal standardization:
Approval of a standardized micro-reactor design and subsequent deployment under a combined license or construction permit and operating license without any significant deviations or departures from the standardized design Maximal design standardization could allow micro-reactors of a common design to be deployed to most sites in the U.S. with minimal need for site-specific features or the associated additional NRC reviews and approvals
17 https://www.nrc.gov/about-nrc/governing-laws/advance-act.html
18 For NRCs public information site for ADVANCE Act updates Contact us with ADVANCE Act questions, comments and ideas
19 SECY Papers:
SECY-24-0008, Micro-reactor Licensing and Deployment Considerations: Fuel Loading and Operational Testing at a Factory (ML23207A250)
20 DGs for Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors (Part 53):
DG-5073, Fitness-For-Duty Programs for Commercial Nuclear Plants and Manufacturing Facilities Licensed Under 10 CFR Part 53 (ML23286A251)
DG-5074, Access Authorization Program for Commercial Nuclear Plants (ML23286A268)
DG-5075, Establishing Cybersecurity Programs for Commercial Nuclear Plants Licensed Under 10 CFR Part 53 (ML23286A278)
DG-5076, Guidance for Technology Inclusive Requirements for Physical Protection of Licensed Activities at Commercial Nuclear Plants (ML23286A282)
DG-5078, Fatigue Management for Nuclear Power Plant Personnel at Commercial Nuclear Plants Licensed Under 10 CFR Part 53 (ML23286A286)
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