ML24277A286
| ML24277A286 | |
| Person / Time | |
|---|---|
| Issue date: | 10/03/2024 |
| From: | Hayes B NRC/NRR/DEX/EXHB |
| To: | |
| References | |
| Download: ML24277A286 (1) | |
Text
Technical Meeting on the Protection of Nuclear Installations Against External Hazards External Hazard 18th Plenary Meeting of the External Events Re v i e w a t t h e U. S. Safety Section Extrabudgetary Programme Nuclear Regulator y Commission
1 Table of Content
Operating Reactor History Parts 50 versus 52 licensing NTTF & POANHI Design centered review approach Current review needs in light of the ADVANCE Act
2 Operating Reactor Snapshot (as of 2023)
3 How we regulate Key for External Hazards Atomic Energy Act of 1954 Regulatory Guidance for National Environmental Policy Act of 1969Reactors L AW S Energy Reorganization Act of 1974
10 CFR Part 50 REGULATIONS 10 CFR Part 51 LAWS 10 CFR Part 52 10 CFR Part 100
Policy Statements GUIDANCE Standard Review Plans Regulatory Guides Interim Staff Guidance
4 NRC Regulations
- Licensing of new and advanced reactors available under 10 CFR Parts 50, 52, and 53 (in development).
- Key Regulation for External Hazards:
- 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 2, Design Bases for Protection Against Natural Phenomena, as it relates to consideration of the most severe of the natural phenomena that have been historically reported for the site and surrounding area, with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data have been accumulated.
- 10 CFR 52.79(a)(iii) requires a COL applicant to identify the most severe of the natural phenomena that have been historically reported for the site and surrounding area and with sufficient margin for the limited accuracy, quantity, and time in which the historical data have been accumulated.
5 10 CFR Part 50 (CP & OL)
6 NUREG/BR-0298, Rev 2 "Nuclear Power Plant Licensing Process" 7 Early Site Permits
( ES Ps)
White paper and topical report (for Standard Design both Parts 50 & Certification (SDCs) 52)
Additional New Reactor Licensing Pre-application Engagement on Manufacturing Site Suitability License (MLs)
Reviews
Standard Design Approval (SDAs)
8 10 CFR Part 52 Regulatory Process
COL DC FSAR ESP and ESP SSAR permissible site permissible design (10CFR 52.79 & 52.80) parameters parameters ESP COL FSAR site COL FSAR design
(10 CFR 52.17) characteristics characteristics
+ +
information on information on DC departures from DC variances from ESP and associated +
(10 CFR 52.47) exemptions
+ relevant COL action items if the COL COL action items references a DC, e.g.
verification of site parameters
9 Post-Fukushima Near -Term Task Force (NTTF)
Recommendation Activities NT TF Recommendation (R) 2.1 and R2.3 efforts were focused on ensuring that operating reactors were safe via walkdowns and flooding and seismic re-evaluations.
R2.2 advised rulemaking requiring that nuclear power plant licensees confirm seismic and flooding hazards every 10 years. Staff proposed to meet the intent of R2.2 by enhancing existing processes to ensure that staff proactively and routinely aggregates and assesses new natural hazard information.
Staff issued Office Instruction LICNatural Hazards Information, dated November 20, 2019, which provides the - 208, Process for Ongoing Assessment of framework for implementing POANHI.
Yhttps://www.nrc.gov/reactors/operating/opsou can find moreinformation on POANHI on USNRCs website at: - experience/poanhi.html.
10 POANHI (po.aan.hee)
An efficient internal process that leverages existing programs and agreements with external organizations to:
Ensure more timely identification and assessment of new information (e. g., data, models, and methods)
Facilitate a methodical assessment of the cumulative effect of new data, models, and methods that accrue over time Update existing hazard models with new information found to be significant so they are readily available.
Framework:
Knowledge Base Activities Active Technical Engagement and Coordination Assessment Activities
Scope: external flood-causing mechanisms; seismic hazards; high winds (tornado and hurricane);
snow/ice loads; extreme temperatures & humidity.
11 Current Siting Review Needs in line with the 2024 ADVANCE Act
The Accelerating Deployment of Versatile, Advanced Nuclear for Clean Energy Act Aims to accelerate nuclear reactor deployment in the U.S.
To achieve this, it's crucial to streamline the siting review process, especially considering external hazards.
Aligns with internal challenges and opportunities related to a recent increase of incoming applications with a wide variety of technologies and siting issues
Act Requirements Related to External Hazards:
Sec. 206. Regulatory issues for nuclear facilities at brownfield sites.
Assessing the licensing review process for new nuclear facilities at former fossil-fuel power plant sites and brownfield sites.
Sec. 207. Combined license review procedure.
Establishing an expedited procedure for reviewing qualifying new reactor license applications (COLs) within 18 months.
Sec. 208. Regulatory requirements for micro-reactors.
Risk-informed performance-based strategies and guidance
12 Climate Change
- USNRCs commitment to Safety Staying abreast of new climate change information The NRC addresses climate related safety concerns
- For power plants, staff evaluates changing through rigorous licensing and oversight processes natural hazard information, including climate by change to determine whether the NRC
- incorporating safety margins in designs, needs to revise the licensing basis
- implementing measures to prevent radioactive throughout the plants lifetime.
releases in case of hazard-induced events beyond design limits, and
- ensuring the availability of backup equipment
- Staff is currently reviewing the recently essential for safety functions. released Fifth National Climate Assessment (NCA5) under POANHI to help to identify The NRC applies principles of conservatism, safety potential gaps in NRCs licensing and margins, and defense-in -depth across all phases of oversight processes with respect to climate nuclear facilities lifecycle from design and change.
construction to operation and decommissioning.
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