ML23017A111

ACRS Presentation CNSC - U.S. NRC Cooperation on Advanced Reactor Technologies and Small Modular Reactors

ML23017A111
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Issue date:	01/11/2023
From:	Office of Nuclear Reactor Regulation
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Download: ML23017A111 (1)

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CNSC - U.S. NRC Cooperation on Advanced Reactor Technologies and Small Modular Reactors January 11, 2023

Outline

• Introduction

• Memorandum of Cooperation process

• First products

• Current work

• Future projects

Introduction

• Memorandum of Cooperation signed in 2019 to collaborate on reviews of designs submitted for review in the U.S. and Canada

• Goal - Collaborate on ART-SMR design reviews and share experience

• Benefits to CNSC and USNRC

• Effective and efficient regulation

• Risk-informed agile decision-making 3

Implementation of the MOC MOU Steering Committee MOC ART-SMR Subcommittee Work plans Working groups/ subject matter experts

Scope of Memorandum of Cooperation (MOC)

Scope of projects

• Pre-licensing engagement

• Licensing reviews

• Science and research Development of work plans Processes for collaboration

Joint NRC/CNSC Products Pre-licensing Engagement

• X-energy - Xe100 reactor pressure vessel construction code assessment

• GEH- BWRX-300 Containment Evaluation Method

• Terrestrial - postulated initiating events Review Approaches

• Report Comparting the U.S. LMP with the Canadian Approach Unique Technical Considerations

• TRISO fuel qualification

Lessons Learned and Improvements to the Collaboration Process Expansion to include UK/ONR Staff exchanges Strengthened communication to external stakeholders Upgrades to collaboration tools

Project Selection

• Request by vendors

• Criteria

• The extent to which the vendor is engaging in meaningful pre-licensing activity with each regulator

• The similarity between the vendors engagement activities in each country

• The timelines for engaging with each regulator

• The ability of the vendor to share information about their design with both regulators

Current Work Collaborative work plans underway Safety Classification of Structures, TRISO Fuel Systems and Qualification GEH BWRX-300 Components

Joint Review of GE Hitachis BWRX-300

• TVA, OPG, SaskPower independently selected the same technology (GE Hitachi's BWRX-300 design)

• NRC and CNSC are conducting collaborative reviews on specific technical topics Under the MOC

• Goal: Efficient and coordinated reviews resulting in common technical positions

• To date, NRC and CNSC have successfully collaborated and issued a joint report on BWRX-300 containment evaluation method.

CNSC-NRC MOC BWRX-300 Current Projects

• BWRX-300: Advanced construction techniques. The NRC and CNSC staff are reviewing a white paper on BWRX-300 Steel-Plate Composite (SC) Containment Vessel (SCCV) and Reactor Building Structural Design

• BWRX-300: Safety Strategy. The NRC and CNSC staff are reviewing a white paper on the Safety Strategy for BWRX-300.

The Safety Strategy incorporates selected guidance from the IAEA Safety Standards Specific Safety Requirements No. SSR-2/1, Revision 1, Safety of Nuclear Power Plants: Design.

• BWRX-300: fuel verification and validation. CNSC is leveraging previous USNRC reviews of the GNF2 fuel product in the CNSCs review of OPGs construction license application.

Next Steps

• Work with vendors and utilities to identify specific technical issues and perform joint reviews of topical reports and white papers in the pre-application phase

• Cooperate on the review of specific sections or topics in licensing applications.

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