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

Pre-licensing Engagement X-energy - Xe100 reactor pressure vessel construction code assessment

• GEH-BWRX-300 Containment Evaluation Method

• Terrestrial - postulated initiating events Joint NRC/CNSC Products Unique Technical Considerations TRISO fuel qualification Review Approaches Report Comparting the U.S. LMP with the Canadian Approach

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

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 GEH BWRX-300 TRISO Fuel Qualification Safety Classification of Structures, Systems and 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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