Joint Reports of the Canadian Nuclear Safety Commission (CNSC) and the NRC
Project Overview
On August 15, 2019, the Canadian Nuclear Safety Commission (CNSC) and the United States Nuclear Regulatory Commission (USNRC), signed a Memorandum of Cooperation (MOC) to increase collaboration on the technical reviews of advanced reactor and small modular reactor technologies. Under the MOC, the NRC and CNSC plan to issue joint reports that cover topics that are generally applicable to advanced reactor developers and designers, as well as targeted reports addressing specific technical aspects for individual vendors or potential applicants. The following table provides brief descriptions and links to completed joint reports.
Joint Reports Issued by NRC and CNSC
| Joint Report Title and Summary |
Link |
| CNSC-NRC joint report concerning X-energy’s reactor pressure vessel construction code assessment white paper – This report documents the results of collaborative activities between the CNSC and the USNRC concerning X-energy’s position about the Xe-100 reactor pressure vessel construction code assessment. |
ML21166A304 |
CNSC-NRC joint report on technology-inclusive, risk-informed reviews for advanced reactors – This report documents the results of a broad overview of NRC and CNSC regulatory frameworks and provides a specific comparison of the licensing modernization project (LMP) endorsed in NRC Regulatory Guide 1.233 with the CNSC approach.
Key messages and FAQs associated with the LMP Report may be found at the following: ML21239A250 |
ML21225A101 |
|
CNSC-NRC Interim joint report on Tristructural Isotropic (TRISO) Fuel Qualification -
The first interim report specifically addresses (1) reactor technologies considered in the study, (2) the regulatory basis for advanced nuclear reactor fuel qualification in Canada and the United States, (3) known degradation mechanism and failure modes for TRISO fuel, and (4) transient behavior of TRISO fuel.
The second interim joint report incorporates the content of the first interim report and provides additional information on fuel manufacturing (including dimensions, constituents, and end-state attributes) and criteria for coolable geometry.
|
ML22030A000
ML22101A297
|
| CNSC-NRC joint report concerning GE Hitachi’s Containment Evaluation Method - This report documents the results of collaborative activities between the CNSC and the USNRC to assess a method for predicting the conditions inside the containment vessel following a loss-of-coolant accident for the GE Hitachi BWRX-300 reactor design. The method was proposed by GEH in the form of a licensing topical report. |
ML22091A201 |
| Joint Report on Terrestrial Energy’s Methodology for Developing a Postulated Initiating Events List for the Integral Molten Salt Reactor - This report documents the results of collaborative activities between the CNSC and the USNRC concerning Terrestrial Energy USA’s white paper on Postulated Initiating Events for its Integral Molten Salt Reactor. |
ML22139A124 |
Page Last Reviewed/Updated Tuesday, May 31, 2022