The purpose of this regulatory document is to specify the detailed requirements and provide guidance pertinent to the certification of the reactor facility workers employed or seeking employment in designated positions

The purpose of this regulatory document is to assist Class I nuclear facility licensees and applicants for a Class I nuclear facility licence to demonstrate to the CNSC that they will ensure the presence of a sufficient number of qualified workers to carry on the licensed activity safely and in accordance with the Nuclear Safety and Control Act (NSCA, the Act) [1], the regulations made under the NSCA, and their licence.

This regulatory document sets out the CNSC’s requirements for the conduct of a PSR. Guidance is also provided on how these requirements may be met.

This regulatory document sets out the requirements of the Canadian Nuclear Safety Commission (CNSC) for deterministic safety analysis for nuclear power plants (NPPs) and small reactor facilities.

This regulatory document sets out the requirements of the Canadian Nuclear Safety Commission (CNSC) with regard to maintenance programs for nuclear power plants (NPPs). This document also provides information and guidance on how the requirements may be met. When incorporated into a licence or other legally enforceable instrument, this regulatory document becomes a legal requirement.

This document describes the pre-licensing review process provided by the CNSC for assessing a vendor’s reactor design. The review considers the areas of design that relate to reactor safety, security and safeguards.

Regulatory document REGDOC-2.3.4, Operations Programs for Reactor Facilities, clarifies the requirements for, and provides guidance on, developing and implementing operations programs for reactor facilities (nuclear power plants, advanced reactor designs and small modular reactors). This regulatory document is based on operational experience (OPEX) and best practices developed from water-cooled nuclear power plants. This information will be updated as additional information is gathered from advanced reactor designs and small modular reactors. Proponents, applicants and licensees of advanced reactor designs and small modular reactors should apply the information and concepts from this regulatory document to the extent practicable and as best applicable to that design.

This licence application guide clarifies the requirements for and provides guidance on applying to the Canadian Nuclear Safety Commission (CNSC) for a licence to construct a reactor facility. Following the information in this regulatory document will prepare applicants to submit the appropriate information to demonstrate that they are qualified and will make adequate provision for the protection of the environment, the health and safety of persons and the maintenance of national security and measures required to implement international obligations to which Canada has agreed.

The purpose of training in the nuclear industry is to ensure that workers are competent and qualified to perform the duties of their position. As required by the General Nuclear Safety and Control Regulations, workers shall be trained to carry on the licensed activity. A training system provides the basis for the analysis, design, development, implementation, evaluation, documentation and management of training for workers at nuclear facilities. It provides a method for meeting the training needs of workers and ensuring that the right people receive the right training at the right time. With a training system as defined in this regulatory document, it can be demonstrated that all required knowledge, skills and safety-related attributes have been attained, through the process of performance-based assessment and program evaluation. Without a training system, there is a risk that important elements of training will be omitted and the operating state of the facility will not be reflected in the training programs.

This regulatory document clarifies requirements and provides guidance for applicants and licensees on how to demonstrate the safety of a Class IB nuclear facility, including information relating to: • the safety analysis program (the managed process that governs the conduct of a safety analysis) • the conduct of a safety analysis (the systematic evaluation of the potential hazards) • safety analysis documents, records and reporting