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Personnel Training, Version 2
REGDOC-2.2.2 establishes mandatory training system requirements for Canadian nuclear facility licensees. Licensees must develop, implement, and maintain comprehensive training programs covering analysis, design, development, implementation, evaluation, and documentation to ensure workers are competent and qualified to safely perform duties involving nuclear substances and equipment. A graded approach commensurate with risk may be applied.
Supplemental Information for Small Modular Reactor Proponents, Version 1.1
REGDOC-1.1.5 provides supplemental guidance for Small Modular Reactor (SMR) licence applicants to Canada's Nuclear Safety Commission. It establishes a risk-informed, graded approach for water-cooled and advanced reactors ranging from megawatts to several hundred megawatts, supporting licence applications for site preparation, construction, operation, and decommissioning stages.
Requirements for Renewal of Operating Licenses for Nuclear Power Plants
This regulation establishes requirements for renewal of operating licenses for nuclear power plants under the Atomic Energy Act. It defines key terms including current licensing basis, integrated plant assessment, and time-limited aging analyses. The rule specifies that license renewal applies to both safety-related and nonsafety-related systems, structures, and components that must be assessed for aging management to maintain acceptable safety levels during extended operation beyond the initial 40-year license term.
Personnel Certification: Radiation Safety Officers
REGDOC-2.2.3 establishes Canadian Nuclear Safety Commission guidance for certifying Radiation Safety Officers at Class II nuclear facilities. It outlines application requirements, qualification criteria, and certification examination procedures to ensure RSOs are competent to perform their safety duties. An exemption applies to persons already certified in equivalent positions at Class I facilities.
Probabilistic Safety Assessment (PSA) for Reactor Facilities, Version 2
REGDOC-2.4.2 Version 3 establishes requirements for probabilistic safety assessments (PSA) at Canadian reactor facilities including nuclear power plants, small reactors, and research reactors. Licensees must conduct systematic analyses demonstrating facility designs protect people and the environment from radiation, achieve balanced designs without disproportionate risk contributions, and prevent cliff-edge effects, using a graded approach aligned with IAEA standards.
Information Dissemination: Licensing Process for Class I Nuclear Facilities and Uranium Mines and Mills, Version 2.1
REGDOC-3.5.1 outlines the Canadian Nuclear Safety Commission's licensing process for Class I nuclear facilities and uranium mines and mills. All persons and companies must obtain a CNSC licence before site preparation, construction, operation, decommissioning, or abandonment of nuclear facilities, or possession, use, transport, and storage of nuclear substances under the Nuclear Safety and Control Act. Version 2.1 is an administrative update reflecting January 2022 organizational changes to the Commission Secretariat and Secretary roles.
Aging Management
REGDOC-2.6.3 establishes Canadian Nuclear Safety Commission requirements for managing aging of structures, systems, and components in power reactor facilities throughout their licensed service life. Licensees must implement coordinated engineering, operational, inspection, and maintenance programs to control physical aging and obsolescence, ensuring required safety functions remain reliable and available in accordance with the licensing basis.
Licence Application Guide: Licence to operate a Nuclear Power Plant, Version 1.3
REGDOC-1.1.3 is the Canadian Nuclear Safety Commission's regulatory guide for licence applications to operate nuclear power plants in Canada. It establishes requirements and guidance using a risk-informed, graded approach, requiring applicants to demonstrate qualifications and adequate safety provisions. No fuel may be loaded until the CNSC grants an operating licence.
Standby Support for Certain Nuclear Plant Delays
10 CFR Part 950 establishes a standby support program providing risk insurance contracts to sponsors of new advanced nuclear facilities approved after 1993. The program covers costs from delays caused by NRC regulatory review failures, pre-operational hearings, or litigation, with indemnification up to $500 million for the first two reactors and $250 million for subsequent reactors.
Design of Rooms Where Unsealed Nuclear Substances Are Used
REGDOC-2.5.6 establishes Canadian Nuclear Safety Commission design requirements for rooms using unsealed nuclear substances. It provides guidance on room finishings, contamination control, ventilation systems, fume hoods, hot cells, and access control across intermediate-level, high-level, containment-level, and nuclear medicine facilities, implementing a risk-informed approach to minimize worker radiation doses per ALARA principles.
Fitness for Duty: Managing Worker Fatigue
REGDOC-2.2.4 establishes Canadian Nuclear Safety Commission requirements for managing worker fatigue at high-security nuclear facilities. Licensees must implement human performance programs using a graded approach proportionate to facility risk to minimize worker errors affecting nuclear safety and security.
Accident Management, Version 2
REGDOC-2.3.2 establishes Canadian Nuclear Safety Commission requirements for integrated accident management at reactor facilities. Licensees must develop, implement, and validate defence-in-depth strategies, operational procedures, and capabilities to manage abnormal and severe accidents, consistent with IAEA safety standards and informed by lessons from the 2011 Fukushima event.
Standard Specifications for the Granting of Patent Licenses
This regulation establishes standard specifications for the Nuclear Regulatory Commission to grant patent licenses on inventions vested in or controlled by the Commission under the Atomic Energy Act of 1954. It defines NRC inventions and foreign inventions, sets procedures for license applications and electronic communications, and specifies that only written interpretations by the General Counsel are binding on the Commission.
Indigenous Engagement, Version 1.2
REGDOC-3.2.2 Version 1.2 establishes requirements for Canadian nuclear licensees to conduct meaningful engagement with Indigenous peoples (First Nations, Inuit, Métis) and provides procedural guidance supporting the Canadian Nuclear Safety Commission's duty-to-consult obligations under federal law. Version 1.2 includes administrative updates to references regarding the Commission Registry.
Decommissioning
REGDOC-2.11.2 establishes Canadian Nuclear Safety Commission requirements and guidance for decommissioning Class I and II nuclear facilities, uranium mines and mills, and nuclear substance sites. It covers all phases from planning through completion, including storage with surveillance, decontamination, dismantling and cleanup to safely retire facilities while protecting human health and the environment.
Financial Protection Requirements and Indemnity Agreements
10 CFR Part 140 establishes financial protection requirements and indemnity agreements for nuclear licensees under the Atomic Energy Act. It applies to operators of nuclear reactors, uranium enrichment facilities, plutonium processing plants, and other nuclear production and utilization facilities. The regulations define procedures for determining required financial protection, liability insurance, and indemnification limits, with special provisions for Federal agencies and nonprofit educational institutions.
Design of Uranium Mines and Mills: Ventilation Systems, Version 1.1
REGDOC-2.5.4 is a Canadian Nuclear Safety Commission regulatory guide for ventilation system design in uranium mines and mills. It establishes requirements for ventilation-related information in licence applications for site preparation, construction, operation, and decommissioning of underground and surface licensable areas, applying a risk-informed, graded approach to protect worker and radiation safety consistent with modern national and international nuclear standards.
Domestic Licensing of Special Nuclear Material
10 CFR Part 70 establishes NRC procedures and criteria for issuing domestic licenses to receive, own, possess, use, and transfer special nuclear material. The regulation applies to all US persons and defines key licensing requirements, relevant definitions (acute exposure, alert conditions, atomic weapons), and references related rules for spent fuel storage, uranium enrichment facilities, and physical security.
Operations Programs for Reactor Facilities
REGDOC-2.3.4 establishes requirements and guidance for developing and implementing operations programs at nuclear reactor facilities, including conventional power plants, advanced reactors, and small modular reactors. Licensees may apply risk-informed and graded approaches proportional to facility risk profiles, based on operational experience and best practices from water-cooled reactors.
Reporting Requirements, Volume I: Non-Power Reactor Class I Facilities and Uranium Mines and Mills, Version 1.1
REGDOC-3.1.2 establishes reporting requirements for Canadian Nuclear Safety Commission licensees operating Class I non-power reactor facilities, uranium mines, and mills. Licensees must submit operational compliance reports, significant event notifications, and business activity notifications using a risk-graded approach. This document consolidates and replaces four prior regulatory documents governing uranium refining, fuel fabrication, and processing facility reporting.
Procedures for Determining Eligibility for Access to Classified Matter and Special Nuclear Material or Eligibility to Hold a Sensitive Position
This Department of Energy regulation establishes procedures for determining eligibility of DOE employees, contractors, and other designated persons for access to classified information, special nuclear material, and sensitive positions. It implements multiple executive orders and the National Security Adjudicative Guidelines, outlining administrative review and appeals processes while ensuring fairness and preventing retaliation.
Design, Testing and Performance of Exposure Devices, Version 1.1
REGDOC-2.5.7 Version 1.1 establishes Canadian Nuclear Safety Commission requirements for design, testing, and certification of exposure devices used in industrial radiography with sealed radioactive sources. The regulation mandates compliance with ISO 3999:2004 and specifies technical requirements for sealed source design, safety mechanisms, automatic securing devices, calibration, endurance and vibration testing, and labelling for portable non-destructive testing equipment used to inspect welds, castings, and building components.
Extraordinary Nuclear Occurrences
10 CFR Part 840 establishes administrative criteria for determining "extraordinary nuclear occurrences" under DOE contractor indemnity agreements. It sets thresholds for substantial discharge or dispersal of source, special nuclear, or byproduct material and offsite radiation levels, then requires evaluation of whether substantial damages to persons or property offsite have occurred or are probable. The criteria are distinct from health and safety regulatory limits and apply to DOE contractor activities covered by nuclear hazards indemnity provisions.
Licenses and Radiation Safety Requirements for Well Logging
10 CFR Part 39 establishes licensing and radiation safety requirements for the use of licensed materials—including sealed sources, radioactive tracers, markers, and uranium sinker bars—in well logging operations. The regulation prescribes definitions, operational requirements, supervisory standards, and compliance obligations for persons handling radioactive sources at temporary jobsites, including personal supervision, safety reviews, and cross-referenced NRC regulatory provisions.
Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste
10 CFR Part 961 establishes standard contract terms for the Department of Energy to accept title to, transport, and dispose of spent nuclear fuel and high-level radioactive waste from civilian nuclear power reactor owners and generators. Owners and generators pay fees to recover DOE's full disposal costs, with receipts deposited in the Nuclear Waste Fund. Contracts must be executed by June 30, 1983, or by the date the owner/generator commences generation or takes title to such waste, whichever is later.
Reactor Site Criteria
10 CFR Part 100 establishes site approval criteria for stationary power and testing reactors to ensure public health and safety through defense-in-depth siting principles. The regulation defines exclusion areas where the licensee controls all activities, low population zones where protective measures are feasible, and population center distance requirements, ensuring radiological doses from normal operation and postulated accidents remain acceptably low while accounting for natural hazards and enabling effective emergency planning and security.
Operators' Licenses
10 CFR Part 55 establishes NRC procedures and criteria for issuing, maintaining, and renewing operator and senior operator licenses for nuclear utilization facilities. It defines license requirements, scope of applicability to individuals manipulating reactor controls or directing licensed activities, and sets forth key definitions including operators, senior operators, simulation facilities, and performance testing standards.
Administrative Claims Under Federal Tort Claims Act
10 CFR Part 14 establishes procedural regulations for filing administrative claims under the Federal Tort Claims Act against the United States for property damage, personal injury, or death caused by negligent or wrongful acts of NRC employees. Claims must be filed with the relevant NRC office or the Office of the General Counsel, and the NRC General Counsel is authorized to adjust, determine, compromise, and settle such claims.
Security of Nuclear Substances: Sealed Sources and Category I, II and III Nuclear Material, Version 2.1
REGDOC-2.12.3 Version 2.1 establishes minimum security requirements for sealed radioactive sources and Category I, II, and III nuclear materials in Canada. Licensees must implement technical and administrative controls during storage, transport, and handling to prevent loss, sabotage, unauthorized possession, or illegal removal. Requirements cover security plans, transport vehicles, containers, and third-party carrier compliance.
Licence Application Guide: Licence to prepare Site for a Deep Geological Repository
REGDOC-1.2.3 is the Canadian Nuclear Safety Commission's licence application guide for entities seeking to obtain a licence to prepare sites for deep geological repositories (DGR) of radioactive waste. It establishes comprehensive requirements across management systems, radiation protection, safety analysis, environmental protection, waste management, security, and public engagement, applying a risk-proportionate graded approach throughout the DGR lifecycle and site preparation stages.
Reporting Requirements for Waste Nuclear Substance Licensees, Class II Nuclear Facilities and Users of Prescribed Equipment, Nuclear Substances and Radiation Devices
REGDOC-3.1.3 establishes mandatory reporting requirements for Canadian Nuclear Safety Commission licensees managing waste nuclear substances, Class II nuclear facilities, and users of prescribed equipment and radiation devices. Licensees must report events, dangerous occurrences and situations within specified timeframes and submit annual compliance reports, following a risk-informed approach aligned with national and international nuclear safety standards.
Application Guide: Certification of Radiation Devices or Class II Prescribed Equipment, Version 1.1
REGDOC-1.5.1 v1.1 is a Canadian Nuclear Safety Commission application guide helping applicants prepare and submit certification applications for radiation devices and Class II prescribed equipment. The guide ensures prescribed equipment is safe, protects public health and environment, meets national security standards, and complies with Canada's international nuclear obligations under the Nuclear Safety and Control Act.
Information Incorporated by Reference in Canada’s Packaging and Transport of Nuclear Substances Regulations, 2015, Volume I, Version 2
REGDOC-2.14.1 incorporates IAEA Standards (SSR-6) into Canada's Packaging and Transport of Nuclear Substances Regulations 2015, establishing requirements for safe radioactive material transport including licensing, package design, certification, material classification, radiation protection, and record-keeping. All persons transporting or offering nuclear substances must comply, with joint enforcement by the CNSC and Transport Canada.
Waste Management, Volume I: Management of Radioactive Waste
REGDOC-2.11.1 establishes requirements and guidance for Canadian Nuclear Safety Commission licensees managing radioactive waste, including characterization, storage, and disposal facilities. The document applies to all CNSC licensees under the Nuclear Safety and Control Act and is complemented by CSA N292 standards for comprehensive radioactive waste management oversight.
Import and Export, Version 2
REGDOC-2.13.2 provides Canadian Nuclear Safety Commission guidance on licensing the import and export of controlled nuclear substances, dual-use equipment, and Category 1–2 radioactive sources. It outlines application procedures, licensing criteria, end-use controls, and compliance verification mechanisms to prevent nuclear weapons proliferation under the Nuclear Non-proliferation Import and Export Control Regulations.
Deterministic Safety Analysis
REGDOC-2.4.1 establishes Canadian Nuclear Safety Commission requirements for deterministic safety analysis at nuclear power plants and small reactor facilities (below 200 MWt). The document prescribes methods for safety analysis reports, design basis event selection, acceptance criteria, and documentation using a risk-informed, graded approach, incorporating Fukushima lessons and international safety practices.
Nuclear Emergency Preparedness and Response, Version 2
REGDOC-2.10.1 establishes emergency preparedness and response requirements for Canadian Class I nuclear facilities and uranium mines/mills licensed by the CNSC. Licensees must develop risk-proportionate emergency programs based on four components: planning basis, program management, response procedures, and preparedness. The standard aligns with IAEA guidance to prevent or mitigate effects of accidental releases.
Framework for Radioactive Waste Management and Decommissioning in Canada, Version 2
REGDOC-2.11 establishes Canada's regulatory framework for radioactive waste management and decommissioning under the Canadian Nuclear Safety Commission. It defines radioactive waste as any material containing radioactive nuclear substances with no further use, and requires waste owners to safely manage such materials through generation, handling, processing, storage, transport, and disposal while protecting public health, safety, environment, and national security. The document provides governance overview and principles for consistent national and international standards.
Site Evaluation and Site Preparation for New Reactor Facilities, Version 1.3
REGDOC-1.1.1 establishes Canadian Nuclear Safety Commission requirements for site evaluation and preparation of new reactor facilities, including nuclear power plants and small modular reactors. Applicants must characterize sites, assess severe external events and multiple simultaneous accidents, and demonstrate adequate safety measures during site preparation and construction using a risk-informed, graded approach.
Minimum Staff Complement
REGDOC-2.2.5 provides guidance to Canadian Class I nuclear facility licensees on demonstrating adequate staffing of qualified workers across all operating states—normal operations, anticipated occurrences, design-basis accidents, and emergencies—to ensure safe and compliant operation under the Nuclear Safety and Control Act.
General Guidelines for the Preliminary Screening of Potential Sites for a Nuclear Waste Repository
10 CFR Part 960 establishes general guidelines for the preliminary screening and evaluation of potential sites for nuclear waste repositories under the Nuclear Waste Policy Act of 1982. The regulations define key terms such as accessible environment, candidate sites, containment, and controlled areas, and establish the framework by which the Department of Energy evaluates site suitability in coordination with the NRC and affected states and Indian tribes.
Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions
10 CFR Part 51 establishes environmental protection regulations for the Nuclear Regulatory Commission's domestic licensing and regulatory functions. The regulations implement Section 102(2) of the National Environmental Policy Act of 1969 and apply to NRC licensing proceedings for production, utilization, and materials facilities, excluding export licensing and foreign environmental effects. Key definitions include construction activities, previously disturbed areas, and NRC organizational roles.
Facility Security Clearance and Safeguarding of National Security Information and Restricted Data
10 CFR Part 95 establishes procedures for facility security clearance and safeguarding of classified National Security Information and Restricted Data in NRC-licensed activities. It defines requirements for access authorization, facility eligibility, classified material handling, storage, transmission protocols, and security procedures for NRC licensees, certificate holders, contractors, and designated parties requiring access to Secret or Confidential information.
Reporting of Defects and Noncompliance
10 CFR Part 21 mandates that directors and responsible officers of nuclear licensees and vendors immediately report to the NRC any information indicating that licensed facilities, activities, or basic components fail to comply with applicable regulations or contain defects that could create substantial safety hazards, unless the Commission has already been adequately informed.
Rules of General Applicability to Domestic Licensing of Byproduct Material
10 CFR Part 30 establishes NRC licensing requirements for domestic possession, production, transfer, and use of byproduct material, including accelerator-produced radioactive material and radium-226 sources. The regulation prescribes general applicability rules, defines licensed activities, and sets compliance deadlines for government agencies and Indian Tribes (2007–2009). It also subjects suppliers of components and services to enforcement action for violations.
Controlling Releases to the Environment
REGDOC-2.9.2 establishes Canadian Nuclear Safety Commission requirements for controlling environmental releases from nuclear facilities. Licensees must apply best available technology and techniques economically achievable (BATEA), establish licensed release limits and action levels, validate treatment system performance, and implement adaptive management when unreasonable risk is identified.
Agency Rules of Practice and Procedure
10 CFR Part 2 establishes procedural rules for all Nuclear Regulatory Commission proceedings under the Atomic Energy Act and Energy Reorganization Act, covering licensing actions, permit issuance, civil penalties, rulemaking, and standard design approvals. The rules define roles of adjudicatory employees, distinguish between general and special procedural rules for different proceeding types, and set administrative requirements for contested and non-contested matters.
Statement of Organization and General Information
This regulation establishes the Nuclear Regulatory Commission's organizational structure, authority, and operations following its creation under the Energy Reorganization Act of 1974. It defines the Commission's composition, designates principal and regional offices, and describes how to access NRC organizational directives, meeting information, regulatory documents, and records under the Freedom of Information Act.
Financial Guarantees for Decommissioning of Nuclear Facilities and Termination of Licensed Activities
REGDOC-3.3.1 establishes requirements for applicants and licensees of Canadian nuclear facilities to establish and maintain financial guarantees ensuring sufficient funds for safe decommissioning and termination of licensed activities. The regulation applies to Class IA/IB nuclear facilities, uranium mines and mills, and waste nuclear substances licenses under the Nuclear Safety and Control Act, superseding the 2000 guidance document G-206.
Management System
REGDOC-2.1.1 establishes management system requirements for Canadian Nuclear Safety Commission licensees operating Class 1A and 1B reactors, uranium mines and mills, and radioactive waste facilities. Licensees must develop and implement frameworks of processes, procedures, and practices aligned with CSA standard N286-12 to safely conduct licensed activities and ensure regulatory compliance.