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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.
Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste
10 CFR Part 72 establishes licensing requirements and procedures for independent spent fuel storage installations (ISFSI) and monitored retrievable storage installations (MRS) to receive, transfer, package, and possess spent nuclear fuel, high-level radioactive waste, and reactor-related greater-than-class-C waste. The regulation applies to both wet and dry storage modes, governs Certificates of Compliance for spent fuel storage cask designs, and applies to all US persons including Agreement States.
Disposal of High-Level Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada
10 CFR Part 63 establishes licensing requirements for the U.S. Department of Energy's geologic repository at Yucca Mountain, Nevada for disposal of high-level radioactive waste and spent fuel. The regulation prescribes rules for construction authorization, defines key technical terms including barriers and containment structures for isolating radionuclides, and outlines design basis standards for repository operations under NRC oversight, with provisions addressing affected Indian tribes and enforcement.
Criteria and Procedures for Emergency Access to Non-Federal and Regional Low-Level Waste Disposal Facilities
10 CFR Part 62 establishes criteria and procedures for the Nuclear Regulatory Commission to grant emergency access to non-Federal and regional low-level radioactive waste disposal facilities for up to 180 days to waste generators who have been denied access to existing facilities under the Low-Level Radioactive Waste Policy Amendments Act of 1985. The regulation defines key terms and applies to all persons regulated by the NRC who have been denied such access and submit requests for emergency disposal authorization.
Licensing Requirements for Land Disposal of Radioactive Waste
10 CFR Part 61 establishes licensing procedures and criteria for land disposal of radioactive waste containing byproduct, source, and special nuclear material in the United States. The regulations apply to all persons except those disposing of high-level waste, uranium or thorium tailings exceeding 10,000 kg with more than 5 millicuries of radium-226, or licensed material under Part 20. Key definitions include active maintenance, buffer zones, commencement of construction, and disposal sites.
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.
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.
Disposal of High-Level Radioactive Wastes in Geologic Repositories
10 CFR Part 60 establishes NRC licensing requirements for the U.S. Department of Energy to construct and operate geologic repositories for high-level radioactive waste disposal under the Nuclear Waste Policy Act of 1982. The regulation defines key terms such as accessible environment, barriers, containment, and controlled areas, and prescribes rules governing licensing and construction authorization for repository operations areas, excluding Yucca Mountain facilities.
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.
Risk-Informed, Technology-Inclusive Regulatory Framework for Commercial Nuclear Plants
10 CFR Part 53 establishes an optional, risk-informed, technology-inclusive regulatory framework for licensing, amending, renewing, and terminating commercial nuclear plants under the Atomic Energy Act. It defines key terms including anticipated event sequences, certified fuel handlers, combined licenses, and commercial nuclear reactors, and applies to all persons providing components, equipment, or services related to licensees and applicants.
Domestic Licensing of Production and Utilization Facilities
10 CFR Part 50 establishes the NRC's licensing framework for domestic nuclear production and utilization facilities under the Atomic Energy Act of 1954. It defines key regulatory terms including applicants, atomic energy, basic components, byproduct materials, and alternate AC power sources, and establishes that persons knowingly providing goods or services to licensees may be subject to NRC enforcement action for violations.
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.
Domestic Licensing of Source Material
10 CFR Part 40 establishes NRC licensing procedures and criteria for possession, use, transfer, and disposal of source material, byproduct material, and residual radioactive material in the United States. The regulation applies to all persons unless exempted, sets license terms and conditions, addresses physical protection of natural uranium shipments, and provides for long-term stewardship of uranium mill tailings sites.
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.
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.
Licenses for Industrial Radiography and Radiation Safety Requirements for Industrial Radiographic Operations
10 CFR Part 34 prescribes licensing and radiation safety requirements for industrial radiography operations using sealed sources of byproduct material. The rule mandates adherence to ALARA principles to minimize radiation exposure, requires annual refresher safety training for employees, and defines standards for radiographic equipment including exposure devices, guide tubes, and collimators. Requirements apply to all industrial radiography users but exclude medical applications.
Specific Domestic Licenses to Manufacture or Transfer Certain Items Containing Byproduct Material
10 CFR Part 32 establishes NRC licensing requirements for manufacturers and distributors of items containing byproduct material, including accelerator-produced radioactive material and radium-226 sources. It prescribes procedures for issuing specific domestic licenses, registration certificates for sealed sources and devices, and radiation safety information requirements for products distributed to exempt persons, general licensees, and medical-use licensees.
General Domestic Licenses for Byproduct Material
10 CFR Part 31 establishes general licenses for commercial, industrial, research, educational, medical, and government entities to possess and use radioactive byproduct material in detection, measurement, gauging, and control devices, as well as light and ionized atmosphere-producing devices. General licensees must maintain manufacturer labeling, conduct leakage testing at six-month intervals, comply with 10 CFR Part 30 and related provisions, and follow all safety precautions.
Access Authorization
10 CFR Part 25 establishes procedures for granting, reinstating, extending, transferring, and terminating access authorizations for NRC licensees, certificate holders, contractors, and other personnel requiring access to classified information related to nuclear licenses, certificates, or NRC-regulated activities. Access authorization is an administrative determination of security clearance eligibility based on investigations conducted by designated security agencies.
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.
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.
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.
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.
Transfer of Real Property at Defense Nuclear Facilities for Economic Development
10 CFR Part 770 establishes procedures for the Department of Energy to transfer real property at closed or downsized defense nuclear facilities through sale or lease to support economic development. The rule includes indemnification procedures for claims arising from releases of hazardous substances or contaminants resulting from DOE activities, subject to NEPA review and fund availability.
Nuclear Criticality Safety, Version 1.1
REGDOC-2.4.3 Version 1.1 establishes Canadian Nuclear Safety Commission requirements for preventing criticality accidents in handling, storage, processing, and transportation of fissionable materials outside reactors. It defines minimum physical constraints and limits applicable during facility construction, operation, decommissioning, and abandonment, aligned with IAEA and ANSI/ANS standards.
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.
Export and Import of Nuclear Equipment and Material
10 CFR Part 110 establishes NRC licensing and enforcement procedures for U.S. export and import of nuclear equipment and material under the Atomic Energy Act. The regulations exempt munitions-list items (State Department jurisdiction), depleted uranium commodities and nuclear referral list items (Commerce Department), and certain imports like deuterium and nuclear graphite. Transit shipments require DOT/IAEA compliance but not NRC licenses.
Safety Analysis for Class IB Nuclear Facilities
REGDOC-2.4.4 establishes safety analysis requirements for Canadian Class IB nuclear facilities processing uranium, thorium, plutonium and other nuclear substances. Licensees must implement managed safety analysis programs using risk-informed graded approaches to systematically evaluate hazards, document design measures, and maintain records demonstrating facility safety commensurate with their risk profiles.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
Reliability Programs for Nuclear Power Plants
REGDOC-2.6.1 establishes Canadian Nuclear Safety Commission requirements for reliability programs at nuclear power plants. Licensees must develop and implement programs ensuring systems important to safety meet defined design and performance criteria throughout the facility's lifetime, covering assessment, modelling, evaluation and monitoring across all lifecycle phases from design through decommissioning.
Packaging and Transportation of Radioactive Material
10 CFR Part 71 establishes NRC requirements for packaging, preparation, and transportation of radioactive licensed material. It applies to licensees who deliver radioactive material to carriers, transport it outside authorized sites, or use public highways. The regulation mandates NRC approval of packaging designs and shipping procedures for fissile material and licensed material exceeding Type A quantities, and requires compliance with operating controls, quality assurance standards, and DOT regulations.
Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material
10 CFR Part 37 mandates physical protection programs for licensees possessing Category 1 or Category 2 quantities of radioactive material. Requirements include access controls to prevent theft or diversion, trustworthiness determinations for individual access, security zones, material transfer procedures, and transport safeguards. Rules apply to possession, use, transfer, and domestic transport of regulated radioactive materials.
Specific Domestic Licenses of Broad Scope for Byproduct Material
10 CFR Part 33 establishes requirements for issuing specific domestic licenses of broad scope for byproduct material. It defines three license types (A, B, C) with varying possession limits for radioactive materials, specifies application procedures using NRC Form 313, and incorporates related regulatory requirements from 10 CFR Parts 30 and 37. OMB approval control numbers are provided for information collection requirements.
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.
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.