Topic
Nuclear
Every regulation in the Vantage corpus tagged with nuclear. Items are tagged by the enrichment cron once they land, plus any topic attribution the connector pre-populates.
Latest items
Open in Browser →Safeguards and Nuclear Material Accountancy
REGDOC-2.13.1 establishes safeguards and nuclear material accountancy requirements for Canadian licensees possessing nuclear material, operating uranium or thorium mines, or conducting nuclear fuel-cycle research and manufacturing. It ensures Canada's compliance with IAEA safeguards agreements under the Non-Proliferation Treaty through mandatory licensee reporting and IAEA inspections to verify nuclear material is not diverted to non-peaceful uses.
Pre-licensing Review of a Vendor’s Reactor Design
REGDOC-3.5.4 describes the Canadian Nuclear Safety Commission's optional pre-licensing review service for nuclear reactor vendor designs. The service assesses designs for safety, security, and safeguards compliance to identify regulatory or technical issues early and increase certainty, but does not certify designs, bind future licensing decisions, or constitute a required part of the licensing process.
Glossary of CNSC Terminology
REGDOC-3.6 is the Canadian Nuclear Safety Commission's official glossary providing standardized definitions for terms used in the Nuclear Safety and Control Act, CNSC regulations, and regulatory documents. Updated regularly as an evergreen reference since December 2016, it ensures consistency and serves as the authoritative standard for future CNSC regulatory guidance and communications.
General Design Considerations: Human Factors
REGDOC-2.5.1 provides guidance for Canadian nuclear licensees on integrating human factors engineering into Class I nuclear facilities and uranium mining/milling operations. Licensees must develop human factors engineering program plans and conduct verification and validation activities to ensure health, safety, and environmental protection through systematic consideration of human performance in facility design and licensed activities.
Medical Use of Byproduct Material
10 CFR Part 35 establishes regulatory requirements for the medical use of byproduct material, including radiation safety standards for workers, the general public, patients, and human research subjects. The regulation defines authorized roles (authorized users, radiation safety officers, authorized medical physicists, and authorized nuclear pharmacists) and licensing provisions issued by the Nuclear Regulatory Commission and Agreement States.
Implementation of the Equal Access to Justice Act in Agency Proceedings
10 CFR Part 12 implements the Equal Access to Justice Act (EAJA) for Nuclear Regulatory Commission proceedings, establishing procedures for awarding attorney fees and expenses to prevailing parties in covered adversary adjudications. Eligible applicants include individuals (net worth ≤$2M), small business owners (≤$7M net worth, ≤500 employees), tax-exempt organizations, and cooperative associations. Awards are available unless the Commission's position was substantially justified or special circumstances apply.
Fitness for Duty Programs
10 CFR Part 26 establishes fitness-for-duty program requirements for nuclear power reactor licensees, special nuclear material handlers, construction permit holders, and contractors. FFD programs must ensure personnel reliability through implementation before receipt of fuel assemblies or start of construction, with scope varying by licensee category and authorization type.
Safety Culture
REGDOC-2.1.2 establishes Canadian Nuclear Safety Commission requirements for Class I nuclear facilities and uranium mines/mills to develop and maintain healthy safety cultures. Organizations must foster shared values and common understandings that reinforce worker perceptions of safety importance through a risk-proportionate graded approach. Safety and security cultures coexist to limit risks from nuclear substances and facilities.
Design of Industrial Radiography Installations
REGDOC-2.5.5 provides design guidance for industrial radiography installations using sealed nuclear sources (cobalt-60, iridium-192, selenium-75) for non-destructive testing of materials in welds, castings, and structures. Installations must incorporate adequate shielding and safety features to limit radiation exposure to certified operators, workers, and the public within regulatory limits while maintaining doses as low as reasonably achievable, and comply with applicable building, fire protection, and safety codes.
Radiation Protection Guidelines for the Safe Handling of Decedents
REGDOC-2.7.3 provides guidance for death-care professionals on safely handling deceased individuals who retain radioactive material from therapeutic nuclear medicine and manual brachytherapy procedures. The document recommends radiation protection measures and dose minimization practices to protect workers and the public from residual nuclear substance exposure. Temporary implants removed before body release require no special precautions.
Environmental Principles, Assessments and Protection Measures, Version 1.2
REGDOC-2.9.1 Version 1.2 establishes the Canadian Nuclear Safety Commission's environmental protection framework for nuclear facilities and activities. It requires environmental reviews proportionate to risk, mandates environmental risk assessments (ERAs) updated at least every five years or when significant changes occur, and specifies that licensees must demonstrate adequate environmental protection measures for facilities with direct environmental interactions.
Guide for Applicants and Intervenors Writing CNSC Commission Member Documents, Version 1.1
REGDOC-3.4.1 is a procedural guide from Canada's Nuclear Regulatory Commission (CNSC) establishing requirements and best practices for applicants and intervenors preparing Commission Member Documents in nuclear licensing proceedings. It provides guidance on plain-language writing, document formatting, filing procedures, and templates to facilitate effective presentation of science-based evidence and efficient Commission hearings.
Compliance and Enforcement: Administrative Monetary Penalties, Version 2
REGDOC-3.5.2 describes Canada's Nuclear Safety Commission's administrative monetary penalties (AMPs) program for enforcing nuclear safety compliance. The CNSC applies a three-tiered compliance approach combining communication, verification, and enforcement measures under the Nuclear Safety and Control Act to ensure regulated entities meet requirements and protect public health, security, and the environment.
Radiation Protection Programs for Nuclear Substances and Radiation Devices Licences
REGDOC-1.6.2 provides Canadian CNSC licensees with guidance on developing, implementing, managing and assessing radiation protection programs for nuclear substances and radiation devices. The document establishes roles and responsibilities of radiation safety officers, defines core program elements including people and procedures, and requires programs proportionate to licensed activities' scope, risk level and complexity.
Regulatory Fundamentals, Version 3
REGDOC-3.5.3 is an informational document describing the Canadian Nuclear Safety Commission's regulatory philosophy and approach under the Nuclear Safety and Control Act. It outlines how the CNSC regulates nuclear energy, materials, and substances to protect health, safety, security, and the environment while fulfilling Canada's international nuclear safeguards commitments. Contains no binding requirements for licensees.
Nondiscrimination in Federally Assisted Programs or Activities Receiving Federal Financial Assistance from the Commission
10 CFR Part 4 establishes nondiscrimination requirements for programs and activities receiving federal financial assistance from the Nuclear Regulatory Commission. The regulation implements Title VI of the Civil Rights Act of 1964 (protecting against discrimination based on race, color, national origin, and sex), Section 504 of the Rehabilitation Act of 1973 (protecting individuals with disabilities), and the Age Discrimination Act of 1975 (protecting against age-based discrimination) across all NRC-funded programs, with specific exemptions for insurance contracts, procurement contracts, and general employment practices.
Criteria and Procedures for Determining Eligibility for Access to or Control over Special Nuclear Material
10 CFR Part 11 establishes criteria and procedures for determining eligibility of individuals to receive special nuclear material access authorization. It applies to NRC licensees' employees, contractors, and consultants requiring access to or control over formula quantities of special nuclear material. The regulation defines two authorization levels (NRC-R and NRC-U) based on background investigation tiers and implements a personnel security program to safeguard special nuclear material and prevent sabotage.
Debt Collection Procedures
10 CFR Part 15 establishes NRC procedures for collecting debts owed to the US Government, including methods for interest assessment, claim compromise, administrative offset, wage garnishment, and referral of delinquent accounts to Treasury and DOJ. The regulation defines key debt collection terms and specifies procedures for civil penalties, employee erroneous payments, and other special debt categories.
Salary Offset Procedures for Collecting Debts Owed by Federal Employees to the Federal Government
This NRC regulation establishes administrative procedures for collecting debts owed by federal employees to the federal government through salary offset without employee consent. The procedures apply to NRC employees owing debts to other agencies and employees of other agencies owing debts to the NRC, but exclude debts under tax, tariff, or other specific statutes. Employees retain rights to request waivers, compromise settlements, or challenge debt validity.
Reporting Requirements for Nuclear Power Plants, Version 3
REGDOC-3.1.1 Version 3 consolidates Canadian Nuclear Safety Commission reporting requirements for nuclear power plant licensees. It mandates immediate notifications of safety events, routine periodic reports including cybersecurity documentation, introduces a retraction process for conservatively reported events, and applies graded approaches across reactor lifecycle phases.
Administrative Remedies for False Claims and Statements
10 CFR Part 13 establishes administrative procedures for the Nuclear Regulatory Commission to impose civil penalties and assessments against persons who submit false, fictitious, or fraudulent claims or statements. The regulation implements the Administrative False Claims Act of 2023, defines key terms including claims, defendants, and procedural concepts, and specifies hearing and appeal rights for defendants.
Notices, Instructions and Reports to Workers: Inspection and Investigations
10 CFR Part 19 establishes requirements for NRC licensees and regulated entities to provide notices, instructions, and reports to workers in nuclear-licensed activities. It defines worker rights and responsibilities during NRC inspections and investigations, including rules for compelled interviews under subpoena, and applies to all persons involved in NRC-licensed nuclear material, production/utilization facilities, and spent fuel storage installations.
Site Access Security Clearance
REGDOC-2.12.2 provides Canadian Nuclear Safety Commission guidance for granting, denying, renewing, and revoking site access security clearances (SASC) for authorized unescorted entry to protected areas at high-security nuclear facilities. The clearance process, mandated under the Nuclear Safety and Control Act and Nuclear Security Regulations, prevents insider threats and mitigates unreasonable risks to facility operations, personnel safety, and national security.
Standards for Protection Against Radiation
10 CFR Part 20 establishes federal standards for protection against ionizing radiation from NRC-licensed activities. It sets dose limits for individuals exposed to byproduct, source, and special nuclear materials, defines key radiation protection terms (absorbed dose, airborne radioactivity, ALARA), and applies to licensees under parts 30–72 of the CFR. Medical exposures and background radiation are excluded.
Conduct of Licensed Activities: Construction and Commissioning Programs
REGDOC-2.3.1 establishes Canadian Nuclear Safety Commission requirements for construction and commissioning of nuclear reactor facilities, including power plants and small reactors for power generation, industrial heat, isotope production, and research applications. The document applies risk-informed, graded approaches to safety-critical structures, systems, and components and forms the licensing basis for regulated facilities.
Periodic Safety Reviews
REGDOC-2.3.3 establishes Canadian Nuclear Safety Commission requirements for periodic safety reviews of nuclear power plants. PSRs comprehensively assess plant design, condition, and operation against current codes, standards, and best practices using a graded risk-based approach to identify improvements ensuring safe long-term operation and conformance to modern safety levels.
Public Information and Disclosure
REGDOC-3.2.1 requires licensees and applicants of Class I and II nuclear facilities and uranium mines/mills to develop and implement public information programs with disclosure protocols. Licensees must transparently communicate facility activities, environmental and health impacts to nearby communities, and establish openness and trust through effective engagement strategies tailored to target audiences.
Licenses and Radiation Safety Requirements for Irradiators
10 CFR Part 36 establishes licensing and radiation safety requirements for panoramic and underwater irradiators using sealed radioactive sources for gamma irradiation, with dose rates exceeding 5 grays per hour at 1 meter. The regulations exempt self-contained dry-source-storage irradiators, medical, radiography, gauging, and agricultural applications. Licensees must comply with additional federal, state, and local regulations on facility siting, zoning, and building codes.
Advisory Committees
This regulation establishes NRC policies and procedures for establishing, utilizing, and terminating advisory committees. Committees must comply with the Federal Advisory Committee Act and serve only in an advisory capacity. The NRC establishes committees only when required by law, essential to NRC business, or when information is unavailable elsewhere. Committees must be balanced and kept to minimum necessary size, and must be terminated when objectives are met, subject matter becomes obsolete, functions transfer elsewhere, or costs become excessive. Non-statutory committees terminate within two years unless renewed. Meetings are open to the public unless justified closure occurs.
Licenses, Certifications, and Approvals for Nuclear Power Plants
10 CFR Part 52 establishes the NRC regulatory framework for issuing licenses, certifications, and approvals for nuclear power plants, including early site permits, standard design certifications, combined licenses, and manufacturing licenses. The regulation defines key terms, outlines applicability to all persons involved in licensed nuclear facility activities, and specifies compliance requirements under 10 CFR Chapter I.
Certification of Gaseous Diffusion Plants
10 CFR Part 76 establishes operational and certification requirements for uranium enrichment gaseous diffusion plants at Portsmouth (Ohio) and Paducah (Kentucky) operated by USEC. The regulations protect public health and safety from radiological hazards and ensure common defense security through administrative controls, compliance plans, and NRC certification processes. The regulations expire January 8, 2027, unless extended by up to five years.
Radiation Protection, Version 1.1
REGDOC-2.7.1 Version 1.1 is Canadian Nuclear Safety Commission guidance on radiation protection for licensed nuclear facilities. It establishes a public dose limit of 1 mSv per calendar year, requires radiation workers to be at least 18 years old, and provides direction on radiation protection programs, worker dose control, and radiological hazard management.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
Physical Protection of Plants and Materials
10 CFR Part 73 establishes physical protection requirements for special nuclear material at fixed sites and in transit, and for plants using such material. The regulation prescribes design basis threats that safeguards systems must counter, including radiological sabotage and theft/diversion of strategic special nuclear material by adversaries with military training, weapons, explosives, vehicles, and cyber attack capabilities.
Public Records
10 CFR Part 9 establishes the Nuclear Regulatory Commission's procedures for public records access and disclosure under the Freedom of Information Act, Privacy Act, Government in the Sunshine Act, and Social Security Number Fraud Prevention Act. It defines key terms, specifies communication procedures for FOIA and Privacy Act requests, confirms OMB approval of information collection requirements, and addresses record production in response to judicial subpoenas.
Material Control and Accounting of Special Nuclear Material
This regulation establishes material control and accounting requirements for special nuclear material (uranium-235, uranium-233, and plutonium) at licensed facilities. It applies to licensees possessing one gram or more of these materials and specifies reporting, recordkeeping, and control procedures based on material strategic significance and facility type, including enrichment facilities and transferred quantities.
Safeguards on Nuclear Material—Implementation of Safeguards Agreements Between the United States and the International Atomic Energy Agency
This regulation implements US safeguards agreements with the International Atomic Energy Agency (IAEA) to fulfill nuclear non-proliferation obligations. It establishes requirements for NRC licensees, certificate holders, and applicants to report information on source and special nuclear materials, their physical locations, and grant IAEA inspectors access to facilities for verification activities consistent with international safeguards standards and the Additional Protocol.
Uranium Enrichment Decontamination and Decommissioning Fund; Procedures for Special Assessment of Domestic Utilities
This regulation establishes procedures for assessing domestic utilities that purchased uranium enrichment separative work units (SWUs) from the Department of Energy between 1945 and October 23, 1992. Utilities are assessed annually based on their proportional share of DOE-produced SWUs, with assessments funding the Uranium Enrichment Decontamination and Decommissioning Fund under the Atomic Energy Act.
Nuclear Safety Management
10 CFR Part 830 establishes nuclear safety management requirements for DOE contractors, personnel, and other parties conducting activities affecting DOE nuclear facility safety. It excludes NRC-licensed activities, Naval Nuclear Propulsion operations, DOT-regulated transportation, nuclear waste activities, and space-based nuclear systems. The regulation defines key safety concepts including documented safety analyses, hazard categories, criticality, technical safety requirements, and administrative controls, applying a graded approach to compliance proportional to facility hazards and mission.
Restrictions on Aircraft Landing and Air Delivery at Department of Energy Nuclear Sites
10 CFR Part 862 prohibits aircraft landing, air delivery, and aircraft operations at DOE nuclear sites, with limited exceptions for federal government, state/local law enforcement, and emergency landings. The rule defines applicable aircraft types, designated sites, and procedures for removal of downed aircraft. Violations may result in criminal penalties under the Atomic Energy Act.
Byproduct Material
10 CFR Part 962 defines 'byproduct material' under the Atomic Energy Act for DOE facilities as any radioactive material (except special nuclear material) produced or made radioactive by exposure to radiation during special nuclear material production or use. For RCRA compliance, only actual radionuclides in DOE-owned radioactive waste are covered; nonradioactive hazardous components remain subject to separate RCRA regulation.
Nondiscrimination on the Basis of Sex in Education Programs or Activities Receiving Federal Financial Assistance
This regulation implements Title IX of the Education Amendments of 1972, establishing nondiscrimination requirements on the basis of sex in education programs and activities receiving federal financial assistance. It defines key terms including educational institutions, federal financial assistance, applicants, and administrative structures, effective September 29, 2000.
Licence Application Guide: Licence to Construct A Reactor Facility, Version 2
REGDOC-1.1.2 is the Canadian Nuclear Safety Commission's guide for applicants seeking a licence to construct reactor facilities in Canada. It clarifies submission requirements, applies to advanced and small modular reactors, and requires applicants to demonstrate qualifications, environmental protection, health and safety measures, national security compliance, and adherence to international obligations using a risk-informed graded approach.
Maintenance Programs for Nuclear Power Plants
REGDOC-2.6.2 establishes Canadian Nuclear Safety Commission requirements for maintenance programs at nuclear power plants. Licensees must develop comprehensive policies, processes and procedures for monitoring, inspection, testing, repair and replacement of all structures, systems and components based on safety importance, emphasizing preventive maintenance and continuous improvement aligned with international IAEA standards.
Chemistry Control for Reactor Facilities
REGDOC-2.6.4 establishes chemistry control program requirements for Canadian reactor facilities (NPPs, advanced reactors, SMRs, research reactors) to ensure structural integrity of safety-critical systems, protect fuel, minimize radioactive material buildup, and achieve ALARA environmental releases. Licensees may propose risk-informed or alternative approaches proportionate to their facility's risk profile.
Licence Application Guide: Nuclear Substances and Radiation Devices, Version 2.1
CNSC guidance document (REGDOC-1.6.1 v2.1) establishing requirements for Canadian licence applications to possess, use, store, transfer, import, export, service, or abandon nuclear substances and radiation devices under the Nuclear Safety and Control Act. Applicants must demonstrate qualifications, adequate health and safety provisions, environmental protection, and effective radiation safety programs.
Guidance on Deep Geological Repository Site Characterization
REGDOC-1.2.1 provides guidance on site characterization programs for deep geological repositories designed to isolate radioactive waste in stable geological formations. It outlines technical investigations integrating hydrogeology, rock mechanics, and geochemistry to evaluate facility performance across site preparation, construction, operation, decommissioning, and closure phases, supporting licence applications and long-term safety cases.
Licence Application Guide: Class IB Processing Facilities
CNSC guidance document establishing requirements for licence applications to site prepare, construct, operate, or decommission Class IB nuclear processing facilities in Canada. Applies to facilities processing uranium, thorium, plutonium, or other nuclear substances exceeding 10^15 Bq annually. Establishes compliance framework under the Nuclear Safety and Control Act including radiation protection, security, and decommissioning standards.
Human Performance, Version 2
REGDOC-2.2.1 Version 2 establishes human performance management requirements for Canadian Class I nuclear facilities and uranium mines/mills. Licensees must systematically manage human, technological, and organizational factors using a risk-proportionate graded approach, incorporating IAEA standards and ISO human-centered management principles to achieve safe and effective performance.
Licence Application Guide: Class II Nuclear Facilities and Prescribed Equipment, Version 1.1
REGDOC-1.4.1 is the Canadian Nuclear Safety Commission's consolidated licence application guide for Class II nuclear facilities and prescribed equipment. It establishes requirements for applicants seeking licences to construct, operate, decommission, or service such facilities, demonstrating qualifications and adequate provisions for health, safety, environmental protection, and national security under the Nuclear Safety and Control Act.
Criteria and Procedures for Determining Eligibility for Access to Restricted Data or National Security Information or an Employment Clearance
10 CFR Part 10 establishes criteria and procedures for determining eligibility for access to Restricted Data and National Security Information for NRC employees, contractors, licensees, and applicants. The regulation implements the Atomic Energy Act and Executive Orders to ensure security of the nuclear energy program while providing administrative review opportunities for individuals seeking access authorization or employment clearance.
Procedural Rules for DOE Nuclear Activities
10 CFR Part 820 establishes procedural rules governing conduct of persons involved in DOE nuclear activities to ensure compliance with DOE Nuclear Safety Requirements. The regulation defines key terms, enforcement processes, and administrative procedures, with Naval nuclear propulsion activities excluded from certain interpretations and exemptions provisions under the Deputy Administrator for Naval Reactors.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.