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Glossary of CNSC Terminology

Framework for Radioactive Waste Management and Decommissioning in Canada, Version 2

Requirements for Renewal of Operating Licenses for Nuclear Power Plants

Regulatory Fundamentals, Version 3

Waste Management, Volume I: Management of Radioactive Waste

Supplemental Information for Small Modular Reactor Proponents, Version 1.1

Licence Application Guide: Licence to prepare Site for a Deep Geological Repository

Disposal of High-Level Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada

Specific Domestic Licenses of Broad Scope for Byproduct Material

Deterministic Safety Analysis

Aging Management

Physical Protection of Plants and Materials

Management System

Maintenance Programs for Nuclear Power Plants

Import and Export, Version 2

Pre-licensing Review of a Vendor’s Reactor Design

Licence Application Guide: Nuclear Substances and Radiation Devices, Version 2.1

Human Performance, Version 2

Controlling Releases to the Environment

Personnel Training, Version 2

Dosimetry, Volume I: Ascertaining Occupational Dose

Operations Programs for Reactor Facilities

Licence Application Guide: Class IB Processing Facilities

Domestic Licensing of Special Nuclear Material

Design, Testing and Performance of Exposure Devices, Version 1.1

Conventional Health and Safety

Financial Guarantees for Decommissioning of Nuclear Facilities and Termination of Licensed Activities

Reporting Requirements, Volume I: Non-Power Reactor Class I Facilities and Uranium Mines and Mills, Version 1.1

Fitness for Duty: Managing Worker Fatigue

Design of Uranium Mines and Mills: Ventilation Systems, Version 1.1

Design of Reactor Facilities, Version 2.1

General Design Considerations: Human Factors

Accident Management, Version 2

Conduct of Licensed Activities: Construction and Commissioning Programs

Reliability Programs for Nuclear Power Plants

Nuclear Emergency Preparedness and Response, Version 2

Site Evaluation and Site Preparation for New Reactor Facilities, Version 1.3

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.

Nondiscrimination in Federally Assisted Programs or Activities Receiving Federal Financial Assistance from the Commission

Site Access Security Clearance

Personnel Certification: Radiation Safety Officers

Guide for Applicants and Intervenors Writing CNSC Commission Member Documents, Version 1.1

Radiation Protection, Version 1.1

Reporting Requirements for Nuclear Power Plants, Version 3

Periodic Safety Reviews

Minimum Staff Complement

Information Dissemination: Licensing Process for Class I Nuclear Facilities and Uranium Mines and Mills, Version 2.1

Licence Application Guide: Licence to Construct A Reactor Facility, Version 2

Nuclear Criticality Safety, Version 1.1

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.