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REGDOC-2.6.1 - Reliability Programs for Nuclear Power Plants
REGDOC-2.6.1, Reliability Programs for Nuclear Power Plants, sets out the requirements and guidance of the Canadian Nuclear Safety Commission (CNSC) for the development and implementation of a reliability program for a nuclear power plant (NPP) in Canada. The reliability program assures that the systems important to safety (SIS) shall meet their defined design, and performance criteria at acceptable levels of reliability throughout the lifetime of the facility.
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REGDOC-2.6.2 - Maintenance Programs for Nuclear Power Plants
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This regulatory document sets out the requirements of the Canadian Nuclear Safety Commission (CNSC) with regard to maintenance programs for nuclear power plants (NPPs). This document also provides information and guidance on how the requirements may be met. When incorporated into a licence or other legally enforceable instrument, this regulatory document becomes a legal requirement.
REGDOC- 2.4.1 - Deterministic Safety Analysis
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This regulatory document sets out the requirements of the Canadian Nuclear Safety Commission (CNSC) for deterministic safety analysis for nuclear power plants (NPPs) and small reactor facilities.
REGDOC-2.5.2 - Design of Reactor Facilities: Nuclear Power Plants, Version 2.1
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This regulatory document sets out the requirements of the Canadian Nuclear Safety Commission (CNSC) for the design of new water-cooled nuclear power plants. It establishes a set of comprehensive design requirements and guidance that are risk-informed and align with accepted national and international codes and practices.
REGDOC-3.1.1 - Reporting Requirements for Nuclear Power Plants, Version 3.0
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This regulatory document consolidates the requirements and guidance of the Canadian Nuclear Safety Commission (CNSC) for reports and, notifications to and the filing of specific records with the CNSC by licensees of nuclear power plants (NPPs), as well as the applicable time frames for reporting. Licensees are required to report to or notify the CNSC of situations, events, or dangerous occurrences that may require short-term action by the CNSC. They are also required to submit or file other reports, notifications or specific records, including routine scheduled reports on various topics such as certain normal business activities that are required for action by the CNSC, or that are required for longer-term compliance monitoring.
REGDOC-2.13.1 - Safeguards and Nuclear Material Accountancy
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REGDOC-2.13.1, Safeguards and Nuclear Material Accountancy, sets out CNSC requirements and guidance for the establishment and maintenance of a safeguards program.
REGDOC-2.4.5 - Nuclear Fuel Safety and Qualification
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This regulatory document clarifies the regulatory requirements and provides guidance for the design, operation, monitoring, qualification and performance assessment of nuclear fuel. It articulates a set of comprehensive fuel-related regulatory requirements and provides risk-informed guidance that aligns with accepted national and international codes and practices.
REGDOC-3.1.2 - Reporting Requirements, Volume I: Non-Power Reactor Class I Nuclear Facilities and Uranium Mines and Mills, Version 1.1
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This regulatory document sets out requirements and guidance for reports and notifications that licensees of Class I nuclear facilities (excluding power reactors) and of uranium mines and mills must submit to the Canadian Nuclear Safety Commission (CNSC). This document presents the types of reports and the applicable timeframe for reporting. Licensees are required to report to the CNSC regarding situations, events and dangerous occurrences that may require short-term action by the CNSC. Licensees must also submit an annual compliance monitoring report. Licensees are also required to provide notification of certain normal business activities (such as work disruptions or financial status) and to file specific records with the CNSC in accordance with the Nuclear Safety and Control Act (NSCA) and the regulations made under the NSCA.
REGDOC-3.1.3 - Reporting Requirements for Waste Nuclear Substance Licensees, Class II Nuclear Facilities and Users of Prescribed Equipment, Nuclear Substances and Radiation Devices
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This regulatory document sets out requirements and guidance for reports and notifications that licensees of waste nuclear substances, Class II nuclear facilities and users of prescribed equipment, nuclear substances and radiation devices must submit to the Canadian Nuclear Safety Commission (CNSC). This document also presents the types of reports and the applicable timeframe for reporting. Licensees and those who transport nuclear substances are required to report to the CNSC regarding situations, events and dangerous occurrences. Regulatory document REGDOC-3.1.3 incorporates and clarifies requirements found in the Nuclear Safety and Control Act (NSCA) and regulations made under the NSCA, including requirements for content and timing of reports. Additionally, it provides guidance on the interpretation and scope of application of these requirements in the context of Class II nuclear facilities, nuclear substances and radiation devicesand waste nuclear substance licensees. Further to the reporting requirements set by the NSCA and the regulations, a licence may contain any term or condition that identifies a reporting requirement and the time frame for submitting the report. This document provides guidance on these licence conditions, including the submission of an annual compliance report (ACR).
REGDOC-2.4.3 - Nuclear Criticality Safety, Version 1.1
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This regulatory document sets out requirements for nuclear criticality safety and provides guidance on how those requirements may be met. It provides information for the prevention of criticality accidents in the handling, storage, processing, and transportation of fissionable materials and the long-term management of nuclear waste.
REGDOC-2.3.2 - Accident Management, Version 2.0
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REGDOC-2.3.2, Accident Management, sets out the requirements and guidance of the Canadian Nuclear Safety Commission (CNSC) for the development, implementation and validation of integrated accident management for reactor facilities.