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-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-2.3.1 - Conduct of Licensed Activities: Construction and Commissioning Programs

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This document provides a framework within which the requirements and guidance in other regulatory documents, codes, and standards may be used in construction and commissioning activities. This framework contributes to ensuring that the construction and commissioning of the plant is effectively managed and consistent with design requirements.

REGDOC-2.4.2 - Probabilistic Safety Assessment (PSA) for Reactor Facilities, Version 2.0

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The purpose of this regulatory document, when incorporated into a licence to construct or operate a reactor facility or other legally enforceable instrument, is to ensure that the licensee conducts a probabilistic safety assessment (PSA) in accordance with defined requirements.

REGDOC-2.6.3 - Aging Management

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REGDOC-2.6.3, Aging Management, sets out the requirements of the CNSC for managing the aging of structures, systems and components (SSCs) of a power reactor facility. Guidance is also provided as to how these requirements may be met. Managing the aging of a reactor facility means to ensure the availability of required safety functions throughout the facility’s service life, with consideration given to changes that occur over time and with use. This requires addressing both physical aging and obsolescence of SSCs where this can, directly or indirectly, have an adverse effect on the safe operation of the reactor facility. This document is intended for use by licensees and applicants in establishing, implementing and improving aging management (AM) programs and plans for reactor facilities.

REGDOC-2.6.1 - Reliability Programs for Nuclear Power Plants

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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.

REGDOC-2.4.4 - Safety Analysis for Class IB Nuclear Facilities

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This regulatory document clarifies requirements and provides guidance for applicants and licensees on how to demonstrate the safety of a Class IB nuclear facility, including information relating to: • the safety analysis program (the managed process that governs the conduct of a safety analysis) • the conduct of a safety analysis (the systematic evaluation of the potential hazards) • safety analysis documents, records and reporting

REGDOC-3.5.4 - Pre-Licensing Review of a Vendor’s Reactor Design

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This document describes the pre-licensing review process provided by the CNSC for assessing a vendor’s reactor design. The review considers the areas of design that relate to reactor safety, security and safeguards.

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.