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CSA A123.21:26 – Standard test method for the dynamic wind uplift resistance of membrane-roofing systems

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236

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CAN/CSA-A123.2-03 (R2023) – Asphalt-coated roofing sheets

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150

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A123.23-15 (R2025) – Product specification for polymer-modified bitumen sheet, prefabricated and reinforced

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118

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CSA A123.24:21 (R2026) – Standard test method for wind resistance of vegetated roof assembly

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161

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CSA A123.25:18 (R2023) – Asphalt core boards used in roofing

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197

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A123.3-05 (R2020) – Asphalt saturated organic roofing felt

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CAN/CSA-A123.4-04 (R2023) – Asphalt for constructing built-up roof coverings and waterproofing systems

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CSA A123.5:16 (R2020) – Asphalt shingles made from glass felt and surfaced with mineral granules

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N290.18-17 (R2022)

N290.18-17 (R2022) – Periodic safety review for nuclear power plants

CDN $1,715.00

Periodic safety review for nuclear power plants

SKU: 2425237 Categories: ,

Description

Preface This is the first edition of CSA N290.18, Periodic safety review for nuclear power plants. This Standard provides requirements regarding the conduct of a periodic safety review in accordance with CNSC regulatory document REGDOC-2.3.3, Periodic Safety Reviews. This Standard is consistent with the IAEA’s Specific Safety Guide No. SSG-25, Periodic Safety Review for Nuclear Power Plants. Users of this Standard are reminded that the site selection, design, manufacture, construction, installation, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the Nuclear Safety and Control Act and its Regulations. The Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard. The CSA N-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. The CSA N286 Standard provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system. This Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements. This Standard was prepared by the Subcommittee on Periodic Safety Review for Nuclear Power Plants under the jurisdiction of the Technical Committee on Reactor Safety and Risk Management and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Scope 1.1 This Standard provides requirements and guidance related to the performance of periodic safety reviews (PSRs) for nuclear power plants (NPPs). Note: This Standard may be used to provide guidance for nuclear facilities other than NPPs using a graded approach. 1.2 This Standard provides specific requirements and guidance related to the PSR for a) development of the basis document; b) conducting reviews of modern requirements documents and practices; c) conducting safety factor reviews, including identification of safety factor findings; d) analysis of safety factor findings, including consolidation of identified gaps and strengths, development of global issues, and preparation of a global assessment report (GAR); and e) preparation of the integrated implementation plan (IIP) where the developed global issues are resolved into actions. 1.3 This Standard identifies required deliverables that will help facilitate achieving the objectives of the PSR process. 1.4 In this Standard, “shall” is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the Standard; “should” is used to express a recommendation or that which is advised but not required; and “may” is used to express an option or that which is permissible within the limits of the Standard. Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material. Notes to tables and figures are considered part of the table or figure and may be written as requirements. Annexes are designated normative (mandatory) or informative (non-mandatory) to define their application. 1.5 In this Standard, “shall be considered” or “shall consider” means that the user evaluates the impact and documents any decisions. Note: Decisions could include no action.

Edition

Not found

Published Date

2026-10-05

Status

Not found

Pages

61

Language Detail Icon

English

Format Secure Icon

Secure PDF

Abstract

Preface This is the first edition of CSA N290.18, Periodic safety review for nuclear power plants. This Standard provides requirements regarding the conduct of a periodic safety review in accordance with CNSC regulatory document REGDOC-2.3.3, Periodic Safety Reviews. This Standard is consistent with the IAEA’s Specific Safety Guide No. SSG-25, Periodic Safety Review for Nuclear Power Plants. Users of this Standard are reminded that the site selection, design, manufacture, construction, installation, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the Nuclear Safety and Control Act and its Regulations. The Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard. The CSA N-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. The CSA N286 Standard provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system. This Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements. This Standard was prepared by the Subcommittee on Periodic Safety Review for Nuclear Power Plants under the jurisdiction of the Technical Committee on Reactor Safety and Risk Management and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Scope 1.1 This Standard provides requirements and guidance related to the performance of periodic safety reviews (PSRs) for nuclear power plants (NPPs). Note: This Standard may be used to provide guidance for nuclear facilities other than NPPs using a graded approach. 1.2 This Standard provides specific requirements and guidance related to the PSR for a) development of the basis document; b) conducting reviews of modern requirements documents and practices; c) conducting safety factor reviews, including identification of safety factor findings; d) analysis of safety factor findings, including consolidation of identified gaps and strengths, development of global issues, and preparation of a global assessment report (GAR); and e) preparation of the integrated implementation plan (IIP) where the developed global issues are resolved into actions. 1.3 This Standard identifies required deliverables that will help facilitate achieving the objectives of the PSR process. 1.4 In this Standard, "shall" is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the Standard; "should" is used to express a recommendation or that which is advised but not required; and "may" is used to express an option or that which is permissible within the limits of the Standard. Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material. Notes to tables and figures are considered part of the table or figure and may be written as requirements. Annexes are designated normative (mandatory) or informative (non-mandatory) to define their application. 1.5 In this Standard, "shall be considered" or "shall consider" means that the user evaluates the impact and documents any decisions. Note: Decisions could include no action.

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