CSA N285.7:26

Description

Preface This is the third edition of CSA N285.7, Periodic inspection of CANDU nuclear power plant balance of plant systems and components . It supersedes the previous editions published in 2021 and 2015. This Standard provides requirements for the periodic inspection of balance of plant systems and components. This Standard is one of a series of Standards intended to provide uniform requirements for CANDU® nuclear power plants. Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL). The major changes to this edition include the following: a) modified the requirement that inspections be post-pressure test (removal of former Clause 12.1.5.1, confirmatory inspections in Clauses 13.2.2.4, 13.3.2.4, 13.4.2.4, 13.5.2.4, and 13.6.2.4); b) provided direction for cases when a requirement of this Standard cannot be practically implemented (Clause 4.4.5); c) updated the requirements for interface with plant in-service corrosion and erosion inspection programs in Clauses 13.1.3.1 and 13.1.3.3; d) provided additional guidance for crediting existing in-service inspection programs (new Annex H added); e) general harmonization with CSA N285.4:23 and CSA N285.5:22; f) modified Clause 5.2.10 providing provision to determine the need for qualification of examination procedures (Clause 5.2.10); g) clarified the extent of inspection for piping and vessels (Clauses 13.2 and 13.3); h) provided requirements to assess susceptibility to degradation for other type of fluids (other than water/steam) in systems subject to period inspection (modified Clause D.4.1 c)); i) provided new degradation mechanism criteria for systems containing fuel oil (added new Tables D.1F, D.1G, D.1H, D.1I, D.2F, D.2G, D.2H, D.2I, D.3C, D.3D, D.3E, D.3F, D.4E, D.4F, D.4G, D.4H, D.5E, D.5F, D.5G, D.5H, D.7E, and D.7H); j) added scope statement to specify applicability of periodic inspection requirements over life cycle of nuclear power plant (added new Clauses 1.4, 12.1.3, and A.3, updated Clauses 3 and 4.1.3.1); k) updated Table 1 to incorporate the impact of CGSB Visual Testing Certification; l) added clause titles and figure descriptions to address the accessibility requirements in Accessibility for Ontarians with Disabilities Act; and m) added requirements for inspection, material monitoring, and test programs for non-metallic components (added new Clauses 13.1.1.3, D.4.3, and modified Clause D.5.1). The CSA N-Series of Standards provides an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 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. Users of this Standard are reminded that the operation of nuclear facilities in Canada is subject to the requirements of the Nuclear Safety and Control Act and Regulations. The Canadian Nuclear Safety Commission may impose additional requirements to those specified in this Standard. Portions of this Standard have been developed using the Risk Informed In-service Inspection (RI-ISI) methodologies and definitions from ASME BPVC, Section XI with 2011 Addenda, Code Case N-578-1, ASME RA-Sa-2009, and EPRI RI-ISI TR-112657 Rev B-A. Excerpts are reprinted with permission from The American Society of Mechanical Engineers, Electric Power Research Institute, Inc., and International Atomic Energy Agency. In order to facilitate adoption by the authority having jurisdiction, this Standard includes some regulatory provisions. CSA Group acknowledges that the development of this Standard was made possible, in part, by the financial support of Bruce Power, Ontario Power Generation, Canadian Nuclear Safety Commission, New Brunswick Power, Canadian Nuclear Laboratories, Candu Energy Inc. — an AtkinsRéalis Company, BWXT Canada, Cameco Corporation, Kinectrics, Orano Canada Inc., Nuclear Waste Management Organization (NWMO), AECOM, Calian, Framatome Canada Ltd., GE Vernova-Hitachi, Tetra Tech, Westinghouse Electric Canada, and AECL. This Standard was prepared by the Technical Committee on Periodic Inspection of Nuclear Power Plant Components, under the jurisdiction of the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee. Scope 1.1 General This Standard defines requirements for the periodic inspection of balance of plant pressure-retaining systems, components, and supports that form part of a CANDU nuclear power plant using a risk informed in-service inspection (RI-ISI) methodology. Periodic inspection (see Annex A for additional guidance) is considered to include the fluid boundary portions of balance of plant systems, components, and piping, including their supports that comprise a complete nuclear power plant, excluding the following systems or portions thereof: a) Systems, and systems connected thereto, containing the fluid that, under normal conditions, directly transports heat from nuclear fuel, and other systems whose failure can result in a significant release of radioactive substances. Note: These systems or portions of systems are subject to periodic inspection in accordance with Clause 3.3.1 a) in CSA N285.4. b) Systems essential for the safe shutdown of the reactor and/or the safe cooling of the nuclear fuel in the event of a process system failure. Note: These systems or portions of systems are subject to periodic inspection in accordance with Clause 3.3.1 b) in CSA N285.4. Compressors, turbines, generators, engines, internal components of vessels and heat exchangers, and hydraulic or pneumatic cylinders are exempt from the periodic inspection requirements of this Standard. This includes piping internal to equipment or mounted upon equipment that carries fluid from one chamber to another on the same foundation. Note: To arrive at a periodic inspection program, the user should consider the examinations and tests performed by other programs such as pipe wall thinning, vessel examinations, equipment reliability, and maintenance programs in addition to RI-ISI. Examinations performed as part of supporting programs are not expected to be repeated in this periodic inspection program, but should be credited to this periodic inspection program to provide assurance that the program satisfies the intended purpose as described in Annex A. See Annex H for additional detail on crediting of examinations conducted by in-service inspection programs. 1.2 Inclusions This Standard addresses the following requirements: a) failure aspects; b) risk categorization of areas subject to periodic inspection; c) provision for access; d) examination techniques and procedures; e) personnel qualifications; f) frequency of periodic inspection; g) responsibilities; h) documentation; i) records; j) evaluation of periodic inspection results; k) dispositioning; and l) repair, replacement, and modification requirements. 1.3 Units of measurement The values given in SI units are the units of record for the purposes of this Standard. The values given in parentheses are for information and comparison only. 1.4 Application of Standard The requirements of this periodic inspection Standard are applicable to the operational phase of a nuclear power plant, until the fuel is removed from the entire reactor core and up to the time at which systems for cooling of the fuel are drained for the purpose of decommissioning of the reactor core. This periodic inspection Standard does contain requirements for providing access to components for pre-service and in-service examinations (part of the periodic inspection program), and hence the requirements of this Standard should be taken into account during plant design and construction. This periodic inspection Standard does contain provisions for crediting of manufacturing and installation examinations as a baseline record for the periodic inspection program, and hence the requirements of this Standard should be taken into account during plant construction. This periodic inspection Standard is not applicable to the decommissioning phase of the nuclear power plant life cycle. 1.5 Terminology 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.