Preface
This is the seventh edition of CSA N285.4, Periodic inspection of CANDU nuclear power plant components. It supersedes the previous editions, published in 2014, 2009, 2005, 1994, 1983, and 1978. It is one of the CSA N285 series of Standards on CANDU®nuclear power plant components.
Note: CANDU®(CANada Deuterium Uranium) is a Registered trademark of Atomic Energy of Canada Ltd., used under exclusive license by Candu Energy Inc., a Member of the SNC-Lavalin Group.
This Standard provides uniform rules for the periodic inspection of pressure-retaining systems and components in CANDU nuclear power plants. It has been revised and updated to account for new knowledge and experience gained from CANDU research and operations, advances in technology, and changes to the regulatory framework in Canada.
The seventh edition of CSA N285.4 includes the following major changes:
a) an update to definitions, specifically definition related to inspection and examination, affecting most clauses;
b) new reporting requirements for measurement of pressure tube to calandria tube gap at fuel channel annulus spacers and displacement of annulus spacers;
c) requirements for measurement of hydrogen isotope concentration measurement in rolled joint region of pressure tube;
d) modifications to fuel channel annulus spacer material surveillance to provide further clarity on sample size and spacer testing methods to be used;
e) new requirements specified for pressure tube fracture protection assessment and leak before break assessment using in-service pressure tube material properties and operating conditions;
f) updated susceptibility criteria, acceptance standards, and inspection sample size for periodic inspections to address wall thinning and environmentally assisted cracking;
g) provided clarity on which supplementary periodic inspections require qualification of the inspection method/procedure, as per Clause 4.3; and
h) updated acceptance standards and disposition process for visual inspection of components and hangers, including provision of criteria for minor condition disposition.
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 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 may provide more specific direction for those requirements.
Users of this Standard are cautioned that, due to restructuring, a clause in this edition might not be directly comparable to the clause with the corresponding number in the previous edition of this Standard. Users are also reminded that the design, manufacture, construction, commissioning, operation, examination, maintenance, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety and Control Act and Regulations as well as other regulatory documents of the Canadian Nuclear Safety Commission (CNSC). The CNSC might impose additional requirements to those specified in this Standard.
In order to facilitate adoption by the authority having jurisdiction, this Standard includes some regulatory provisions.
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
This Standard defines requirements for the periodic inspection of pressure retaining systems, components, and supports that form part of a CANDU nuclear power plant.
Periodic inspection (see Annex A for additional guidance) is considered to include the fluid boundary portions of components and piping, including their supports that comprise
a) systems containing fluid that directly transports heat from nuclear fuel and other systems whose failure can result in a significant release of radioactive substance;
b) systems essential for the safe shutdown of the reactor or the safe cooling of the fuel, or both, in the event of a process system failure; and
c) other systems or components whose failure could jeopardize the integrity of the systems described in Item a) or b), or both.
In addition, for components exposed to conditions beyond the known experience base, and where such components constitute part of a vital system, the components may be considered suitable for inclusion in the periodic inspection program, as supplementary periodic inspections.
1.2
This Standard addresses
a) failure aspects;
b) classification of areas subject to periodic inspection;
c) provision for access;
d) examination methods 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
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 (nonmandatory) to define their application.
