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CSA N285.5 : 2013

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

PERIODIC INSPECTION OF CANDU NUCLEAR POWER PLANT CONTAINMENT COMPONENTS
Available format(s)

Hardcopy , PDF

Superseded date

07-08-2021

Language(s)

English, French

Published date

01-01-2013

Preface
1 Scope
2 Reference publications
3 Definitions
4 General requirements
5 Inspection methods and procedures
6 Inspection staff
7 Inaugural inspection
8 Periodic inspection
9 Evaluation of results and dispositioning
10 Repair and replacement
11 Modifications
12 Recording requirements and reports
Annex A (informative) - Periodic inspection, material
        property monitoring, and test programs for fiberglass
        reinforced plastic (FRP) containment components
Annex B (informative) - Guide for periodic inspection

Describes requirements for the periodic inspection of containment system components, including containment pressure suppression systems, in CANDU nuclear power plants.

DevelopmentNote
French Edition issued on 01-09-2014. (11/2014)
DocumentType
Standard
Pages
59
PublisherName
Canadian Standards Association
Status
Superseded
SupersededBy
Supersedes

CSA N285.0 : 2006 GENERAL REQUIREMENTS FOR PRESSURE-RETAINING SYSTEMS AND COMPONENTS IN CANDU NUCLEAR POWER PLANTS
CSA N290.1 : 2013 REQUIREMENTS FOR THE SHUTDOWN SYSTEMS OF CANDU NUCLEAR POWER PLANTS
CSA N290.0 & N290.1 PACKAGE : 2013 CONSISTS OF N290.0-11, GENERAL REQUIREMENTS FOR SAFETY SYSTEMS OF NUCLEAR POWER PLANTS AND N290.1-13, REQUIREMENTS FOR THE SHUTDOWN SYSTEMS OF NUCLEAR POWER PLANTS
CSA N285.3 : 0 REQUIREMENTS FOR CONTAINMENT SYSTEMS COMPONENTS IN CANDU NUCLEAR POWER PLANTS
N291-15 Requirements for safety-related structures for nuclear power plants
N285.0-17/N285.6 SERIES-17 General requirements for pressure-retaining systems and components in CANDU nuclear power plants / Material Standards for reactor components for CANDU nuclear power plants
CSA N285.7 : 2015 Periodic inspection of CANDU nuclear power plant balance of plant systems and components<br>
CSA N287.7 : 2017(R2018) IN-SERVICE EXAMINATION AND TESTING REQUIREMENTS FOR CONCRETE CONTAINMENT STRUCTURES FOR NUCLEAR POWER PLANTS
CSA N290.0 & N290.3 PACKAGE : 2016 CONSISTS OF N290.0-11, GENERAL REQUIREMENTS FOR SAFETY SYSTEMS OF NUCLEAR POWER PLANTS AND N290.3-16, REQUIREMENTS FOR THE CONTAINMENT SYSTEM OF NUCLEAR POWER PLANTS
CSA N290.0 & N290.2 PACKAGE : 2017 CONSISTS OF N290.0-17, GENERAL REQUIREMENTS FOR SAFETY SYSTEMS OF NUCLEAR POWER PLANTS AND N290.2-17, REQUIREMENTS FOR EMERGENCY CORE COOLING SYSTEMS OF NUCLEAR POWER PLANTS

CSA N285.0 : 2006 GENERAL REQUIREMENTS FOR PRESSURE-RETAINING SYSTEMS AND COMPONENTS IN CANDU NUCLEAR POWER PLANTS
ISO 9712:2012 Non-destructive testing Qualification and certification of NDT personnel
ASTM D 5229/D5229M : 2014-06 TEST METHOD FOR MOISTURE ABSORPTION PROPERTIES AND EQUILIBRIUM CONDITIONING OF POLYMER MATRIX COMPOSITE MATERIALS
ASTM D 792 : 2013 : REDLINE Standard Test Methods for Density and Specific Gravity (Relative Density) of Plastics by Displacement
CSA N285.6 SERIES : 2005 MATERIAL STANDARDS FOR REACTOR COMPONENTS FOR CANDU NUCLEAR POWER PLANTS
ASTM D 6272 : 2017 : REDLINE Standard Test Method for Flexural Properties of Unreinforced and Reinforced Plastics and Electrical Insulating Materials by Four-Point Bending
N285.4-14 Periodic inspection of CANDU nuclear power plant components
ASTM D 790 : 2017 : REDLINE Standard Test Methods for Flexural Properties of Unreinforced and Reinforced Plastics and Electrical Insulating Materials
ASME PV CODE 5 : 2017 BOILER AND PRESSURE VESSEL CODE - NONDESTRUCTIVE EXAMINATION
CGSB 48.9712 : 2014 NON-DESTRUCTIVE TESTING - QUALIFICATION AND CERTIFICATION OF PERSONNEL
ASTM D 695 : 2015 : REDLINE Standard Test Method for Compressive Properties of Rigid Plastics
ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS

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