Document History of REGDOC-2.5.2, Design of Reactor Facilities
View REGDOC-2.5.2, Design of Reactor Facilities, Version 2.1
Summary
REGDOC-2.5.2, Design of Reactor Facilities, sets out requirements and guidance for new licence applications for water-cooled reactor facilities. It establishes a set of comprehensive design requirements and guidance that are risk informed and align with accepted international codes and practices.
This document provides criteria pertaining to the safe design of new water-cooled reactor facilities. All aspects of the design are taken into account, and multiple levels of defence are promoted in design considerations. To the extent practicable, the requirements and guidance provided herein are technology neutral with respect to water-cooled reactor facilities. An applicant or licensee may put forward a case to demonstrate that the intent of a requirement is addressed by other means and demonstrated with supportable evidence.
Status
May 2023: Published
Document History
| Document Milestone | Dates | Links |
|---|---|---|
| Publication | May 2023 | REGDOC-2.5.2, Design of Reactor Facilities, Version 2.1 |
| Publication | April 2023 | REGDOC-2.5.2, Design of Reactor Facilities, Version 2 |
| Consultation | January 19, 2021 to April 19, 2021 |
Draft REGDOC-2.5.2, Design of Reactor Facilities, Version 2 [PDF | 173 pages, 1.6 MB]
Comments received [PDF | 23 pages, 312 KB] Comments and feedback are available upon request |
| Publication | May 2014 | REGDOC-2.5.2, Design of Reactor Facilities: Nuclear power Plants [HTML] [PDF, 183 pages, 1.36 MB] |
| Additional consultation | August 22 to October 21, 2013 |
Comments received on REGDOC-2.5.2, Design of Reactor Facilities, Nuclear Power Plants [PDF | 189 pages, 1.33 MB]
Comments and feedback are available upon request |
| Presentation to the Commission | August 22, 2013 |
Presentation of REGDOC-2.5.2
Consultation report [PDF | 6 pages, 54 KB] Comments table [PDF | 143 pages, 1.08 MB] |
| Consultation on GD-337 | September 18 to November 20, 2012 | Comments and feedback are available upon request |
| Consultation on RD-337 | July 26 to October 4, 2012 | Comments and feedback are available upon request |
| Publication | June 2011 | RD-367, Design of Small Reactor Facilities [HTML] [PDF, 69 pages, 471 KB] |
| Publication | November 2008 | RD-337, Design of New Nuclear Power Plants [HTML] [PDF, 92 pages, 571 KB] |
Related CSA Standards
- N290.15, Requirements for the safe operating envelope of nuclear power plants
- N286-12 (R2017), Management system requirements for nuclear facilities
- N286.7, 3rd Edition, Quality assurance of analytical, scientific, and design computer programs
- N286.7-16 (R2021), Guideline for the application of N286.7-99, Quality assurance of analytical, scientific, and design computer programs for nuclear power plants
- N288.2, Guidelines for Calculating Radiation Doses to the Public from a Release of Airborne Radioactive Material under Hypothetical Accident Conditions in Nuclear Reactors
- N285, General requirements for pressure-retaining systems and components in CANDU nuclear power plants
- N290.13, Environmental qualification of equipment for CANDU nuclear power plants
- N290.14, Qualification of Pre-developed Software for Use in Safety Related Instrumentation and Control Applications in Nuclear Power Plants
- N290.6, Requirements for Monitoring and Display of Nuclear Power Plant Safety Functions in the Event of an Accident
- N293, Fire protection for nuclear power plants
- N289, Series on seismic design and qualification
- N289.3, Design procedures for seismic qualification of nuclear power plants
- A23.3, Design of Concrete Structures for concrete structures
- S16, Design of Steel Structures for steel structures
- N287 series on requirements for concrete containment structures for CANDU nuclear power plants
- N287.1, General Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants, for general requirements in documentation of design specification and design reports
- N287.2, Material Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants
- N287.3, Design Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants
- N290.0/N290.3 PACKAGE, General requirements for safety systems of nuclear power plants and Requirements for the containment system of nuclear power plants
- N287.4, Construction, Fabrication and Installation Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants, and N287.5, Examination and Testing Requirements for Concrete Containment Structures for Nuclear Power Plants, for containment construction and inspection
- N287.6, Pre-operational proof and leakage rate testing requirements for concrete containment structures for nuclear power plants, for pressure test before operation
- N291, Requirements for Safety-Related Structures for CANDU Nuclear Power Plants
- N289.5, Seismic Instrumentation Requirements for Nuclear Power Plants and Nuclear Facilities
- N290.4, Requirements for reactor control systems of nuclear power plants
- CAN3-N290.1, Requirements for the Shutdown Systems of CANDU Nuclear Power Plants
- N287.7, In-service Examination and Testing Requirements for Concrete Containment Structures for CANDU Nuclear Power Plants
- N285.4, Periodic inspection of CANDU nuclear power plant components
- N285.5, Periodic inspection of CANDU nuclear power plant components
- N287 series of standards
- N294, Decommissioning of Facilities Containing Nuclear Substances
- N288.4, Environmental monitoring programs at Class I nuclear facilities and uranium mines and mills
- N290.5, Requirements for electrical power and instrument air systems of CANDU nuclear power plants
- N292.3, Management of Low-and Intermediate-level Radioactive Waste
- N289.4, Testing procedures for seismic qualification of nuclear power plants
- N286.7, Quality Assurance of Analytical, Scientific and Design Computer Programs for Nuclear Power Plants
- N288.5, Effluent Monitoring Programs at Class I Nuclear
- N288.9, Guidance for Design of fish Impingement and Entrainment Program at Class I Nuclear Facilities
- N288.6 Environmental Risk Assessment at Class I Nuclear Facilities
- N288.7, Groundwater Protection Program at Class I Nuclear Facilities and Uranium Mines and Mills
How to gain free access to all nuclear related CSA standards
Contact information
For questions and information related to REGDOC-2.5.2, Design of Reactor Facilities, please contact the CNSC Public Information team or send mail to:
Directorate of Assessment and Analysis
Canadian Nuclear Safety Commission
280 Slater St
PO Box 1046 Stn B
Ottawa ON K1P 5S9
Canada
Telephone: 1-800-668-5284 (Canada only)
Fax: 613-995-5086
Related links
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