Licence Application Guide: Licenceto Prepare Site for a Deep
Geological Repository
REGDOC-1.2.3

April 2024

Licence Application Guide: Licence to Prepare Site for a Deep Geological Repository
Regulatory document REGDOC1.2.3© His Majesty the King in Right of Canada, as represented by the Minister of Natural Resources, 2024
Cat. No. CC172-257/2024E-PDF
ISBN 978-0-660-70711-2
Extracts from this document may be reproduced for individual use without permission provided thesource is fully acknowledged. However, reproduction in whole or in part for purposes of resale orredistribution requires prior written permission from the CNSC.
Également publié en français sous le titre : REGDOC-1.2.3, Guide de présentation d’une demande depermis : Permis de préparation de l’emplacement d’un dépôt géologique en profondeur
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This document can be viewed on the CNSC website. To request a copy of the document in English or
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Canadian Nuclear Safety Commission
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Publishing history
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Licence Application Guide: Licence to Prepare Site for a Deep Geological Repository

PrefaceThis regulatory document is part of the CNSC’s regulated facilities and activities series of regulatory
documents. The full list of regulatory document series is included at the end of this document and canalso be found on the CNSC’s website.
In accordance with the Nuclear Safety and Control Act (NSCA) and regulations made under it, a person
must have a licence issued by the CNSC to prepare a site for a Deep Geological Repository (DGR).
The CNSC uses a comprehensive licensing system that covers the lifecycle of a DGR. This regulatory
document, REGDOC-1.2.3, Licence Application Guide: Licence to Prepare Site for a Deep Geological
Repository, provides clarity on the requirements and guidance for preparing an application for a licence toprepare a site for a DGR.
A graded approach, commensurate with risk, may be defined and used when applying the requirements
and guidance contained in this regulatory document. The use of a graded approach is not a relaxation ofrequirements. With a graded approach, requirements are applied in proportion to the risks and particularcharacteristics of the facility or licensed activity.
For information on the implementation of regulatory documents and the graded approach, see REGDOC3.5.3, Regulatory Fundamentals [1]. Information on the relevance of the graded approach to thisregulatory document is found in clause 4.4 of CSA N-292.7, Deep geological disposal of radioactive
waste and irradiated fuel [2].
The words “shall” and “must” are used to express requirements to be satisfied by the licensee or licenceapplicant. “Should” is used to express guidance or that which is advised. “May” is used to express an
option or that which is permissible within the limits of this regulatory document. “Can” is used to express
possibility or capability.
Nothing contained in this document is to be construed as relieving any licensee from any other pertinent
requirements. It is the licensee’s responsibility to identify and comply with all applicable regulations andlicence conditions.

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Table of Contents
1.

Introduction .................................................................................................................................... 4
1.1
1.2
1.3
1.4

2.

Background on the DGR Licensing Process ................................................................................ 6
2.1
2.2
2.3
2.4
2.5

3.

Overview of site preparation ............................................................................................... 7
Site evaluation..................................................................................................................... 8
Site characterization ............................................................................................................ 8
Monitoring and surveillance ............................................................................................... 8
Post-closure safety case ...................................................................................................... 9

Regulatory Requirements and Guidance..................................................................................... 9
3.1
3.2
3.3
3.4
3.5
3.6
3.7
3.8
3.9
3.10
3.11
3.12
3.13
3.14
3.15
3.16

4.

Purpose................................................................................................................................ 4
Scope................................................................................................................................... 4
Relevant legislation............................................................................................................. 5
Waste management framework and standards .................................................................... 6

Management system ........................................................................................................... 9
Human performance management .................................................................................... 11
Operating performance ..................................................................................................... 11
Safety analysis .................................................................................................................. 12
Physical design ................................................................................................................. 12
Fitness for service ............................................................................................................. 13
Radiation protection .......................................................................................................... 13
Conventional health and safety ......................................................................................... 13
Environmental protection.................................................................................................. 13
Emergency management and fire protection .................................................................... 14
Waste management ........................................................................................................... 15
Security ............................................................................................................................. 16
Safeguards and non-proliferation...................................................................................... 16
Packaging and transport .................................................................................................... 17
Reporting .......................................................................................................................... 17
Indigenous and public engagement ................................................................................... 17

Standard application information .............................................................................................. 17
4.1
4.2
4.3
4.4
4.5
4.6
4.7
4.8
4.9
4.10
4.11
4.12
4.13
4.14
4.15

Statement of purpose ........................................................................................................ 17
Licence period................................................................................................................... 18
Description of site ............................................................................................................. 18
Applicant’s name and business address ............................................................................ 18
Mailing address ................................................................................................................. 18
Authority to act ................................................................................................................. 18
Applicant authority ........................................................................................................... 19
Proof of legal status .......................................................................................................... 19
Owner or authority for the site .......................................................................................... 19
Other information ............................................................................................................. 19
Cost recovery .................................................................................................................... 20
Financial guarantees ......................................................................................................... 20
Billing contact person ....................................................................................................... 20
Notification ....................................................................................................................... 20
Structuring the application ................................................................................................ 20

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Submitting the application ................................................................................................ 20

Appendix A: Reference Documents by Safety and Control Area......................................................... 22
Appendix B: Sample Format for Supporting Documentation .............................................................. 28
Glossary ..................................................................................................................................................... 29
References .................................................................................................................................................. 30
Additional Information ............................................................................................................................ 32

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Licence to Prepare Site for a Deep Geological Repository
1.

Introduction
1.1

PurposeThis document is a licence application guide, which is a specific type of guidance document thatmaps relevant regulatory documents and technical standards to topics, to inform the licenceapplication process. This regulatory document provides clarity about the requirements andguidance on the information needed to apply for a licence to prepare site for a deep geologicalrepository (DGR) facility.
A DGR is a facility where radioactive waste is placed in a deep, stable, geological formation(usually several hundred metres or more below the surface). The facility is engineered to isolate
and contain radioactive waste to ensure the long-term isolation of nuclear substances from thebiosphere.
In this document, two key terms are used with respect to a DGR’s lifecycle: pre-closure andpost-closure. The pre-closure period encompasses site preparation, construction, operation andclosure, while the post-closure period follows the closure of a DGR facility.
The information in an application for a licence to prepare site and its referenced documents serves
several purposes:••••

provides the safety case for the site preparation phase of the project, which is incorporated
into the licensing basis for the site preparation activities
documents the conditions of the site and surrounding region that must be addressed in any
technologies being considered, and associated safety and control measuresdemonstrates that any technologies under consideration for the site will be able to withstandthe conditions imposed on the facility by the site and its surroundings
demonstrates that the available site characteristic data support the post-closure safety caseNote: Applicants are to apply the graded approach as outlined in REGDOC-3.5.3 [1] to any
requirements or guidance referenced in this document.
1.2

Scope

This document describes the licensing requirements and guidance associated with the Nuclear
Safety and Control Act (NSCA) and its regulations, to obtain a licence to prepare site for a DGR,
in particular the requirements and guidance associated with the specific areas relevant to thislicensing stage.
This document does:
•
•
•
•
•

not provide guidance on finding or selecting a site
not apply to disposal facility types other than DGR facilities
not apply to surface and near-surface waste management facilities
not apply to waste from uranium mines and mills
not apply to surface facilities and other ancillary facilities associated with a DGR, such as
packaging plants, storage facilities, and water treatment plants

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not describe the requirements and guidance needed for a safety case for disposal facilities
not replace the federal impact assessment requirements

Under Canada’s current environmental review framework, a proposed DGR facility is a
designated project under the Impact Assessment Act (IAA). Information on the integrated impact
assessment process can be found at canada.ca/IAAC.
1.3

Relevant legislation

The following provisions of the NSCA and the regulations made under it are relevant to thisdocument:
NSCA:
•
•

subsection 24(2), 24(4)paragraphs 21(1)(a), 26(a), (b) and (e)Canadian Nuclear Safety Commission Cost Recovery Fees Regulations (CNSCCRFR):•

part 2

Class I Nuclear Facilities Regulations (CINFR):•

sections 3, 4

General Nuclear Safety and Control Regulations (GNSCR):•••

sections 3, 15, 17, 21, 22, 23, 27, 28, 29, 30, 31 and 32
subsections 3(2), 12(1), 23(2), 28(1)paragraph 3(1)(b), (c), (d), (e), (f), (g), (h), (i), (j) and (k), 10(b), 12(1)(a), (b), (c), (d), (e), (f),(g), (h), (i) and (j), 17(b), (c) and (e), 20(d), 21(1)(a), 29(1)(d), (h), and (i)Nuclear Non-Proliferation Import and Export Control Regulations (NNPIECR):•

section 3

Nuclear Security Regulations (NSR):•

section 48

Nuclear Substances and Radiation Devices Regulations (NSRDR):••

paragraphs 36(1)(a) and (d)subsection 36(1)Radiation Protection Regulations (RPR):•••

sections 4, 13, 14, 15, 20, 21, 22 and 23
subsection 1(3)paragraph 4(b)

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REGDOC-1.2.3, Licence Application Guide: Licence to Prepare Site for a Deep Geological Repositorysubparagraph 4(a)(ii)

Note: While each section of the regulatory document addresses select requirements related to thesafety and control area (SCA) or other topic of regulatory importance, applicants are responsible
for ensuring that all requirements for the proposed activities under the NSCA and regulations are
addressed in an application.
The CNSC also considers pertinent legislation from other government departments, such as:
•
•
•
•
•
1.4

Impact Assessment Act
United Nations Declaration on the Rights of Indigenous Peoples Act
Canadian Environmental Protection Act, 1999
Species at Risk Act
Migratory Birds Convention Act, 1994
Waste management framework and standards

The CNSC’s regulatory framework for waste management includes the following relevant
regulatory documents:
•
•
•
•
•
•

REGDOC-1.2.1, Guidance on Deep Geological Repository Site Characterization [3]REGDOC-2.11, Framework for Radioactive Waste Management and Decommissioning in
Canada [4]
REGDOC-2.11.1, Waste Management, Volume I: Management of Radioactive Waste [5]REGDOC-2.11.1, Waste Management, Volume III: Safety Case for Disposal of Radioactive
Waste [6]REGDOC-2.11.2, Decommissioning [7]
REGDOC-3.3.1, Financial Guarantees for Decommissioning of Nuclear Facilities andTermination of Licensed Activities [8]Key principles and elements articulated in this document are consistent with national andinternational standards. This document is complemented by CSA N292.7, Deep geologicaldisposal of radioactive waste and irradiated fuel [2], which provides specific criteria associatedwith many of the topics covered.

2.

Background on the DGR Licensing Process
The CNSC’s licensing of a DGR facility begins after site selection, starting with site preparationand ending with decommissioning. The licensing phases are sequential; however, activities
associated with a particular phase are expected to occur in parallel and continue across licensing
phases. These activities are shown at the bottom of Figure 1 and include site evaluation andcharacterization, monitoring and surveillance, design, development of the post-closure safety caseand engagement with the public and Indigenous Nations and communities.
The safety case for disposal is the main tool used to assess the safety of a DGR facility over its
lifecycle (see section 3.4 of this document). The safety case is updated iteratively at eachlicensing phase and is reviewed by the Commission before making any decision.
The CNSC’s lifecycle approach also requires an applicant to plan for decommissioning
throughout the duration of each licensed activity. The requirements associated with

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decommissioning planning during site preparation are provided in REGDOC-2.11.2 [7] (see also
section 3.11 of this document).
This document provides information for DGR site preparation and does not provide guidance on
future DGR licensing phases.
Figure 1: Licensing stages and lifecycle activities for a deep geological repository

Caption: The figure above shows the licensing phases and typical activities for a DGR.
Note that at each licensing phase, the applicant will consider information gathered from its public
and Indigenous engagement activities as an input into site evaluation and for the development ofenvironmental monitoring and surveillance programs, for example. This includes considering
Indigenous knowledge and historical and current land use by members of the public andIndigenous Nations and communities. The applicant must also consider the other lifecycle
activities at each licensing phase, except for design.
2.1

Overview of site preparation

The applicant is required to have a licence to prepare site before any site preparation work for a
DGR facility begins. Site preparation is expected to take place over several years and typicallyinvolves a range of activities, including the following:
•
•
•
•
•
•
•

clearing vegetation and grubbing
grading
fencing
installation of project infrastructure, including a power supply and utilities
establishing site access roads and parking
construction of flood protection and erosion control measuresconstruction of surface non-nuclear facility structures, systems and components (SSCs), suchas foundation structures

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REGDOC-1.2.3, Licence Application Guide: Licence to Prepare Site for a Deep Geological Repository

Site evaluation

Site evaluation determines whether the characteristics of a site and the surrounding region areappropriate for the lifecycle activities of a nuclear facility regulated under the NSCA. The processof site evaluation begins before the applicant applies for a licence to prepare a site and continues
throughout the lifecycle of a DGR facility. Information from the site evaluation is a key input into
DGR facility design and safety case and informs environmental reviews. Continued evaluation
ensures that the facility’s design basis and safety case will remain current with potential changing
environmental conditions or modifications to the facility itself.
Site evaluation activities carried out during the site preparation stage of a DGR facility includesite characterization and the continued development and update of a safety case for both thepre- and post-closure periods.
The expectations regarding site evaluation for a DGR facility are provided in CSA N292.7 [2].
2.3

Site characterization

The applicant must describe the planned activities and provide data about the site characteristics
in their application for a licence to prepare site for a DGR facility. Site characterization data areused to develop an understanding of the site and how it is expected to evolve over time. It isessential information for assessing radioactive waste containment and isolation from theenvironment over a geologically long timeframe. Site characterization information is part of site
evaluation and a component of the post-closure safety case. The applicant begins collecting data
before submitting a licence application and continues doing so throughout the licensed phases of
the DGR facility.
The CNSC’s requirements for site characterization for radioactive waste disposal facilities, which
include DGRs, are found in the following regulatory documents:•••

REGDOC-2.11.1, Waste Management, Volume I: Management of Radioactive Waste [5],subsection 11.2, which specifies the requirement for the site to be characterized at a level ofdetail sufficient to support an understanding of the current site characteristics and how thesite is expected to evolve over time.
REGDOC-2.11.1, Waste Management, Volume III: Safety Case for the Disposal ofRadioactive Waste [6], subsection 7.3, which specifies that site characterization is required
information as part of the disposal system description and in subsection 7.4 that, as part of thesafety assessment, the quality of the site characterization data must also be ensured.
CSA N292.7 [2], clause 6 provides detailed criteria and guidance for site evaluation and sitecharacterization for a DGR facility. Table 1 in CSA N292.7 [2] also describes the role of sitecharacterization throughout the lifecycle of a DGR facility.

For guidance on site characterization for DGR facilities and the role of site characterization in the
CNSC’s regulatory process, see REGDOC-1.2.1 [3].
2.4

Monitoring and surveillance

The applicant must provide a plan for monitoring the effects of site preparation activities on theenvironment as part of the application for a licence to prepare site (section 3.9).

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The expectations regarding a monitoring and surveillance program for a DGR facility areprovided in CSA N292.7 [2] and in REGDOC-2.11.1, Waste Management, Volume I [5].
2.5

Post-closure safety case

The applicant must provide a post-closure safety case in support of a licence to prepare site
application for a DGR facility. The requirements and guidance for developing a post-closure
safety case are provided in REGDOC-2.11.1, Waste Management, Volume III [6].
CSA N292.7 [2], clause 9 outlines the criteria for ongoing site evaluation using analyticalassessment, such as quantitative modelling of the facility over time. Table 2 in CSA N292.7 [2]further describes the role of analytical assessments, including those central to the post-closure
safety case, throughout the lifecycle of a DGR facility.

3.

Regulatory Requirements and Guidance
For activities that take place during the site preparation stage for the development of a futurenuclear facility, the applicant must clearly demonstrate what measures will be taken to protect
health, safety, security and the environment.
To demonstrate this, the licence to prepare site application must provide information to address
all:
•
•
•

relevant requirements in the NSCA
requirements in regulations made under the NSCA
relevant requirements in the CNSC’s regulatory framework

This includes providing sufficiently detailed information about the safety policies, programs,
procedures and safety and control measures. CNSC staff use 14 SCAs to assess, review, verify
and report on regulatory requirements and performance across all regulated facilities andactivities.
For each SCA, the applicant must consider the proposed design of the DGR when addressing any
requirements. The applicant should also provide information to address the associated guidance,
relative to the design of the proposed DGR facility.
This section describes the requirements and guidance for the SCAs that are applicable to site
preparation for a DGR, as well as other regulatory areas, including reporting and public andIndigenous engagement.
For more information on the SCAs and licensing basis, see REGDOC-3.5.3. Regulatory
Fundamentals [1]. Note that Appendix A provides a list of reference documents by relevant
specific area within each SCA.
3.1

Management system

The application must describe the management system programs, processes and procedures thathave been or will be defined and implemented to protect health, safety, security and theenvironment, as well as provide a description of the organizational management structure for the

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application’s site preparation work activities, in accordance with CSA N286, Management system
requirements for nuclear facilities [9].
The applicant’s management system must include:
•
•

•
•
•
•
•
•
•
•

a clear structure that reflects a logical hierarchy of processes and procedures that is aligned
and integrated with the applicant’s business purpose and safety culture
the applicant’s organizational structure and resources for the duration of the activities,
including:• verification that adequate organizational structures and resources will be in place to meetthe nuclear safety management needs of the activities• top-level organizational charts with references to the full organizational charts, including
the staffing levels• use of contracted resources to supplement in-house capability• how organizational changes will be managed• key dates and milestones for the anticipated site preparation work activities
procedures to control the effectiveness of assessments and engineering activities performed in
the different stages of the site evaluation process
records of all work carried out during site evaluation and site characterization
methods for preservation of records
respective design and safety analysis; supply chain and contractor management programs;
processes and procedures in cases where there may be the need for early procurement of SSC
to accommodate early use or long (critical path) procurement spans, such as long-lead items
documentation about technical knowledge that will be maintained and managed
documentation on the resources to control the work performed by contractors; in particular,
defining the requirements for the activities, and description of oversight and integration
documentation on the results of studies, including models and simulations; and investigations
in sufficient detail to permit independent review
a configuration management program to ensure and maintain consistency among design
requirements, physical configuration and configuration documentation

The applicant must also ensure, as a contractual obligation, that the applicant and the CNSC will
have right of access to the premises of any supplier and sub-supplier carrying out licensed
activities.
The applicant’s management system should account for:
•
•
•
•
•
•
•
•
•

data control, verification and validation
data format
traceability of data
configuration control, including data, for environmental, meteorological, geological,
geophysical, survey, hydrological, biological factors
measuring and test equipment
use and control of computer modellingfield and laboratory work control
calculations and analyses
measures to ensure that the results of the site characterization are accurate, complete,
reproducible, traceable and verifiable

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reporting the results of all site evaluation and site characterization work, laboratory tests andgeotechnical analyses and evaluations
changes to prescribed information

The applicant should involve workers with extensive experience and knowledge who can perform
technical and engineering analyses and synthesize data from multiple disciplines to provide
correct information about the site’s current and future state when establishing management
system parameters related to site evaluation. Note: The parameters and analyses may not lendthemselves to direct verification by inspections, tests, or other techniques that can be defined andcontrolled. In such cases, evaluations should be reviewed and verified by individuals or groups
that are independent of those who did the work and the criteria for any review or verification
activity should be documented.
The applicant should demonstrate that they have an approach to foster a healthy safety culture inaccordance with REGDOC-2.1.2, Safety Culture [10].
REGDOC-2.1.1, Management System [11] provides general guidance on management systems.
3.2

Human performance management

For site preparation, human performance management, including worker training, is addressed
under the management system SCA. This means that applicable worker training and humanperformance management provisions and considerations must be described in the management
system. For information on worker training, see CSA N286 [9], clause 4.5.2.
3.3

Operating performance

For activities conducted under the licence to prepare site, the applicant must:••

characterize the risks to health, safety and the environment that may be encountered byworkers and the public
outline the strategy that the applicant will take, including development of mitigation
measures, upon discovery of additional risks to the health and safety of the public that were
not anticipated during the licence application process

Risks to the health and safety of the public in site preparation include:
•
•
•
•
•
•

noise hazards from blasting and operation of heavy machinery
chemical hazards from the handling of fuels, lubricants and other conventional chemicals
used in the construction equipment
mechanical hazards from excavation, earth movement and road building
electrical hazards from installation of construction infrastructure
dust from overburden and rock removal and movement
ground vibration and flying rock hazards from blasting

The applicant’s assessment of risks to the health and safety of workers and the public resulting
from the activities encompassed by the licence to prepare site should include consideration of
accidents and malfunctions that could occur during site preparation activities.

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Where risks to the health and safety of either workers or the public are identified, the applicant
should provide credible research supporting the potential consequences and measures to mitigate
the risks. For example, if site investigation has indicated the presence of a sub-surface hazardous
substance, the applicant should provide an investigation of the effects of that substance, if
unearthed, on the health and safety of workers and the local public. See 3.8 Conventional healthand safety for more information.
3.4

Safety analysis

The application must include:•••

a pre-closure safety analysis that is in accordance with REGDOC-2.4.4, Safety Analysis forClass IB Nuclear Facilities [12], including a deterministic safety analysis focusing on
activities under this licencea hazard analysis focusing on activities under this licence, including:• the analysis of external hazards at the site evaluation stage to confirm that the facility willwithstand events as described in Appendix C of REGDOC-2.4.4 [12]• considerations for both design-basis events and beyond-design-basis events for theoperational phase in accordance with section 4.1 of REGDOC-2.4.4 [12]a post-closure safety assessment that is in accordance with REGDOC-2.11.1, Waste
Management, Volume III [6]Assessment of site suitability forms part of the overall site evaluation. The general criteria forassessing site suitability includes a detailed and methodical site evaluation. The associatedexpectations regarding site evaluation for a DGR facility are provided in CSA N292.7 [2], clause
6.
The applicant should have a credible program for managing safety issues, which includes any
planned or ongoing research and development activities.
3.5

Physical design

The application must include:
•
•
•
•
•

a description of the overall physical design of the facility, the design practices and the safetyconcepts commensurate with the activities being proposed in the licencea description of the approach followed for the general design and the performance of theSSCs, including the means for preparing equipment maintenance and the monitoring of SSCs
to confirm that they will continue to operate during site preparation, as required by the design
the principles, policies, programs, processes and procedures for carrying out site preparation
activities
a description of the design considerations related to human factors as outlined in REGDOC2.5.1, General Design Considerations: Human Factors [13]information on the frequency and severity derived from the characterization of the hazards
resulting from external events in establishing the design basis hazard level, including
uncertainties in the design basis hazard level

The applicant must also provide information on the proposed exclusion zone, including size andboundary, and on the proposed emergency planning regions.

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Additional considerations for the exclusion zone include:•••site footprint optimization from the onset of the project
implications for emergency preparedness based on the physical layout of the facility
security considerations

For structure design and system design at the site preparation stage for a DGR facility, theapplicant should propose design descriptions and guides.
3.6

Fitness for service

The application must include an aging management plan, listing all SSCs important to safety, toprovide for the timely detection and mitigation of the aging effects to ensure integrity andfunctional capacity of the SSCs throughout the pre-closure period. It will also ensure that they are
as described in the pre- and post-closure safety assessments (see Safety analysis). For more
information, see Appendix A of REGDOC-2.6.3, Aging Management [14].
3.7

Radiation protection

The application must describe the approaches for meeting the requirements of the Radiation
Protection Regulations for activities conducted under the licence to prepare site.
The application must describe a radiation protection program and should demonstrate how thedesign of that program is commensurate with any radiological hazards associated with, orencountered during, the licensed activity.
The application must also describe how radiological hazards will be monitored and controlledduring any site preparation activities, as applicable.
For additional guidance on meeting regulatory expectations for radiation protection, including thedevelopment of a radiation protection program and monitoring doses, see REGDOC-2.7.1,
Radiation Protection [15] and REGDOC 2.7.2, Dosimetry, Volume I: Ascertaining Occupational
Dose [16].
3.8

Conventional health and safety

The application must describe the program and implementation of policies to minimize risk to thehealth and safety of workers posed by conventional (non-radiological) hazards in the workplace,including the management of workplace safety hazards and the protection of workers.
The application must provide information detailing compliance to all applicable requirements
under the Canada Labour Code, including all occupational exposure limits for all chemicalcompounds listed under its regulations.
For more information, see REGDOC-2.8.1, Conventional Health and Safety [17].
3.9

Environmental protection

The application must include a comprehensive set of applicable environmental protection
measures, including an environmental risk assessment, environmental management systems,
effluent and emissions control and monitoring program, environmental monitoring program and

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groundwater protection and monitoring program that meet all requirements applicable to site
preparation activities in REGDOC-2.9.1, Environmental Protection: Environmental Principles,
Assessments and Protection Measures [18].
For site preparation, environmental monitoring consists of monitoring the effects of site
preparation activities on the environment.
The applicant must provide the proposed environmental protection policies, programs andprocedures needed for the licensing phase.
3.10 Emergency management and fire protection
Emergency management
The application must describe an emergency preparedness program that meets the requirements
associated with REGDOC-2.10.1, Nuclear Emergency Preparedness and Response [19].
The applicant must provide details of the site emergency response organizations and otherapplicable organizations, including the numbers and positions of all site staff who are assigned toemergency response duties for site preparation activities.
For site preparation activities, applicants must demonstrate that they have:•••included information on arrangements with first responders, provisions for mutual support oraid, and interagency communication requirements (if a memorandum of understanding isestablished with a first responders’ agency, the same must be provided as part of theapplication)
an emergency response plan to ensure that adequate and timely emergency assistance isavailable to protect workers, the public and the integrity of site security, while mitigating
adverse environmental effects during project activities
an emergency preparedness program that maintains an adequate response capability torespond to and mitigate the emergency situations that could occur at the site, including
malevolent acts, medical emergencies, accidents and malfunctions for the site preparation
phase

The applicant’s emergency preparedness program should contain the following elements:•••

a training program for emergency response personnel, commensurate with evolving hazards
at the sitea site hazard change program which, when implemented, can inform emergency preparedness
staff of changing hazards on the licensed site to maintain adequate emergency response
capability for all potential accident situations, including a notification process to allow
emergency response organizations to prepare adequately prior to the introduction of newhazards on the licensed sitereferences to population studies and emergency planning considerations related to the site

All aspects of the emergency preparedness program should be commensurate with the hazards on
the licensed site.
Although hazards of a malevolent nature are not described in this section of the licenceapplication, the applicant must consider the emergency response to such hazards. It should be
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noted that the effects of such hazards are likely to be similar to those of conventional accidents
and malfunctions.
Fire protection
The application must describe a fire protection program to ensure adequate protection against
fires. It should describe how the fire protection activities will be implemented, managed andmonitored to ensure that fire risks are minimized during site preparation activities, as applicable.
3.11 Waste management
Site preparation activities for a DGR facility should not involve the handling of radioactive
materials or the generation of any radioactive wastes. The applicant should consider how tomanage existing onsite hazardous substances that are identified during the site evaluation, as wellas the hazardous substances that will be produced during activities encompassed by the licence toprepare site.
The applicant must address:•••

quantities and physical characteristics, including hazards posed to health and safety, of each
substance or waste, including by-products for each substance or by-product to be regulated orcontrolled, and the relevant list of regulations governing their control
transport, storage and use of hazardous substances
processing and disposal of hazardous wastes

The applicant should characterize all potential hazardous substances and hazardous wastes in alist as follows:
•
•
•
•
•
•
•

name of hazardous substance or hazardous waste
origin of hazardous substance or hazardous wastepossible by-products that could evolve from the hazardous substance or hazardous waste
any interactions between the hazardous substances or hazardous wastes, or between thepossible by-products
anticipated quantity or volume and anticipated form
risks to workers and the public who may be exposed to the hazardous substance hazardous
waste or by-products
how the hazardous substance, hazardous waste or by-products will be processed or disposedof at the site

Preliminary decommissioning planAs part of the application to prepare site, the applicant must:••

demonstrate that the site evaluation process has appropriately considered futuredecommissioning in the planning for the nuclear facility and has adequately considered endof-life decommissioning
prepare a preliminary decommissioning plan in accordance with REGDOC-2.11.2 [7]

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3.12 Security
Applicant submissions and associated correspondence related to security are prescribed
information under the NSCA and must be submitted in a secure manner.
The security program must include an inventory change control process for prescribed
information.
The security measures must provide oversight, management and control, with documented
policies and procedures for prescribed information.
At the site preparation stage, the security program is primarily focused on the protection ofprescribed information. Prescribed equipment is not expected to be part of a licence to prepare
site. The security program is developed in view of the project progressing to the construction
stage.
For site preparation activities, the applicant should include in their security measures:
•
•
•
•
•

a description of the site security policy, which demonstrates that the security quality
assurance criteria are integrated into overall quality assurance
the applicable quality assurance criteria referenced in ISO/IEC 27002:2022, Information
security, cybersecurity and privacy protection — Information security controls [20]a description of procedures and processes that ensure that the required quality is defined andconsistently achieved within the applicant’s security policy
documentation of how site personnel will be trained in security
information on the security system and subsystem availability program, which accounts for
documentation and archiving, and maintaining records of functional testing and routine fieldtesting

The application must describe the cyber security program, processes and procedures that havebeen or will be defined and implemented to comply with CSA N290.7, Cyber security for nuclear
facilities [21].
The applicant’s cyber security program must describe each element of the program specified in
section 4.2 of CSA N290.7 [21], with sufficient detail to show that the cyber threats,vulnerabilities and risks identified in the Site Selection Threat and Risk Assessment (SSTRA) areproperly considered.
The applicant should define operational procedures for protecting cyber essential assets from acyber attack.
Additional guidance is also available in International Atomic Energy Agency (IAEA) NSS No.
17-T, Computer Security Techniques for Nuclear Facilities [22].
3.13 Safeguards and non-proliferation
The applicant must provide a description of the arrangements, as applicable to site preparation,that will permit the CNSC to discharge Canada’s obligations and provide information to the
IAEA, in accordance with REGDOC-2.13.1, Safeguards and Nuclear Material Accountancy [23].

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The applicant should describe the plan to document measures related to a safeguards program forthe full lifecycle of the DGR.
3.14 Packaging and transport
The packaging and transport SCA is not included in an application for a licence to prepare site fora DGR.
3.15 Reporting
With respect to site preparation, the applicant must describe how they will meet the requirementsof REGDOC-3.1.2, Reporting Requirements, Volume I: Non-Power Reactor Class I Nuclear
Facilities and Uranium Mines and Mills [24].
3.16 Indigenous and public engagement
The applicant must provide the CNSC with information about its public and Indigenous
engagement activities as part of its licence application.
The applicant must also describe how their proposed public information and disclosure program
meets the requirements in REGDOC-3.2.1, Public Information and Disclosure [25].
As an agent of the Crown, the CNSC is responsible for fulfilling Canada’s legal duty to consult
and, where appropriate, accommodate Indigenous peoples when CNSC decisions may haveadverse effects on potential or established Indigenous and/or treaty rights.
In fulfilling its consultation obligations, the CNSC may use the information collected andmeasures proposed by licensees to avoid, mitigate or offset adverse effects. REGDOC-3.2.2,
Indigenous Engagement [26] outlines requirements and guidance for applicants whose proposed
projects may raise the Crown’s duty to consult and accommodate. In addition, sections 3.2 and 5
of REGDOC-1.2.1, Guidance on Deep Geological Repository Site Characterization [3], identify
considerations related to Indigenous knowledge and land use.
Conducting engagement activities with the public and Indigenous peoples early in the project
development process, including site evaluation, is expected to result in more effective andefficient consultation practices, strengthen relationships and assist the Crown in meeting its
obligations regarding any potential legal duty to consult and accommodate, as well as reduce therisk of delays in the regulatory review process.

4.

Standard application information
4.1

Statement of purpose

An applicant must complete a licence application when:••requesting a new licence
renewing, amending, replacing or revoking an existing CNSC licence

The application provides details for the licence, which will consequently authorize only specified
activities. The applicant must provide:

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REGDOC-1.2.3, Licence Application Guide: Licence to Prepare Site for a Deep Geological Repositorya description of any nuclear facility and any prescribed equipment or information to beencompassed by the licence
information on all activities to be licensed, as described in any of paragraphs 26(a) to (f) of
the NSCA, and their purpose

For a licence renewal, the activities requested in this application must match those currently listedon the existing CNSC licence.
This information may be provided in summary format; for example, by listing facilities,
equipment or information.
4.2

Licence period

The applicant should state the requested licence period. The licensee may request a specificlicence period to match planned activities or an anticipated change in status.
4.3

Description of site

The application must contain a description of the site of the activity to be licensed, including thelocation of any exclusion zone and any structures within that zone.
For Class I nuclear facilities, the applicant must provide plans showing the location, perimeter,areas, structures and systems of the facility.
4.4

Applicant’s name and business address

The applicant must provide the applicant's name and business address.
The name must be that of the persons or organization applying for the licence, as it appears on the
proof of legal status documentation, such as the proof of incorporation or sole proprietorship.
The applicant should name an individual only if that person is a sole proprietor or will be solely
responsible for the licence.
The business address must be the legal, physical address of the applicant’s head office, including
the complete street name and number, city, province or territory and postal code. A post office
box number is not acceptable.
4.5

Mailing address

If the mailing address is different from the business address, the applicant must provide themailing address, including the complete street name and number, city, province or territory andpostal code.
If no address is provided, any licence issued in response to the application will be mailed to thehead office address. A post office box number is acceptable as a mailing address.
4.6

Authority to act

The applicant must notify the Commission of the persons authorized to act on their behalf in theirdealings with the Commission.

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The applicant should provide a list of names, positions and contact information of all persons who
are authorized by the applicant to interact with the CNSC.
Note: The applicant may request, for security reasons, this information be subject toconfidentiality requirements.
4.7

Applicant authority

The applicant must provide the name, title and contact information—address, email address andtelephone number—of the individual who has the legal signing authority for the application.
The signature of the applicant authority indicates that all statements and representations made in
the application and on supplementary pages are binding on the applicant.
4.8

Proof of legal status

Applicants should provide proof of legal status by appending proof of incorporation, corporation
number or charter. When submitting an application to renew, a revised proof of legal status
should be provided if the applicant’s original organization name has changed.
If the applicant is a corporation, the application should include the following information:
•
•
•
•
•
4.9

corporation’s legal namecorporation number
date of incorporation
jurisdiction of incorporation
registered office address (if different from the head office address)
Owner or authority for the site

The applicant must provide evidence that the applicant is the owner of the site or has authority
from the owner of the site to carry out the activity to be licensed.
4.10 Other information
If applicable, the applicant should describe the relationship of this application to any previous
licences issued by the CNSC for activities at this facility, including any changes to the licensing
basis contained in previous licences.
The applicant should reference any other CNSC licences that apply to the use of other nuclear
substances and authorized activities conducted at the facility; for example, licences for nuclear
substances and radiation devices, dosimetry service, and import/export of controlled nuclear andnuclear-related substances, equipment and information.
Where applicable, the applicant may provide supporting information, including:••

the results of experimental programs, tests or analyses (for example, results of manufacturers’
material tests and qualification data)
those that have been submitted to, received from, or published by a foreign national
regulatory body

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information published by a national agency or an international nuclear agency

4.11 Cost recovery
Where applicable, the application must be accompanied by the appropriate regulatory fee as
outlined in the Canadian Nuclear Safety Commission Cost Recovery Fees Regulations. Anyquestions can be addressed to the CNSC Cost Recovery Advisory Group.
4.12 Financial guarantees
The application must describe the financial guarantees for the costs of decommissioning thefacility or licensed activity according to the NSCA and the GNSCR. The applicant should also
provide a cross-reference to the supporting document regarding the value and form of thefinancial guarantee.
For more information about financial guarantees and licensing, consult REGDOC-3.3.1 [8].
4.13 Billing contact person
The applicant must provide the following information for the person responsible for the licencefee payments:
•
•
•
•

name
positioncontact information (email, telephone, facsimile)
mailing address, if different from the business address

4.14 Notification
The applicant must notify the CNSC within 15 days of any changes to the contact names
identified in the application.
4.15 Structuring the application
The application may be completed in either of Canada’s official languages. The applicant may
choose to organize the information in any structure. However, the applicant is encouraged toorganize the licence application according to the SCA framework to facilitate CNSC staff review.
The CNSC uses SCAs as the technical topics to assess, review, verify and report on regulatory
requirements and performance across all regulated facilities and activities, as outlined in
REGDOC-3.5.3 [1]. This REGDOC also contains information on licensing and certification,
including the licensing basis and other key regulatory concepts, such as the graded approach.
4.16 Submitting the application
The applicant must ensure that the application is complete, dated and signed by the appropriate
authority, that all supporting documents are clearly identified and cross-referenced and submitted
in a secure format to the CNSC Registry at registry-greffe@cnsc-ccsn.gc.ca.

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If the applicant chooses to submit the licence application in printed format, the applicant should
provide two signed and dated printed copies of the application to:
Canadian Nuclear Safety Commission
280 Slater Street
P.O. Box 1046, Station B
Ottawa, ON K1P 5S9CanadaAll information submitted is subject to the Access to Information Act and the Privacy Act. The
applicant must identify, with justification, any material that is subject to confidentiality
requirements and not suitable for public disclosure. Any information that is submitted may bepresented to the Commission to support the licensing decision. Any such information is also
made available to the public upon request, in total or in a redacted form, according to the CNSC’slegal obligations.
The applicant must keep a record of all licence information, as required by section 27 of the
GNSCR.
The CNSC may request additional information from the applicant to further substantiate claims
made in the application or to address any gaps identified in the application.

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Appendix A: Reference Documents by Safety and Control Area
The CNSC’s regulatory requirements and expectations for the safety performance of programs areorganized into a framework made up of 14 safety and control areas (SCAs), which are subdivided into
specific areas.
The table that follows outlines each applicable SCA, their applicable specific areas, and referencematerials that relate to an application to prepare site for a DGR or subsequent licensing stage to facilitate
planning.
Table 1: Reference documents by applicable SCA and specific area
Safety andcontrol area

SpecificareaStandard(s) or
regulatory documents

Management
systemManagement
systemCSA N286-12 Management System Requirements for Nuclear Facilities [9]REGDOC-2.1.1, Management System [11]IAEA GSR Part 2, Leadership and Management for Safety: General Safety
Requirements [A1]
IAEA GS-G-3.1, Application of the Management System for Facilities andActivities [A2]
IAEA GS-G-3.5, The Management System for Nuclear Installations [A3]
ISO 9001:2015, Quality management systems – Requirements [A5]IAEA, No. GS-G-3.4, The Management System for the Predisposal
Management and Disposal of Radioactive Waste [A6]

Organization

CSA N286-12 [9]IAEA GSR Part 2 [A1]
ISO 9001:2015 [A5]IAEA, No. GS-G-3.4 [A6]Performanceassessment,
improvement andmanagement
review

CSA N286-12 [9]Operatingexperience(OPEX)CSA N286-12 [9]ISO 9001:2015 [A5]IAEA, No. GS-G-3.4 [A6]

Changemanagement

CSA N286-12 [9]Safety culture

REGDOC 2.1.2 Safety Culture [10]CSA N286-12 [9]Configuration
management

CSA N286-12 [9]ISO 9001: 2015 [A5]

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SpecificareaStandard(s) or
regulatory documents
IAEA, No. GS-G-3.4 [A6]Records
management

CSA N286-12 [9]ISO 9001: 2015 [A5]IAEA, GS-G-3.4 [A6]
NEA 7421, Preservation of Records, Knowledge and Memory (RK&M)
Across Generations: Final Report of the RK&M Initiative [A7]
NEA 7423, Preservation of Records, Knowledge and Memory (RK&M)
Across Generations: Compiling a Set of Essential Records for a Radioactive
Waste Repository [A8]Management ofcontractors

CSA N286-12 [9]ISO 9001:2015 [A5]Humanperformance
management

Personnel
training

CSA N286-12 [9]REGDOC-2.2.2, Personnel Training [A9]Operatingperformance

Reporting andtrending

REGDOC-3.1.2 Reporting Requirements, Volume I: Non-Power Reactor
Class I Nuclear Facilities and Uranium Mines and Mills [24]Safetyanalysis

Deterministic
safety analysis

CSA N292.0:19 General principles for the management of radioactive waste
and irradiated fuel [A10]
REGDOC 2.4.4 Safety Analysis for Class IB Nuclear Facilities [12]REGDOC-2.11.1, Waste Management, Volume III [6]Hazard analysis

CCME, Canadian Environmental Quality Guidelines [A13]
CEAA, Incorporating climate change considerations in environmental
assessment: general guidance for practitioners [A14]
REGDOC-1.2.1 Guidance on Deep Geological Repository Site
Characterization [3]REGDOC 2.4.4 [12]REGDOC-2.11.1, Waste Management, Volume III [6]REGDOC-2.7.1 Radiation Protection [15]Criticality safety

CSA N292.0:19 [A10]
CSA N292.7 Deep geological disposal of radioactive waste and irradiatedfuel [2]REGDOC-2.4.3, Nuclear Criticality Safety [A16]

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Safety andcontrol area
PhysicaldesignFitness forserviceREGDOC-1.2.3, Licence Application Guide: Licence to Prepare Site for a Deep Geological Repository

SpecificareaStandard(s) or
regulatory documents

Sitecharacterization

REGDOC-1.2.1 [3]REGDOC-2.9.1 Environmental Protection: Environmental Principles,
Assessments and Protection Measures [18]CCME, Canadian Environmental Quality Guidelines, Canadian Water
Quality Guidelines for the Protection of Aquatic Life [A17]
CCME, Canadian Environmental Quality Guidelines, Sediment Quality
Guidelines for the Protection of Aquatic Life [A18]
IAEA, SSG-18, Meteorological and Hydrological Hazards in Site
Evaluation for Nuclear Installations [A19]
CSA N292.7 [2]REGDOC-2.11.1, Waste Management, Volume I [5]REGDOC-2.11.1, Waste Management, Volume III [6]Facility design

REGDOC-2.5.1 General Design Considerations: Human Factors [13]
CSA N292.7 [2]REGDOC-2.11.1, Waste Management, Volume III [6]National Building Code of Canada [A20]

Structure, systemand component
design

IAEA, SSG-14, Geological Disposal Facilities for Radioactive Waste [A43]
National Building Code of Canada [A20]
CSA N285.0, General requirements for pressure-retaining systems andcomponents in CANDU nuclear power plants/Material Standards for reactor
components for CANDU nuclear power plants [A21]
CSA G40.20-13/G40.21-13, General requirements for rolled or welded
structural quality steel / Structural quality steel [A22]
CSA W59-13, Welded steel construction (metal arc welding) [A23]
ASME Boiler and Pressure Vessel Code (BPVC), Section II, Part A: Ferrous
Material Specification; Part C: Specifications of Welding Rods, Electrodes
and Filler Metals [A24]
ASME BPVC, Section III, Division 1, Rules for the Construction of Nuclear
Facility Components [A25]
ASME BPVC, Section III, Division 3, Containments for Transportation andStorage of Spent Nuclear Fuel and High-level Radioactive Material andWaste [A26]
ASME BPVC, Section V, Nondestructive Examination [A27]
ASME BPVC, Section IX, Welding and Brazing Qualification [A28]
CAN/CGSB-48.9712-2014 / (ISO 9712:2012, IDT), Non-destructive testing– Qualification and certification of NDT Personnel [A29]Agingmanagement

REGDOC-2.11.1, Waste Management, Volume I [5]REGDOC-2.6.3 Aging Management [14]CSA N292.0:19 [A10]

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Safety andcontrol area
Radiation
protection

REGDOC-1.2.3, Licence Application Guide: Licence to Prepare Site for a Deep Geological Repository

SpecificareaStandard(s) or
regulatory documents

Application of
ALARA

REGDOC-2.7.1 [15]Worker dose
control

REGDOC-2.7.1 [15]REGDOC 2.7.2, Dosimetry, Volume I [16]Radiation
protection
programperformance

REGDOC-2.7.1 [15]Radiologicalhazard control

REGDOC-2.7.1 [15]Conventional
health andsafetyPerformance,
practices andawareness

Canada Labour CodeREGDOC-2.8.1 Conventional Health and Safety [17]Environmental
protection

Effluent andemissions control(releases)

REGDOC-2.9.1 [18]
CSA N288.0:22, Environmental management of nuclear facilities: Common
Requirements of the CSA N288 series of Standards [A12]
CSA N288.5:22, Effluent and emissions monitoring programs at nuclear
facilities [A34]
CSA N288.8-17, Establishing and implementing action levels for releases tothe environment from nuclear facilities [A32]

Environmental
management
system (EMS)REGDOC-2.9.1 [18]
CSA N288.0:22 [A12]
ISO 14001: 2015 Environmental management systems [A4]

Assessment andmonitoring

REGDOC-2.9.1 [18]
CSA N288.0:22 [A12]
CSA N288.4:19, Environmental monitoring programs at Class I nuclear
facilities and uranium mines and mills [A33]
CSA N288.7:15, Groundwater protection programs at Class I nuclear
facilities and uranium mines and mills [A35]

Environmental
risk assessment

REGDOC-2.9.1 [18]
CSA N288.6-22, Environmental risk assessments at nuclear facilities anduranium mines and mills [A36]
CSA N288.0:22 [A12]
Health Canada, Guidance for Evaluating Human Health Impacts in
Environmental Assessment: Human Health Risk Assessment [A37]

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Safety andcontrol area

Emergency
management
and fireprotection

Wastemanagement

REGDOC-1.2.3, Licence Application Guide: Licence to Prepare Site for a Deep Geological Repository

SpecificareaStandard(s) or
regulatory documents

Protection ofpeopleREGDOC-2.9.1 [18]REGDOC-2.7.1 [15]CSA N288.0:22 [A12]
CSA N288.6:22 [A36]
CSA N288.1:20 Guidelines for modelling radionuclide environmental
transport, fate, and exposure associated with the normal operation of
nuclear facilities [A31]Conventional
emergency
preparedness andresponse

REGDOC-2.10.1 Nuclear Emergency Preparedness and Response [19]REGDOC-3.2.1 Public Information and Disclosure [25]

Nuclearemergency
preparedness andresponse

REGDOC-2.10.1 [19]Fire emergency
preparedness andresponse

REGDOC-2.10.1 [19]National Building Code of Canada [A20]

Wastecharacterization

CSA N292.0:19 [A10]
CSA N292.8:21 Characterization of radioactive waste and irradiated fuel[A38]
REGDOC-2.11.1, Waste Management, Volume I [5]Waste
minimization

REGDOC-2.11.1 [5]CSA N292.0:19 [A10]
CSA N292.5-11 Guideline for the exemption or clearance from regulatory
control of materials that contain, or potentially contain, nuclear substances
[A30]

Waste
management
practices

REGDOC 2.11 [4]REGDOC-2.11.1 [5]CSA N292.0:19 [A10]
CSA N292.8:21 [A38]
CSA N292.5-11 [A30]

Decommissioning REGDOC-2.11.2 Decommissioning [7]
plans

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Safety andcontrol area
Security

Safeguards
and nonproliferation

REGDOC-1.2.3, Licence Application Guide: Licence to Prepare Site for a Deep Geological Repository

SpecificareaStandard(s) or
regulatory documents

Facilities andequipment

REGDOC-2.12.1, High-Security Sites: Volume II: Criteria for Nuclear
Security Systems and Devices [A41]

Security practices

IAEA Nuclear Security Series No.23-G, Security of Nuclear Information[A42]
IAEA NSS No. 30-G, Sustaining a Nuclear Security Regime [A40]

Cyber security

CSA N290.7-21 [21]IAEA Nuclear Security Series No.17-T: Computer Security at Nuclear
Facilities [A39]

Access andassistance to the
IAEA

REGDOC-2.13.1 Safeguards and Nuclear Material Accountancy [23]IAEA INFCIRC/164 [A15]
IAEA INFCIRC/164/Add.1 [A11]

Operational anddesigninformation

REGDOC-2.13.1 [23]IAEA INFCIRC/164 [A15]
IAEA INFCIRC/164/Add.1 [A11]

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Appendix B: Sample Format for Supporting Documentation
The applicant should ensure that the licence application addresses all of the information requested in thislicence application guide. The applicant is encouraged to map the information provided in the application
to the related sections and subsections of this document.
The table below provides a sample format that the applicant may consider for providing a mapping of the
supporting information to the SCA framework, which is how section 3 of this document is organized.
Document
Identifier

Versionno.

Title

Refers to which parte.g. 3.12 Security

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Glossary
For definitions of terms used in this document, refer to REGDOC-3.6, Glossary of CNSC Terminology,
which includes terms and definitions used in the NSCA and the regulations made under it, and in CNSC
regulatory documents and other publications. REGDOC-3.6 is provided for reference and information.
The following terms are either new terms being defined or include revisions to the current definition forthat term. Following public consultation, the final terms and definitions will be submitted for inclusion in
the next version of REGDOC-3.6, Glossary of CNSC Terminology.

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References
The CNSC may include references to information on best practices and standards such as those publishedby Canadian Standards Association (CSA) Group. With permission of the publisher, CSA Group, allnuclear-related CSA standards may be viewed at no cost through the CNSC web page “How to gain freeaccess to all nuclear-related CSA standards”. REGDOCs are available on the CNSC web page“Regulatory documents”.
[1] CNSC, REGDOC-3.5.3, Regulatory Fundamentals, Version 3, Ottawa, 2023.
[2] CSA Group, CSA N-292.7, Deep geological disposal of radioactive waste and irradiated fuel,Mississauga, 2022.
[3] CNSC, REGDOC-1.2.1, Guidance on Deep Geological Repository Site Characterization, Ottawa,
2021.
[4] CNSC, REGDOC-2.11, Framework for Radioactive Waste Management and Decommissioning in
Canada, Ottawa, 2021.
[5] CNSC, REGDOC-2.11.1, Waste Management, Volume I: Management of Radioactive Waste,
Ottawa, 2021.
[6] CNSC, REGDOC-2.11.1, Waste Management, Volume III: Safety Case for the Disposal ofRadioactive Waste, Ottawa, 2021.
[7] CNSC, REGDOC-2.11.2, Decommissioning, Ottawa, 2021.
[8] CNSC, REGDOC-3.3.1, Financial Guarantees for Decommissioning of Nuclear Facilities andTermination of Licensed Activities, Ottawa, 2021.
[9] CSA Group, CSA N286-12, Management System Requirements for Nuclear Facilities, Mississauga,
2012.
[10] CNSC, REGDOC-2.1.2, Safety Culture, Ottawa, 2018.
[11] CNSC, REGDOC-2.1.1, Management System, Ottawa, 2019.
[12] CNSC, REGDOC-2.4.4, Safety Analysis for Class IB Nuclear Facilities, Ottawa, 2020.
[13] CNSC, REGDOC-2.5.1, General Design Considerations: Human Factors, Ottawa, 2019.
[14] CNSC, REGDOC-2.6.3, Aging Management, Ottawa, 2014.
[15] CNSC, REGDOC-2.7.1, Radiation Protection, Ottawa, 2021.
[16] CNSC, REGDOC-2.7.2, Dosimetry, Volume I: Ascertaining Occupational Dose, Ottawa, 2021.
[17] CNSC, REGDOC-2.8.1, Conventional Health and Safety, Ottawa, 2019.

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REGDOC-1.2.3, Licence Application Guide: Licence to Prepare Site for a Deep Geological Repository[18] CNSC, REGDOC-2.9.1, Environmental Principles, Assessments and Protection Measures, Version
1.1, Ottawa, 2017.
[19] CNSC, REGDOC-2.10.1, Nuclear Emergency Preparedness and Response, Ottawa, 2016.
[20] International Organization for Standardization (ISO), ISO 27002:2022, Information security,
cybersecurity and privacy protection — Information security controls, 2022.
[21] CSA Group, CSA N290.7:21, Cyber security for nuclear facilities, Mississauga, 2021.
[22] IAEA, Computer Security Techniques for Nuclear Facilities, IAEA Nuclear Security Series No. 17T (Rev. 1), Vienna, 2021.
[23] CNSC, REGDOC-2.13.1, Safeguards and Nuclear Material Accountancy, Ottawa, 2018.
[24] CNSC, REGDOC-3.1.2, Reporting Requirements, Volume I: Non-Power Reactor Class I Nuclear
Facilities and Uranium Mines and Mills, Ottawa, 2022.
[25] CNSC, REGDOC-3.2.1, Public Information and Disclosure, Version 1, Ottawa, 2018.
[26] CNSC, REGDOC-3.2.2, Indigenous Engagement, Ottawa, 2022.

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Additional Information
The CNSC may recommend additional information on best practices and standards such as thosepublished by CSA Group. With permission of the publisher, CSA Group, all nuclear-related CSA
standards may be viewed at no cost through the CNSC webpage “How to gain free access to all nuclearrelated CSA standards”.
The following documents provide additional information that may be relevant and useful forunderstanding the requirements and guidance provided in this regulatory document:
A1.
A2.
A3.
A4.
A5.
A6.
A7.
A8.
A9.
A10.
A11.
A12.
A13.
A14.
A15.
A16.
A17.
A18.

IAEA, Leadership and Management for Safety, IAEA Safety Standards Series No. GSR Part2, Vienna, 2016.
IAEA, Application of the Management System for Facilities and Activities, IAEA Safety
Standards Series No. GS-G-3.1, Vienna, 2006.
IAEA, The Management System for Nuclear Installations, IAEA Safety Standards Series No.
GS-G-3.5, Vienna, 2009.
International Organization for Standardization (ISO), ISO 14001:2015, Environmental
management systems - Requirements with guidance for use, 2015.
ISO, ISO 9001:2015, Quality management systems - Requirements, 2015.
IAEA, The Management System for the Disposal of Radioactive Waste, IAEA Safety
Standards Series No. GS-G-3.4, Vienna, 2008.
Nuclear Energy Agency (NEA), NEA 7421, Preservation of Records, Knowledge and Memory(RK&M) Across Generations: Final Report of the RK&M Initiative, Organisation for
Economic Co-operation and Development (OECD), Paris, 2019.
NEA, NEA 7423, Preservation of Records, Knowledge and Memory (RK&M) AcrossGenerations: Compiling a Set of Essential Records for a Radioactive Waste Repository,
OECD, Paris, 2019.
CNSC, REGDOC-2.2.2, Personnel Training, Ottawa, 2016.
CSA Group, CSA N292.0:19, General principles for the management of radioactive waste andirradiated fuel, Mississauga, 2019.
IAEA, Protocol Additional to the Agreement between Canada and the IAEA for the
Application of Safeguards in Connection with the Treaty on the Non-Proliferation of Nuclear
Weapons, IAEA INFCIRC/164/Add 1, 2000.
CSA Group, CSA N288.0:22, Environmental management of nuclear facilities: Common
Requirements of the CSA N288 series of Standards, Mississauga, 2022.
Canadian Council of Ministers of the Environment (CCME), Canadian Environmental Quality
Guidelines, https://ccme.ca/en/current-activities/canadian-environmental-quality-guidelines.
Federal-Provincial-Territorial Committee on Climate Change and Environmental Assessment,
Incorporating Climate Change Considerations in Environmental Assessment: General
Guidance for Practitioners, Gatineau, 2003.
IAEA, Agreement between Government of Canada and IAEA for the Application of
Safeguards in Connection with the Treaty on the Non-Proliferation of Nuclear Weapons,
IAEA INFCIRC/164, 1972.
CNSC, REGDOC-2.4.3, Nuclear Criticality Safety, Ottawa, 2020.
CCME, Canadian Environmental Quality Guidelines, Canadian Water Quality Guidelines for
the Protection of Aquatic Life, https://ccme.ca/en/resources/water-aquatic-life.
CCME, Canadian Environmental Quality Guidelines, Sediment Quality Guidelines for theProtection of Aquatic Life, https://ccme.ca/en/resources/sediment.

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A19. IAEA, Meteorological and Hydrological Hazards in Site Evaluation for Nuclear Installations,
IAEA Safety Standards Series No. SSG-18, Vienna, 2011.
A20. National Research Council of Canada, National Building Code of Canada, 2020.
A21. CSA Group, CSA N285.0, General requirements for pressure-retaining systems andcomponents in CANDU nuclear power plants/Material Standards for reactor components for
CANDU nuclear power plants, Mississauga, 2017.
A22. CSA Group, G40.20-13/G40.21-13, General requirements for rolled or welded structuralquality steel / Structural quality steel, Mississauga, 2018.
A23. CSA Group, CSA W59 - Welded steel construction (metal arc welding), Mississauga, 2013.
A24. ASME, Boiler and Pressure Vessel Code (BPVC) Section II-Materials-Part A-Ferrous
Materials Specifications, New York, 2023.
A25. ASME BPVC, Section III, Division 1, Rules for the Construction of Nuclear Facility
Components, New York, 2023.
A26. ASME BPVC, Section III, Division 3, Containments for Transportation and Storage of Spent
Nuclear Fuel and High-level Radioactive Material and Waste, 2023.
A27. ASME BPVC, Section V, Nondestructive Examination, 2023.
A28. ASME BPVC, Section IX, Welding, and Brazing Fusing Qualifications, New York, 2023.
A29. Canadian General Standards Board, CAN/CGSB-48.9712-2014 / (ISO 9712:2012, IDT), Nondestructive testing – Qualification and certification of NDT Personnel, 2014.
A30. CSA Group, CSA N292.5, Guideline for the exemption or clearance from regulatory controlof materials that contain, or potentially contain, nuclear substances, Mississauga, 2011.
A31. CSA Group, CSA N288.1:20, Guidelines for modelling radionuclide environmental transport,
fate, and exposure associated with the normal operation of nuclear facilities, Mississauga,
2020.
A32. CSA Group, CSA N288.8, Establishing and implementing action levels for releases to theenvironment from nuclear facilities, Mississauga, 2017.
A33. CSA Group, CSA N288.4:19, Environmental monitoring programs at nuclear facilities anduranium mines and mills, Mississauga, 2019.
A34. CSA Group, CSA N288.5:22, Effluent and emissions monitoring programs at nuclear
facilities, Mississauga, 2022.
A35. CSA Group, CSA N288.7:15, Groundwater protection programs at Class I nuclear facilities
and uranium mines and mills, Mississauga, 2015.
A36. CSA Group, CSA N288.6:22, Environmental risk assessments at nuclear facilities anduranium mines and mills, Mississauga, 2022.
A37. Health Canada, Guidance for Evaluating Human Health Impacts in Environmental
Assessment: Human Health Risk Assessment, Ottawa, 2019.
A38. CSA N292.8:21, Characterization of radioactive waste and irradiated fuel, Mississauga, 2021.
A39. IAEA, IAEA Nuclear Security Series No.17-T: Computer Security at Nuclear Facilities, 2011.
A40. IAEA, IAEA NSS No. 30-G, Sustaining a Nuclear Security Regime, Vienna, 2018.
A41. CNSC, REGDOC-2.12.1, High-Security Sites: Volume II: Criteria for Nuclear Security
Systems and Devices, Ottawa, 2018.
A42. IAEA, IAEA Nuclear Security Series (NSS) No.23-G, Security of Nuclear Information,
Vienna, 2015.
A43. IAEA. IAEA NSS No. SSG-14, Geological Disposal Facilities for Radioactive Waste, Vienna,
2011.

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CNSC Regulatory Document Series
Facilities and activities within the nuclear sector in Canada are regulated by the CNSC. In addition to the
Nuclear Safety and Control Act and associated regulations, these facilities and activities may also be
required to comply with other regulatory instruments such as regulatory documents or standards.
CNSC regulatory documents are classified under the following categories and series:
Regulated facilities and activities
Series 1.1
1.2
1.3
1.4
1.5
1.6

Reactor facilities
Class IB facilities
Uranium mines and mills
Class II facilities
Certification of prescribed equipment
Nuclear substances and radiation devices

Safety and control areas
Series 2.1
2.2
2.3
2.4
2.5
2.6
2.7
2.8
2.9
2.10
2.11
2.12
2.13
2.14

Management system
Human performance management
Operating performance
Safety analysis
Physical design
Fitness for service
Radiation protection
Conventional health and safety
Environmental protection
Emergency management and fire protection
Waste management
Security
Safeguards and non-proliferation
Packaging and transport

Other regulatory areas
Series 3.1
3.2
3.3
3.4
3.5
3.6

Reporting requirements
Public and Indigenous engagement
Financial guarantees
Commission proceedings
CNSC processes and practices
Glossary of CNSC terminology

Note: The regulatory document series may be adjusted periodically by the CNSC. Each regulatory
document series listed above may contain multiple regulatory documents. Visit the CNSC’s website forthe latest list of regulatory documents.

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