REGDOC-1.2.2, Licence Application Guide: Class IB Processing Facilities - Consultation

Consultation on REGDOC-1.2.2, Licence Application Guide: Class IB Processing Facilities, is open from October 12, 2021 to January 10, 202.


This regulatory document is part of the CNSC’s Class IB Facilities series of regulatory documents. The
full list of regulatory document series is included at the end of this document and can also be found on the CNSC’s website.

Regulatory document REGDOC-1.2.2, Licence Application Guide: Class IB Processing Facilities, sets
out requirements and guidance on submitting a formal application to the CNSC to obtain a licence to
prepare a site for, construct, operate and/or decommission a Class IB processing facility in Canada, and
identifies the information that should be included in the application.

This document will be used to assess licence applications for proposed new processing facilities and for
licence renewals for existing processing facilities. Once the Commission has granted a licence, the safety and control measures described in the licence application and the documents needed to support the application will form part of the licensing basis.

This document is the first version.

Consultation on REGDOC-1.2.2, Licence Application Guide: Class IB Processing Facilities, is open from October 12, 2021 to January 10, 202.


This regulatory document is part of the CNSC’s Class IB Facilities series of regulatory documents. The
full list of regulatory document series is included at the end of this document and can also be found on the CNSC’s website.

Regulatory document REGDOC-1.2.2, Licence Application Guide: Class IB Processing Facilities, sets
out requirements and guidance on submitting a formal application to the CNSC to obtain a licence to
prepare a site for, construct, operate and/or decommission a Class IB processing facility in Canada, and
identifies the information that should be included in the application.

This document will be used to assess licence applications for proposed new processing facilities and for
licence renewals for existing processing facilities. Once the Commission has granted a licence, the safety and control measures described in the licence application and the documents needed to support the application will form part of the licensing basis.

This document is the first version.

Read REGDOC-1.2.2

 Preface


 
This regulatory document is part of the CNSC’s Class IB Facilities series of regulatory documents. The
full list of regulatory document series is included at the end of this document and can also be found on the
 
CNSC’s website.


 Regulatory document REGDOC-1.2.2, 
Licence Application Guide: Class IB Processing Facilities, sets
out requirements and guidance on submitting a formal application to the CNSC to obtain a licence to
prepare a site for, construct, operate and/or decommission a Class IB processing facility in Canada, and
 identifies the information that should be included in the application.


This document will be used to assess licence applications for proposed new processing facilities and for
licence renewals for existing processing facilities. Once the Commission has granted a licence, the safety
and control measures described in the licence application and the documents needed to support the
 application will form part of the licensing basis.


 This document is the first version.


For information on the implementation of regulatory documents and on the graded approach, see
 REGDOC-3.5.3, 
Regulatory Fundamentals.


The words “shall” and “must” are used to express requirements to be satisfied by the licensee or
licence applicant. “Should” is used to express guidance or that which is advised. “May” is used to
express an option or that which is advised or 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 and licence conditions.

 


Comment on preface



Licence Application Guide: Class IB Processing Facilities


 
1. Introduction


 
1.1 Purpose
 
This licence application guide identifies the information to be provided in support of an
application for a licence to prepare a site for, construct, operate or decommission a Class IB
 nuclear facility for:


 
· processing, reprocessing or separation of an isotope of uranium, thorium or plutonium;
 
· the manufacturing of a product from uranium, thorium or plutonium; or
 
· processing or use, in a quantity greater than 1015 Bq per calendar year, of nuclear substances
 other than uranium, thorium or plutonium


This guide sets out requirements and guidance on submitting a formal application to the Canadian
 Nuclear Safety Commission (CNSC) to obtain a licence.


Following the information in this regulatory document will prepare applicants to submit the
appropriate information to demonstrate that they are qualified and will make adequate provisions
for the protection of the environment and the health and safety of persons and the maintenance of
national security and measures required to implement international obligations to which Canada
 has agreed.


Comment on Section 1.1 

 


 
1.2 Scope
 
This document is a guide in the preparation of a licence application for a licence to prepare a site
for, construct, operate and/or decommission a proposed new Class IB processing facility or for
 the renewal of a licencefor an existing facility.


Comment on section 1.2


 
1.3 Relevant legislation
 
The following provisions of the Nuclear Safety and Control Act (NSCA, the Act) and the
 regulations made under it are relevant to this document:


 
· NSCA, subsection 24(4) and paragraphs 26(a) and (e)
 
· General Nuclear Safety and Control Regulations (GNSCR), subsection 3(1.1)


Other relevant sections of the regulations made under the NSCA are included in the content of
this document. Appendix A maps a list of relevant clauses from the NSCA and the regulations
 made under the NSCA to the related sections of this licence application guide.


The applicant must also comply with all applicable laws and regulations at all jurisdictional
 levels.


 
Note: This regulatory document includes select requirements that are based on the NSCA and the
regulations made under the NSCA. While each section of the regulatory document addresses
select requirements related to the safety and control area (SCA) or other topics of regulatory
interest, applicants are responsible for ensuring that all requirements under the NSCA and
 regulations, for the proposed activities, are addressed in an application.


Comment on section 1.3


 

 
1.4 National and international standards
 
Key principles and elements used in developing this document are consistent with national and
international standards. Furthermore, this regulatory document is compatible with the safety
 objectives and principles in IAEA SSR-4, 
Safety of Nuclear Fuel Cycle Facilities [1].


 

Comment on section 1.4


 
1.5 CNSC contact information
 
A single point of contact from the CNSC is assigned to work with every licensee or applicant.
This point of contact can provide the licensee or applicant with additional information or
 explanation of the information contained within this document.


 To contact the CNSC, refer to the 
CNSC’s website.


 
Note: An applicant who intends to possess Category I and/or Category II nuclear material should
consult with CNSC staff to identify additional relevant requirements for the site prior to
 submitting an application.


Comment on section 1.5


 
2. Licensing Basis, Process and Submission
 
This section provides information on the licensing basis, licensing process, and on completing
 and submitting the licence application.


Comment on section 2


 
2.1 Licensing basis
 
The licensing basis sets the boundary conditions for a regulated activity and establishes the basis
for the CNSC’s compliance program for that regulated activity. The concept of the licensing basis
 is explained in REGDOC-3.5.3, 
Regulatory Fundamentals [2].


CNSC staff review both the application and the supporting documentation, and assess whether the
information is sufficient and acceptable. If the Commission grants a licence, the information
 submi
tted by the applicant will form part of the licensing basis.


Comment on section 2.1


 
2.2 Licensing process
 
REGDOC-3.5.1, Licensing Process for Class I Nuclear Facilities and Uranium Mines and
 Mills 
[3], clarifies the licensing process in the context of the NSCA.


In addition to the information provided in this licence application guide (REGDOC-1.2.2), the
 CNSC may request additional information as necessary to evaluate the application.


The licensing process is initiated when the applicant submits a licence application. Applicants
should ensure they include sufficiently detailed information to allow the licensing process to
 proceed efficiently. Early engagement with CNSC staff is encouraged.


Protecting the environment is part of the CNSC’s mandate. The CNSC requires the environmental
effects of all licensed activities to be assessed and considered when licensing decisions are made.
Environmental reviews are based on the scale and complexity of the environmental risk
 associated with a nuclear facility or activity.


 For more information on the CNSC’s environmental review and licensing processes, see:

 

 
· REGDOC-2.9.1, Environmental Protection: Environmental Principles, Assessments and
Protection Measures [4]
 
· REGDOC-3.5.1, Licensing Process for Class I Nuclear Facilities and Uranium Mines and
 Mills, [3]


 
Note: The information provided in this document does not prevent applicants from proposing
alternatives. However, any proposed alternative should appropriately reflect the complexities and
 hazards of the proposed activities and should be supported by suitable information.


Comment on section 2.2


 
2.3 Structuring the licence application
 
The application may be completed in either of Canada’s official languages (English or French).
This licence application guide describes the expected safety and control measures, organized by
the CNSC’s safety and control area (SCA) framework. 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 follows (see appendix B):


 
· 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


Each of the 14 SCAs is further divided into specific areas that cover topics addressed in a
 complete assessment and review.


The applicant may choose to organize the information in any structure. However, the applicant is
encouraged to organize the licence application according to the SCA framework to facilitate
 CNSC staff review.


 

Comment on section 2.3


 
2.4 Completing the licence application
 
The applicant is responsible for ensuring that the licence application contains sufficient
information to meet regulatory requirements. The applicant should provide cross-references to
 detailed information in other sections as appropriate.


Early in the licensing process, the CNSC may provide guidance to the applicant identifying the
appropriate version (publication date and revision number) of each document to be cited or
addressed in the application. This supplemental guidance may also indicate documents other than
 those listed in appendix C that the applicant should consider and address in the application. The

 
application should cite the regulatory documents, codes and standards that were used to
demonstrate the applicant’s ability to meet the regulatory requirements set under the NSCA.

 The applicant may provide references to any documents included in a previous licence
 application.


 The application should indicate the relevant sections of each supporting document.


 
New licence applications
 
For new licence applications, the applicant should consult with CNSC staff to confirm which
editions of the codes and standards applicable to the facility are acceptable. This should be done
prior to developing proposed safety policies, programs, processes, procedures and other safety
 and control measures.


 
Licence renewals
 
For the renewal of an existing licence, the applicant shall indicate if any information was
submitted with previous licence applications. Subsequent applications shall provide a list of the
 supporting documents and clearly identify which information was previously submitted.


 
Note: If the document version in the supporting information has changed, the applicant shall
 provide the CNSC with the new version number and a revised copy of the document.


Comment on section 2.4


 
2.5 Submitting the licence application
 
The applicant should ensure that the application is complete, dated and signed by the appropriate
authority, and that all supporting documents are clearly identified and cross-referenced. All
 information submitted is subject to the 
Access to Information Act and the Privacy Act. It is the
responsibility of the applicant to identify, with justification, any material that is not suitable for
public disclosure. All submitted information may be presented to the Commission to support the
licensing decision. Any such information is also made available to the public upon request,
 subject to confidentiality requirements.


If the licence application is subject to the 
Canadian Nuclear Safety Commission Cost Recovery
Fees Regulations
, the applicant should ensure that payment is enclosed. For further details,
contact the 
CNSC Cost Recovery Advisory Group at 613-995-5894 or toll-free at
1-888-229-2672.
 

Applicants are strongly encouraged to submit the documents in electronic format. Secure devices
may be used. Applicants who choose to submit a licence via email must submit the application to
 the 
CNSC Secretariat.


If the applicant chooses to submit the licence application in printed (hard copy) format, the
applicant should provide two printed copies of the application (signed and dated) to the
 Commission at:


Canadian Nuclear Safety Commission
280 Slater Street
P.O. Box 1046, Station B
Ottawa, ON K1P 5S9
 Canada

 

 
The applicant shall keep a record of licence information, as required by section 27 of the General
 Nuclear Safety and Control Regulations
.


Note that it is prohibited to submit prescribed information via unencrypted email. Prescribed
information, such as details of the security program, shall be submitted in accordance with
 sections 21 and 23 of the 
General Nuclear Safety and Control Regulations. Guidance for the
 protection and transmission of prescribed information can be found in REGDOC-2.12.3, 
Security
 of Nuclear Substances: Sealed Sources and Category I, II and III Nuclear Material 
[5].


Comment on section 2.5


 
3. General Application Requirements
 
This section addresses the requirements of the following regulations under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(a), (b), (c), (d) and (k), and
section 15
 
· Class I Nuclear Facilities Regulations, paragraphs 3(a), (b), (c) and (i)
 
· Nuclear Security Regulations, section 41


The licence application shall include the following general information to satisfy the regulations
and should also include additional general information where appropriate, as listed below. The
applicant shall identify the appropriate information and documents that are subject to
 confidentiality requirements.


Comment on section 3


 
3.1 Identification and contact information


Comment on section 3.1


3.1.1 Current licence number
 
If the licence application is for the renewal of an existing licence, the applicant shall provide the
 current licence number.


Comment on section 3.1.1


 
3.1.2 Applicant’s name and business address
 
The applicant shall provide the applicant's name and business address.


The name shall 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 shall 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.


 The applicant shall notify the Commission within 15 days of any changes to this information.


Comment on section 3.1.2


 
3.1.3 Mailing address
 
If the mailing address is different from the head office address, the applicant should provide the
mailing address, including the complete street name and number, rural route number if
 appropriate, city, province or territory, and postal code.

 

 
If no address is provided, any licence issued in response to the application will be mailed to the
 head office address. A post office box number is acceptable as a mailing address.


 The applicant should notify the Commission within 15 days of any changes to this information.


Comment on section 3.1.3


 
3.1.4 All persons who have authority to interact for the applicant with the CNSC
 
The applicant shall notify the Commission of the persons who have authority to act for them in
 their dealings with the Commission.


The applicant shall notify the Commission within 15 days of any changes to this information.
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 to confidentiality requirements.


Comment on section 3.1.4


 
3.1.5 Proof of legal status
 
Applicants shall provide proof of legal status by appending proof of incorporation, corporation
number or charter. When submitting an application to renew a licence, proof of legal status need
 only be provided if the applicant’s original organization name has changed.


 If the applicant is a corporation, the application should include the following information:


 
· corporation’s legal name
 
· corporation number
 
· date of incorporation
 
· registered office address (if different from the head office address)


Comment on section 3.1.5


3.1.6 Evidence that the applicant is the owner of the site or has authority from the owner of the site to carry on the activity to be licensed

The applicant shall provide evidence that the applicant is the owner of the site or has authority
 from the owner of the site to carry on the activity to be licensed.

 


Comment on section 3.1.6



3.1.7 Identification of persons responsible for management and control of the licensed
 activity

The application shall contain the applicant’s organizational management structure insofar as it
may bear on the applicant’s compliance with the NSCA and the regulations made under it,
 including the internal allocation of functions, responsibilities and authority.


The applicant shall notify the Commission of the names and position titles of the persons who are
responsible for the management and control of the licensed activity and the nuclear substance,
nuclear facility, prescribed equipment or prescribed information encompassed by the licence. The
applicant shall notify the Commission within 15 days of any changes to this information.
 

To satisfy these requirements, the applicant should provide a summary list of all persons
 responsible for management and control of the licensed activity, including:

 

 
· names
 
· positions (job titles)
 
· contact information (email, telephone, facsimile)
 
· mailing addresses (if different from the business mailing address)


 

Comment on section 3.1.7


 
3.1.8 Billing contact person
 
The applicant shall provide the following information for the person responsible for the licence
 fee payments:


 
· name
 
· position
 
· contact information (email, telephone, facsimile)
 
· mailing addresses (if different from the business mailing address)



Comment on section 3.1.8



 
3.1.9 Legal signing authority
The applicant shall provide the name, title and contact information (address, email address and
telephone number) of the individual who is signing the application, as the applicant authority.
 

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.



Comment on section 3.1.9


 
3.2 Facility and activities to be licenced


Comment on section 3.2


3.2.1 Licence period
 
The applicant should state the requested licence period (years or months).


The licensee may request a specific licence period to match planned activities or anticipated
 change in status.


Comment on section 3.2.1


 
3.2.2 Statement of the main purpose
 
The applicant shall provide:


 
· information about all activities to be licensed and their purpose
 
· a description of any nuclear facility, prescribed equipment or prescribed information to be
 encompassed by the licence


This information may be provided in summary format; for example, by listing facilities,
 equipment or information.


Comment on section 3.2.2


 
3.2.3 Description of site
 
The application shall contain:


 
· a description of the site of the activity to be licensed, including the location of any exclusion
zone and any structures within that zone
 
· plans showing the location, perimeter, areas, structures and systems of the nuclear facility
 

If the licence processes or stores Category III nuclear material, an application for a licence in
respect to a nuclear facility shall contain a description of the physical protection measures to be
taken to ensure compliance with sections 42 to 48 of the 
Nuclear Security Regulations in addition
to the information required by sections 3 to 8 of the 
Class I Nuclear Facilities Regulations.


Comment on section 3.2.3


 
3.2.4 Description of the facility’s existing licensing status, if any
 
If an activity on the site is currently licensed by the CNSC, or a previous licence application is
 pending, the applicant shall provide a description of the licensing status.


Comment on section 3.2.4


 
3.2.5 Nuclear and hazardous substances
 
The applicant shall provide:


 
· the name, maximum quantity and form of any nuclear substance to be encompassed by the
licence
 
· the name, form, characteristics and quantity of any hazardous substances that may be on the
 site while the activity to be licensed is carried on


The applicant should provide the scientific name of each nuclear and hazardous substance.
 

This information may be provided in summary format; for example, by providing a table of the
nuclear and hazardous substances and the information required for each substance.


Comment on section 3.2.5


 
3.3 Other relevant information


Comment on section 3.3


3.3.1 Permits, certificates and other licences
The applicant should describe the relationship of this application to any previous licences (for
example, siting, construction or operation) issued by the CNSC for activities at this facility,
including any changes to the licensing basis that were included 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 nuclear substances.


Comment on section 3.3.1


 
3.3.2 Similar facilities (for a licence application for a new facility)
If this licence application is for a new facility, the applicant should provide a list of any similar
facilities owned or operated by the applicant that have been assessed and licensed by either the
CNSC or any foreign regulatory body. The list should include the following information:


 
· facility name
 
· location
 
· date when the most recent licence was granted
 
· description of the facility


Comment on section 3.3.2


 
3.3.3 Supporting information
 
Where applicable, supporting information includes:


 
· 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
 
· information published by a national agency or an international nuclear agency such as the
International Atomic Energy Agency (IAEA) or the International Commission on
 Radiological Protection (ICRP)


Comment on section 3.3.3


 
4. Safety Policies, Programs, Processes, Procedures and Other Safety and Control
Measures
 
The applicant shall ensure to include in the application sufficiently detailed information about the
safety policies, programs, procedures and other documents that describe safety and control
measures. All policies and programs should allow for continuous development, on an on-going
 basis for all lifecycle stages of the facility.


 
Note: Appendix A shows all relevant clauses in regulations for a licence to prepare a site,
construct, operate, or decommission a Class IB processing facility. It is up to the applicant to
 ensure sufficient details are provided for each activity.


Comment on section 4


 
4.1 Management system
 
The management system SCA establishes the framework for the processes and programs required
to ensure an organization achieves its safety objectives, continuously monitors its performance
 against these objectives, and fosters a healthy safety culture.


 This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(k), 12(1)(a), and 17(c) and
(e), and sections 15, 27 and 28
 
· Class I Nuclear Facilities Regulations, paragraphs 3(d), (d.1) and (f), 4(d), 5(c), (g), (i) and
(l), 6(d), (e), (g), (h), (k), (l), (m) and (n) and 7(c), (f), (i) and (j) and subsections 14(1), (2),
(4) and (5)
 
· Nuclear Security Regulations, subsections 37(1), (2) and (3), and section 38
 
· Nuclear Substances and Radiation Devices Regulations, subsection 36(1)


Comment on section 4.1


 
4.1.1 General considerations
 
The application shall describe the management system programs, processes and procedures that
have been or will be put in place to protect health, safety and the environment, as well as a
 description of the organizational management structure.


The application shall also describe the safety policies, the roles of external safety assessment
organizations and the advisory committees that will advise the management of the organization
 that will carry out licensed activities.


 The application should refer to CSA N286-12, 
Management system requirements for nuclear
 facilities 
[6] to meet the requirements for the management system SCA. If an application does not
 use CSA N286-12, it should provide the alternate standard used with justification.

 

Comment on section 4.1.1


 
4.1.2 Management system
 
The application shall describe how the applicant’s management system is compliant with relevant
 requirements and how the management system will be implemented.


Comment on section 4.1.2


 
4.1.3 Organization
 
The application shall describe the organizational structure.


Comment on section 4.1.3


 
4.1.4 Performance assessment, improvement and management review
 
The applicant shall describe the programs covering performance assessment, improvement and
 management review.


The application shall describe the adequate provisions made for an objective internal selfevaluation program supported by periodic external reviews and taking into account national and
 international experience and feedback from the nuclear industry.


The application should describe how organizational effectiveness and safety performance are
measured, including the use of performance indicators to detect any shortcomings and
 deteriorations in safety.


The application should describe how organizational changes are managed to prevent degradation
 of safety performance.


The applicant should demonstrate that the analysis of the causes of significant events will
consider technical, organizational and human factors aspects, and that the necessary arrangements
 have been made to report and analyze near-miss events.


The application should clearly state how the applicant intends to present, promote and assess the
key characteristics of good safety performance by all workers, at the facility, including
contractors and subcontractors. The application should provide a proposed timeline and
milestones for completion of specific detailed safety performance documentation that will be
 developed later.


Comment on section 4.1.4


 
4.1.5 Operating experience
 
The application should describe how the program for feedback of operating experience has been
implemented during site evaluation and design activities, and how it will continue during the
 construction, commissioning and operating phases of the processing facility’s lifecycle.


Comment on section 4.1.5


 
4.1.6 Change management
 
The application should describe change management within the processing facility.


Comment on section 4.1.6


 
4.1.7 Safety culture
 
The application shall demonstrate that the applicant’s approach to foster a healthy safety culture
 is in accordance with REGDOC-2.1.2, 
Safety Culture [7].


Comment on section 4.1.7


 
4.1.8 Configuration management
 
The application should describe the provisions to establish and maintain configuration from
 concept until end of operation life.


Comment on section 4.1.8


 
4.1.9 Records management
 
The application should describe the adequate provisions for records management. Licensees are
 required to keep records relating to the licence submitted to the Commission.


Comment on section 4.1.9


 
4.1.10 Business continuity
 
The application should include a business continuity plan. This plan should provide procedures
and information that guide the applicant to respond, recover, resume and restore to a predefined
 level following disruption. Some examples of disruptions are:


 
· natural disasters (such as hurricanes, floods, blizzards, earthquakes and fire)
 
· accidents
 
· sabotage, including cyber attacks and hacker activity
 
· labour actions
 
· loss of a key contractor
 
· power and energy disruptions
 
· communication, transport, safety and service sector failure
 
· health-related epidemic or pandemic events that have or could have a measurable impact
 
· environmental events (such as pollution and hazardous materials spills)


Comment on section 4.1.10


 
4.2 Human performance management
 
The human performance management SCA covers activities that enable effective human
performance through the development and implementation of processes that ensure that a
sufficient number of licensee personnel are in all relevant job areas and have the necessary
 knowledge, skills, procedures and tools in place to safely carry out their duties.


 This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(k), and 12(1)(a), (b), (e)
and (j), and section 17
 
· Class I Nuclear Facilities Regulations, paragraphs 3(f), 5(i), (l) and (m), 6(d), (h), (k), (l),
(m), (n) and 7(f), (i) and (j) and subsection 14(2)
 
· Nuclear Security Regulations, section 48


Comment on section 4.2


 
4.2.1 General considerations


 
The application shall describe the qualifications, adequate numbers, skills and competencies
required by workers at the facility. For the purposes of this document, the regulatory focus of this
SCA for these types of facilities is personnel training. As applicable, the other specific areas are
 assessed as part of the licence application if requested.

 

 
The description shall include the measures to ensure a sufficient number of workers in all job
areas and that workers have the necessary knowledge, skills, procedures and tools in place to
 safely carry out their duties.


The application should describe the measures to promote and support human performance at all
levels in the organization. The application should demonstrate how the applicant’s programs and
processes interface to support continuous improvement of human performance. The application
should demonstrate various measures to identify and monitor human performance weaknesses
 and to correct any organizational deficiencies to minimize human error.


The application should describe the workforce planning process, including measures for
knowledge transfer, to ensure that workers are recruited and trained to fill each key role within
 the organization.


Comment on section 4.2.1


 
4.2.2 Human performance program


 
The application should describe how the human performance program addresses and integrates
 the range of human factors that influence human performance, including but not limited to:


 
· the adequate provision of qualified workers
 
· the reduction of human error
 
· organizational support for safe work activities
 
· the continuous improvement of human performance
 
· monitoring hours of work


Comment on section 4.2.2


 
4.2.3 Personnel training
 
The application shall describe a training system that is in accordance with REGDOC-2.2.2,
 
Personnel Training [8].


Comment on section 4.2.3


 
4.2.4 Work organization and job design
 
The application should describe the minimum number of workers with specific qualifications
required for normal operations and unusual conditions (minimum staff complement). The
application should demonstrate that the minimum staff complement will be monitored and
 recorded.


The applicant should demonstrate that the adequacy of the minimum staff complement has been
determined through a systematic analysis to identify the required number of workers and their
qualifications. The applicant should demonstrate that the minimum staff complement can meet
 the performance requirements and support the safe operation of the facility.


 For more information, refer to REGDOC-2.2.5, 
Minimum Staff Complement [9], and REGDOC-
 2.5.1, 
General Design Considerations: Human Factors [10].


Comment on section 4.2.4


 
4.2.5 Fitness for duty
 
High security sites are identified as a nuclear power plant or a nuclear facility where Category I
 or II nuclear material is processed, used or stored as per section 1 of the 
Nuclear Security
 Regulations
. For sites subject to this designation, the application should identify the oversight
 requirements for supervisors of security personnel from the perspective of fitness for duty.

 

 
For more information regarding fitness for duty for high security sites, refer to:
 
· REGDOC-2.2.4, Fitness for Duty: Managing Worker Fatigue [11]
 
· REGDOC-2.2.4, Fitness for Duty, Volume II: Managing Alcohol and Drug Use [12]
 
· REGDOC-2.2.5, Minimum Staff Complement [9]


Comment on section 4.2.5


 4.3 Operating performance
The operating performance SCA includes an overall review of the conduct of the licensed
activities and the activities that enable effective performance.


This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(k) and 12(1)(c), (e) and (f),
and sections 17, 29, 30, 31 and 32
 
· Class I Nuclear Facilities Regulations, paragraphs 4(a), 5(c), (i), (l) and (m), 6(c), (d), (e),
(g), (h) and (k), 7(a), (c), (f) and (i) and subsection 14(2)
 
· Radiation Protection Regulations, subsection 1(3) and sections 13, 14 and 15


Comment on section 4.3


 
4.3.1 General considerations
 
The application shall include information on how the applicant will ensure that normal facility
 operations:


 
· are carried out safely, such that radiation doses to workers and members of the public—as
well as any planned discharges or releases of radioactive material or hazardous substances
from the facility—will be within the proposed limits and conditions
 
· adhere to any applicable provincial legislation or other applicable codes and standards


The application should describe how the operating principles, policies, processes and programs
will confirm that the structures, systems and components (SSCs) will perform and function in
accordance with the design specifications and regulatory requirements outlined in the safety
analysis.


The application should include information regarding the development, verification, validation
and implementation of programs and procedures related to commissioning, maintenance,
operation and decommissioning.


For a new facility, the application should describe the processes used to ensure that the
performance of the SSCs has been assured from site preparation to construction to operation and
to the future, if major modifications are made to the facility.


Comment on section 4.3.1


 
4.3.2 Conduct of licensed activity
 
The application shall describe the proposed measures, policies, methods and procedures for
carrying on the licenced activity at the nuclear facility. The application shall describe the means
for preparation of equipment for maintenance and the monitoring of SSCs to confirm that they
 will continue to operate as required by the design.


 The application shall also describe how the applicant will:

 

· exercise overall responsibility for safety in conducting licensed activities, including ongoing
upgrades and modifications to the facility
 
· handle, store, load and transport nuclear and hazardous substances
 
· carry out effective oversight of these activities and procedural adherence


Comment on section 4.3.2


 
4.3.3 Procedures
 
The application shall describe the development, verification, validation and implementation of
operating procedures for the activities to be licensed covering normal, unplanned and emergency
 conditions.


The application should describe how all normal, unplanned and emergency operating procedures
 will be validated. For more information, refer to REGDOC-2.5.1, 
General Design
 Considerations: Human Factors 
[10].


Comment on section 4.3.3


 
4.3.4 Reporting and trending
 
The application shall include the analysis of operating performance including the causes of
events, accidents, injuries, unplanned shut downs and reportable events. For more information,
 refer to REGDOC-3.1.2, 
Reporting Requirements, Volume I: Non-Power Reactor Class I
 Facilities and Uranium Mines and Mills 
[13].


Comment on section 4.3.4


 
4.3.5 Operating limits and conditions
 
The application should state the safe operating limits and conditions. The information submitted
should describe how the applicant will comply with limits imposed by the design and safety
analysis assumptions. The application should clearly describe the actions to be taken if the limits
 and conditions are not met.


The information available on the set of limits and conditions and the accompanying design
information for the facility should be sufficient to support the training and qualification of facility
 workers.


Comment on section 4.3.5


 
4.4 Safety analysis
 
The safety analysis SCA covers development and maintenance of the safety analysis that supports
the overall safety case for the facility. Safety analysis is a systematic evaluation of the potential
hazards associated with the conduct of a proposed activity or facility and considers the
effectiveness of preventive measures and strategies in reducing the effects of such hazards.
 This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(d), (e) and (i), and 12(1)(c)
and (f)
 
· Class I Nuclear Facilities Regulations, paragraphs 3(b) and (d), 5(f), (i), (j) and (k), 6(a), (b),
(c), (d), (h), (i), (j) and (k), and 7(f) and (g)
 
· Radiation Protection Regulations, subsection 1(3) and sections 4, 13, 14 and 15
 

Comment on section 4.4


 
4.4.1 General considerations
 
The application shall include a safety analysis program that is in accordance with
 REGDOC-2.4.4, 
Safety Analysis for Class IB Nuclear Facilities [14]. It is required for licensees
to submit a preliminary safety analysis report for a licence to construct and a final safety analysis
 report for a licence to operate.


Comment on section 4.4.1


 
4.4.2 Postulated initiating events
 
The safety analysis shall identify postulated initiating events (PIEs) using a systematic
methodology (for example, hazard and operability studies). The scope and classification of PIEs
 in the application shall meet the requirements specified in REGDOC-2.4.4, 
Safety Analysis for
 Class IB Nuclear Facilities 
[14]. The information provided should demonstrate that all credible
events with the potential for serious consequences or with a significant frequency of occurrence
 are anticipated and considered.


The application should describe how the design and safety analyses have taken into account the
 potential for specific hazards from common cause events on the site.


Comment on section 4.4.2


 
4.4.3 Deterministic safety analysis
 
The application shall include a deterministic safety analysis to evaluate and justify facility safety,
 conducted in accordance with REGDOC-2.4.4, 
Safety Analysis for Class IB Nuclear Facilities
 
[14]. The level of conservatism of each deterministic safety analysis should be appropriate for the
frequency of the event analyzed and the analysis objectives and should take into account
 operational experience/feedback from similar facilities.


Comment on section 4.4.3


 
4.4.4 Hazard analysis
 
The application should describe the analysis of all credible hazards (internal and external), both
 natural and human-induced. Some examples are:


 
· for natural external hazards: earthquakes, droughts, floods, high winds, tornadoes, abnormal
surges in water level and extreme meteorological conditions
 
· for human-induced external hazards: those that are identified in the site evaluation, such as
airplane crashes, ship collisions, and accidents at surrounding activities such as chemical
explosion
 
· for internal hazards: internal fires, internal floods, turbine missiles, on-site transportation
accidents and releases of hazardous substances from on-site storage facilities
 

The application should describe the analysis of any credible combinations of the external hazards
and should consider maximum probable scenarios where applicable. It should also consider the
potential interaction of external and internal hazards, such as external events that initiate internal
fires or floods.


Comment on section 4.4.4


 
4.4.5 Criticality safety
 
Operations with fissionable materials shall meet the requirements of REGDOC 2.4.3, Nuclear
 Criticality Safety 
[15]. Operations with fissionable materials introduce risks of a criticality
accident resulting in a release of radiation that can be lethal to nearby personnel. However,
 experience has shown that extensive operations can be performed safely and economically with a

 
combination of carefully considered engineered design features to prevent criticality and
appropriate human performance measures. The few criticality accidents that have occurred show
 frequency and severity rates far below those typical of non-nuclear accidents.


Comment on section 4.4.5


 
4.5 Physical design
 
The physical design SCA relates to activities that impact the ability of SSCs to meet and maintain
their design basis, given new information arising over time and taking changes in the external
 environment into account.


This section addresses the requirements of the following regulations made under the NSCA:
 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(d), (e), (g), (h), (i) and (j),
and 12(1)(c) and (f)
 
· Class I Nuclear Facilities Regulations, paragraphs 3(a), (b), (d) and (i), 4(a), (b), (c) and (d),
5(a), (b), (d), (e), (f), (g) and (j), 6(a), (b), (c), (g), (h), (i), (j), (k), (m) and (n), and 7(f), (g),
(h) and (i)
 
· Radiation Protection Regulations, subsection 1(3) and sections 4, 13, 14 and 15


Comment on section 4.5


 
4.5.1 General considerations
 
The application shall include an appropriate level of detail about the description of the overall
physical design of the facility, the design practices and the safety concepts commensurate with
the activities being proposed in the licence. The application shall also describe the approach
followed for the general design of and the performance of the SSCs.
For a new facility, the application shall include information showing that the facility’s design,
construction, commissioning and operation is consistent with prevailing national and international
codes and standards. The facility design shall conform to the National Building Code of Canada,
National Fire Code of Canada and CSA N393. Where appropriate, CNSC staff may require more
stringent requirements with regards to seismic and fire protection. The IAEA suite of safety
standards and safety guides are used as guidance in the technical assessment of fuel cycle facility
 design. These safety guides include:


 
· SSR-1, Site Preparation for a Nuclear Facility [16]
 
· SSR-4, Safety of Nuclear Fuel Cycle Facilities [1]
 
· SSG-5, Safety of Conversion Facilities and Uranium Enrichment Facilities [17]
 
· SSG-6, Safety of Fuel Fabrication Facilities [18] (for less than 6% enrichment)
 
· SSG-7, Safety of Uranium and Plutonium Mixed-Oxide Fabrication Facilities [19]
 
· SSG-42, Safety of Nuclear Fuel Reprocessing Facilities [20]
 
· SSG-43, Safety of Nuclear Fuel Cycle Research and Development Facilities [21]


For other radioisotope processing facilities, including processing of unsealed nuclear substances,
 REGDOC-2.5.6, 
Design of Room where Unsealed Nuclear Substances are Used [22] should be
 used as guidance.


Where there are multiple set of regulatory requirements for the same parameters, the most
stringent requirement should be applied. Where there is a conflict between requirements, the
applicant may propose alternate approaches and provide justification. The application should
provide information that demonstrates compliance with the most recent national and international
best practices as applicable.

 

For existing facilities, the application should address the information in this section to the extent
practicable and provide references to past submissions. Any alternative approaches selected or
mitigating measures applied should be identified and justified.


The application may refer to information that was submitted previously (for example, in the
application for a licence to construct). The set of documents that address the requirements in this
section should be submitted only once for the initial application, with few subsequent revisions.
 

Where appropriate, the application shall describe the radiation protection and environmental
protection design principles and approaches adopted with the intent for facility operations to be
carried out safely. The information submitted shall demonstrate that, in all operational states,
radiation doses within the facility or any planned release of nuclear substances from the facility
meet the requirements of REGDOC-2.9.1, 
Environmental Protection: Environmental Principles,
Assessments and Protection Measures 
[4], and REGDOC-2.4.4, Safety Analysis for Class IB
Nuclear Facilities 
[14]; are kept below regulatory limits; and are as low as reasonably achievable
(ALARA). REGDOC-2.7.1, 
Radiation Protection [23], also provides guidance on design
considerations for meeting CNSC regulatory requirements for the control of occupational
exposures.


Comment on section 4.5.1


 
4.5.2 Design governance
 
The application shall describe how design governance and design change control are
implemented for the proposed activities in consideration of factors described below.


Design change control and configuration management should be in accordance with CSA N286-
12, 
Management systems for nuclear facilities [6]. For facilities processing radioisotopes used in
medicinal applications, alternate standards, including ISO 13485, 
Medical devices – Quality
management systems – Requirements for regulatory purposes 
[24], may be applied.


For more information please refer to REGDOC-2.5.1 General Design Considerations: Human
Factors 
[10].


Comment on section 4.5.2


 
4.5.3 Site characterization
 
The application shall refer to, or summarize, the information previously submitted in any relevant
environmental assessment or licensing documentation, such as environmental impact statements
 and any previous licence application. This information includes:


 
· geological, geotechnical, seismological, hydrological, hydrogeological and meteorological
data
 
· site plan and description, and site reference data
 
· proximity of industrial, transport and military facilities


The site characterization should be developed in accordance with CSA N288.6
, Environmental
risk assessments at Class I nuclear facilities and uranium mines and mills 
[26]


Comment on section 4.5.3


 
4.5.4 Facility design
 
The application shall describe the overall conceptual design of the facility and the operation and
interaction of all of the SSCs. To ensure that the facility will be reliable, robust and maintainable,
 the applicant shall ensure that the design:


 
· conforms to an acceptable quality assurance program
 
· incorporates the latest developments in knowledge and technology
 
· is resistant to the effects of common-cause events and, to the extent practicable, to severe
 accidents


The application shall identify the criteria used for determining the level of acceptable risk and
demonstrates that the criteria meet general safety objectives.


The application should describe the decision-making methodology (for example, cost/benefit and
best available technology) that was used to select the design option.
 

The application should include basic technical and schematic drawings of the main facility SSCs,
 including:


 
· details of the physical and geographical location of the facility
 
· means of access to the site by rail, road and water


The application should also include general layout drawings of the entire facility, accompanied by
a brief description of the main systems and equipment, and their individual purposes and
interactions. The application should refer to the confidential information on the adequate
provisions made for the physical protection of the facility.


The applicant should provide information on the design of laboratories and Class II nuclear
facilities within the facility and if included as a licensed activity under the Class I licence. The
design of laboratories and Class II nuclear facilities shall meet the requirements of the 
Class II
Nuclear Facilities and Prescribed Equipment Regulations 
and the Nuclear Substances and
Radiation Devices Regulations
, as applicable.


The applicant should provide information on the adequate provisions for storage of items such as,
but not limited to, contaminated tooling and radiation sources.
 For more information, refer to REGDOC-2.5.6, 
Design of Room where Unsealed Nuclear
 Substances are Used
, [22].


Comment on section 4.5.4


 
4.5.5 System and component design
 
Commensurate with the activities being proposed in the licence application and safety importance
of the system as it applies to the activities, the applicant shall provide, in detail, the characteristics
and major components of the system and its design basis requirements (for example, the
functional and performance requirements associated with the definition of design basis).
The application shall describe the basis for the design of the pressure-retaining SSCs and their
supports. The application should also describe the pressure boundary standards and codes along
with their editions and effective dates. It should also describe the overall pressure boundary
program, including its implementation processes and procedures. In addition, the application
should describe the service agreement with a recognized authorized inspection agency and the
 related pressure boundary quality assurance program.


The application shall clearly describe facility heating, ventilation and air conditioning (HVAC)
 systems when those systems are credited in the facility safety analysis. The description should

 
include areas such as control facilities, wet storage bays, the auxiliary and radioactive waste area
 and the ventilation systems for safety systems.


The safety significance of any HVAC system credited in the facility safety analysis should be
clearly stated, including all common safety-related functionality dependencies such as the air
conditioning system for an equipment room that may contain multiple divisions or groupings of
support systems. Where applicable emergency ventilation may be required for personnel safety,
 and these areas and the associated requirements should be clearly identified and listed.


Comment on section 4.5.5


 
4.5.6 Waste treatment and control
 
The application should describe how the generation of radioactive and hazardous wastes is
minimized, and how the wastes are characterized, controlled, handled, conditioned and disposed
 of.


The application should also describe how releases within the facility and to the environment will
 be monitored and controlled such that they remain within prescribed limits.


Comment on section 4.5.6


 
4.5.7 Control facilities
 
The applicant shall provide a description of the facility control facilities, including any control
 rooms.


The description should cover the habitability systems, equipment, supplies and procedures that
are in place to ensure that essential facility workers, including those in the control rooms, can
remain at their posts and operate the facility safely in all operational states considered in the
 safety analysis.


Comment on section 4.5.7


 
4.5.8 Structure design
 
The application shall include relevant information on the design of the site layout and on civil
engineering works and structures associated with the nuclear facility. Site and facility layout
information should include the buildings and structures (including the foundation) and access to
 all essential services required for both normal and emergency operation.


The application should describe the design principles, design basis requirements and criteria, and
applicable codes and standards used in the design. The application should demonstrate that the
safety margins are sufficient for the buildings and structures important to safety (for example,
robustness against internal and external events). The application should clearly state and justify
 any deviation from applicable codes and standards or from other design requirements.


Comment on section 4.5.8


 
4.6 Fitness for service
 
The fitness for service SCA covers activities that affect the physical condition of SSCs to ensure
that they remain effective over time. This area includes programs that ensure all equipment is
 available to perform its intended design function when called upon to do so.


This section addresses the requirements of the following regulations made under the NSCA:
 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(d), (e), (i) and (j), and
 12(1)(c) and (f)

 
· Class I Nuclear Facilities Regulations, paragraphs 3(f), 5(d), (e), (f) and (m), and 6(a), (b),
(c), (d), (m) and (n); and subsection 14(2)
 
· Radiation Protection Regulations, subsection 1(3); and sections 4, 13, 14 and 15



Comment on section 4.6



 
4.6.1 General considerations
 
The application should identify all facility-wide asset management programs that ensure fitness
for service of all equipment and services are available as per its design intent and are functioning
within the OLCs identified in the facility’s safety analysis. The application should identify all
SSCs important to safety. The applicant may use an acceptable risk assessment methodology (for
example, Failure Mode and Effects Analysis or Mean Time Failure) in identifying frequency of
 maintenance and periodic inspection to ensure fitness for service of all equipment and SSCs.


Comment on section 4.6.1


 
4.6.2 Maintenance program
 
Maintenance activities include monitoring, inspecting, testing, assessing, calibrating, servicing,
repairing and replacing parts. In general, maintenance programs should include: preventative
maintenance, periodic maintenance based on inspections and corrective maintenance.
 

The application shall include a clearly defined maintenance program containing the proposed
measures, policies, methods and procedures that provide direction for maintaining SSCs so that
they remain capable of maintaining their functions, as described in design documents and safety
analyses that are included in the facility licensing documentation.
 

The application should describe the processes for planning, monitoring, scheduling and executing
work activities so that SSCs continue to perform the design intent and remain fit for service in the
 presence of degradation mechanisms.


 The application should describe:


 
· preventive maintenance activities
 
· maintenance processes and record retention requirements
 
· corrective maintenance
 
· calibration of measuring and monitoring devices
 
· SSC monitoring, activity optimization
 
· work planning and scheduling
 
· work execution
 
· maintenance procedures
 
· post-maintenance verification and testing
 
· maintenance program assessment


Comment on section 4.6.2


 
4.6.3 Aging management program
 
The applicant shall identify end-of-life testing and a replacement plan for SSCs and major
equipment (for example, calciners, flame reactors and sintering furnaces) and ensure that the
equipment is performing as expected and that the equipment remains fit for service. The
application should propose a plan to test for the structural integrity of major component to ensure
fitness for service (ex. corrosion in pipes, wall thinning, stress cracks or fatigue). Regular
 monitoring, including any non-destructive testing, for common aging-related circumstances

 
corrosion-related should also be provided in the application. Where applicable, a replacement
 plan of major equipment must be provided.


Comment on section 4.6.3


 
4.6.4 Periodic inspection and testing programs
 
The application shall include periodic inspection and testing programs for SSCs relied upon for
safety. Periodic inspection and testing programs require physical inspection and testing of SSCs
to ensure availability and confirm that service-induced degradation has not increased the
likelihood of a failure of a barrier against the release of radioactive or hazardous substances.


The application should state the codes and standards that the applicant intends to use as the basis
of the design, inspection and testing programs. Regulatory acceptance of the proposed codes and
standards will be considered as part of the application review process.


The application shall include a maintenance program for pressure boundary components as per a
formal agreement with an authorized inspection agency. The authorized inspection agency should
be recognized by the CNSC as authorized to register designs and procedures, perform inspections
 and other functions as defined by CSA B51, 
Boiler pressure vessel and pressure piping code
 
[27].


Program documents should describe baseline inspection activities implemented to establish the
condition of an SSC at the time it was placed into service and describe periodic inspection
 activities spanning the intended operating life of the facility.


Comment on section 4.6.4


 
4.7 Radiation Protection
 
The radiation protection SCA covers the implementation of a radiation protection program in
 accordance with the 
Radiation Protection Regulations. This program shall ensure that
contamination levels and radiation doses received by individuals are monitored, controlled and
 maintained as low as reasonably achievable (ALARA).


 This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(e) and (f), 12(1)(b), (c),
(d), (e) and (f); and section 17
 
· Class I Nuclear Facilities Regulations, paragraphs 5(j) and (l), 6(d), (e), (h), (i), (k), (m) and
(n), 7(e), (f), (g), (i) and (j); and section 14
 
· Radiation Protection Regulations, subsection 1(3) and sections 4-16 and 20-24


Comment on section 4.7


 
4.7.1 General considerations
 
The application shall describe the approaches for meeting the requirements of the Radiation
 Protection Regulations
.


The application shall include a radiation protection program and should demonstrate how the
design of the program is commensurate with the radiological hazards associated with the licensed
activities, based on a thorough analysis of radiological hazards, radiation exposures and dose
 assessments, and an optimization of doses to conform to the ALARA principle.

 

 
The structure of a radiation protection program should include the policies and procedures for key
 elements of the radiation protection framework, including:


 
· application of the ALARA principle
 
· management control over work practices
 
· personnel qualification and training
 
· control of occupational and public exposure to radiation
 
· planning for unusual situations
 
· ascertaining the quantity and concentration of any nuclear substance released as a result of
 the licensed activity


The application should describe the proposed action levels, along with the supporting technical
justification. Action levels are designed to alert licensees before regulatory dose limits are
reached. Applicants are responsible for identifying the parameters of their program that represent
timely indicators of potential losses of control of the radiation protection program, and providing
 rationale justifying the corresponding action levels.


 REGDOC-2.7.1, 
Radiation Protection [23]provides detailed guidance for applicants and
licensees on meeting regulatory expectations for radiation protection, including the development
 of radiation protection programs and action levels.


Comment on section 4.7.1


 
4.7.2 Application of ALARA
 
The application shall describe how the radiation protection program ensures that effective dose
and equivalent dose received by and committed to persons are ALARA, taking into account
social and economic factors. The application should describe the application of ALARA, in
 accordance with REGDOC-2.7.1, 
Radiation Protection [23].


Comment on section 4.7.2


 
4.7.3 Worker dose control
 
The application should describe how worker dose will be controlled, in accordance with the
 principles found in REGDOC-2.7.1, 
Radiation Protection [23]. Licensees should refer to
 REGDOC-2.7.2, 
Dosimetry, Volume I: Ascertaining Occupational Dose [25] for guidance on
 ascertaining worker dose.



Comment on section 4.7.3



 
4.7.4 Radiation protection program performance
 
The application should describe how radiation protection program performance will be evaluated,
 in accordance with the principles found in REGDOC-2.7.1, 
Radiation Protection [23].


Comment on section 4.7.4


 
4.7.5 Radiological hazard control
 
The application should describe how radiological hazards will be controlled, in accordance with
 the principles found in REGDOC-2.7.1, 
Radiation Protection [23].


Comment on section 4.7.5


 
4.8 Conventional health and safety
 
The conventional health and safety SCA covers the implementation of a program to manage
 workplace safety hazards and to protect workers.

 

 
This section addresses the requirements of paragraph 21(1)(a) of the NCSA and of the following
 regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, subsection 12(1); section 17; and
paragraphs 29(1)(d), (h), and (i)
 
· Class I Nuclear Facilities Regulations, paragraphs 3(e), (f) and (h), 4(e), 5(i), 6(e) and (h),
 and 7(f) and (i)


 It also addresses the requirements of the 
Canada Labour Code Part II and the Canada
 Occupational Health and Safety Regulations 
or, where applicable, the provincial occupational
 health and safety legislation.


Comment on section 4.8 


 
4.8.1 General considerations
The application shall describe the program and implementation of policies to minimize risk to the
health and safety of workers posed by conventional (non-radiological) hazards in the workplace,
including the management of workplace safety hazards and the protection of personnel and
equipment.


The application shall provide information detailing compliance to all applicable requirements
 under the 
Canada Labour Code, including all occupational exposure limits for all chemical
compounds listed under its regulations.
 

Where possible, the applicant shall indicate occupational exposure for acute exposure and chronic
 exposure.


For more information, see REGDOC-2.8.1, 
Conventional Health and Safety [28].


Comment on section 4.8.1


 
4.8.2 Practices
The application shall describe programs and policies in place to demonstrate compliance with
Canada Occupational health and safety Regulations. The applicant should also list all hazardous
substances used, produced, handled and stored for use in the workplace and list the recommended threshold limit values for the same as adopted by the American Conference of  Government Industrial Hygienists (ACGIH). Where applicable, both short-term exposure limits  and long-term exposure limits should be provided.


Comment on section 4.8.2


 
4.9 Environmental protection
 
The environmental protection SCA covers programs that identify, control and monitor all releases
of radioactive and hazardous substances and effects on the environment from facilities or as the
 result of licensed activities.


 This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(c) and (e), 12(1)(c) and (f),
and 17(b), (c) and (e)
 
· Class I Nuclear Facilities Regulations, paragraphs 3(e), (g), and (h), 4(c) and (e), 5(b), (i), (j)
and (k), 6(d), (h), (i), (j) and (k), and 7(f), (g), (h) and (i); and subsection 14(1)
 
· Radiation Protection Regulations, subsection 1(3) and paragraph 4(b)


 
These regulations include adequate provisions to ensure that licensees are meeting the CNSC’s
mandate to protect the environment and the health, safety and security of persons. Licensees shall
 demonstrate that their environmental protection measures consider the following:


 
· commensurate with the level of risk associated with the activity
 
· account for uncertainty by keeping all releases to the environment as low as reasonably
achievable and apply the best available technology and techniques economically available
 
· implement corrective actions to eliminate the identified root causes and verify completion to
 prevent recurrence


Comment on section 4.9


 
4.9.1 General considerations
The application shall include a comprehensive set of environmental protection measures,
including an environmental risk assessment, environmental management systems and
environmental monitoring program that meet all requirements, as applicable, of REGDOC-2.9.1,
Environmental Protection: Environmental Principles, Assessments and Protection Measures [4].
Some supplemental information to REGDOC-2.9.1, 
Environmental Protection: Environmental
Principles, Assessments and Protection Measures 
[4] is set out in the following sections.
 

The release of hazardous substances is regulated by the CNSC and the applicable provincial
authority for environmental protection. The application shall demonstrate compliance with the
applicable provincial legislation.


Comment on section 4.9.1


 
4.9.2 Effluent and emissions control
 
The applicant shall propose licenced release limits and establish environmental action levels that
 are performance as per REGDOC-2.9.2, 
Controlling Releases to the Environment [29]. The
effluent and emissions control measures in place are used to inform the development of the
licenced release limits and environmental action levels for the facility or activity being licensed.


Comment on section 4.9.2


4.9.3 Environmental management system
The application shall describe the environmental management system established to ensure
protection of the environment throughout operation.


Comment on section 4.9.3


4.9.4 Assessment and monitoring
The application shall describe the monitoring system established to cover all environmental
monitoring activities on the site during as identified in the environmental risk assessment (ERA)
licensed activities.


Comment on section 4.9.4


 
4.9.5 Protection of the public
The application shall identify and describe all of the radiological and non-radiological aspects of
site activities that could have environmental effects, including exposure to members of the public
during operation.


All applicants should submit the technical basis for calculating the dose to the public from
licensed activities.

 

For existing facilities, the application should include the maximum effective doses to the public
as a result of activities conducted at the facility during the current licence period.


This information may be submitted as part of the information addressing environmental
protection.


Comment on section 4.9.5


 
4.9.6 Environmental risk assessment
The application shall include an ERA and review the ERA from previous submissions, if
applicable, and update the information as necessary to reflect any changes to the site or the
situation.


 

Comment on section 4.9.6


 
4.10 Emergency management and fire protection
 
The emergency management and fire protection SCA covers emergency plans and emergency
preparedness programs that exist for emergencies and for non-routine conditions. This area also
includes any results of participation in exercises.


Note: This SCA includes conventional emergency and fire response. Fire protection operations,
design and analysis are discussed in the appropriate SCA of operating performance, safety
analysis and physical design.


This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(d) and (i) [all requirements
related to fire]), and 12(1)(a), (b), (c), (d), (e), (f), (g) and (h)
 
· Class I Nuclear Facilities Regulations, paragraphs 3(a) and (f), 5(i) and (k), 6(h) and (k), and
7(f) and (i)
 
· Radiation Protection Regulations, section 15


Comment on section 4.10


 
4.10.1 General considerations
 
The application shall describe an emergency preparedness program that meets the requirements of
 REGDOC-2.10.1, 
Nuclear Emergency Preparedness and Response [30] and REGDOC-2.10.2,
 
Fire Protection [31].


 An effective emergency preparedness program is based on the following components:


 
· planning basis
 
· program management
 
· response plan and procedures
 
· preparedness


The application should describe the preparations that have been made to ensure that on-site and
off-site emergencies will be dealt with safely and effectively. The application should reference
 population studies and emergency planning considerations related to the site.

 

Comment on section 4.10.1


 
4.10.2 Nuclear emergency preparedness and response
 
The application should describe how the nuclear emergency program encompasses both
 emergency preparedness and emergency response measures as per REGDOC-2.10.1, 
Nuclear
 Emergency Preparedness and Response 
[30].


Comment on section 4.10.2


 
4.10.3 Conventional emergency preparedness and response
 
The application shall describe all non-radiological, non-routine conditions at the facility for
which the emergency preparedness program has been established. The description shall include
details about which adequate provisions exist on-site and which provisions involve off-site
response support. The application shall include information that determines the need for an
emergency response facility, on or near the site, from which the on-site response to an emergency
 can be coordinated.


Comment on section 4.10.3


 
4.10.4 Fire emergency preparedness and response
 
The applicant shall describe a comprehensive fire protection program that ensures the licensed
activities do not result in unreasonable risk to the health and safety of persons and the
environment due to fire. The application shall include information on arrangements with first
responders, provisions for mutual support or aid, and interagency communication requirements. If
a memorandum of understanding is established with the first responders’ agency, the same shall
 be provided as part of the application.


Comment on section 4.10.4


 
4.11 Waste management
 
The waste management SCA covers internal waste-related programs that form part of the
facility’s operations up to the point where the waste is removed from the facility to a separate
waste management facility. This area also covers the planning for decommissioning.


This section addresses the requirements of the following regulations made under the NSCA:
 

· General Nuclear Safety and Control Regulations, paragraphs 3(1)(c) and (j), and 12(1)(c)
 
· Class I Nuclear Facilities Regulations, paragraphs 3(e), (f) and (k), 4(e), 5(i), (j) and (k),
6(e), (h), (i) and (j); section 7; and subsection 14(2)
 
· Radiation Protection Regulations, subsection 1(3); and sections 4, 13, 14, 15, 20, 21, 22 and
 23


Comment on section 4.11


 
4.11.1 General considerations
 
The application should demonstrate compliance with the six principles of radioactive waste
 management set out in REGDOC-2.11, 
Framework for Radioactive Waste Management and
 Decommissioning in Canada 
[32].


The application should contain a waste management program that meets the requirements of
 REGDOC-2.11.1, 
Waste Management, Volume I: Management of Radioactive Waste [33].
 

The application should demonstrate that the licensee will implement and maintain associated
programs and procedures to support the waste management program (e.g. waste characterization).
These programs and procedures should be commensurate with the risk of the waste streams being
 managed.

 

Comment on section 4.11.1


 
4.11.2 Waste characterization
 
The application shall demonstrate that waste characterization will be performed at appropriate
intervals during the management of radioactive waste. The application should meet the
 requirements of REGDOC-2.11.1, 
Waste Management, Volume I: Management of Radioactive
 Waste 
[33].


Comment on section 4.11.2


 
4.11.3 Waste minimization
 
The application shall demonstrate how the waste hierarchy will be considered in the management
 of radioactive waste.


Comment on section 4.11.3


 
4.11.4 Waste management practices
 
The application shall demonstrate that the licensee will:


 
· be responsible for the safe management of its radioactive waste, taking into consideration the
health and safety of persons, the environment and national security
 
· optimize the steps in radioactive waste management and practices to ensure the protection of
the health and safety of people and the environment
 
· take into account interdependencies among all steps in radioactive waste management, as
appropriate; each step shall be evaluated as an individual step in the process and as part of an
 integrated radioactive waste management system


The application should contain the waste classification plan and the waste acceptance criteria, if
 applicable, that meet the requirements of REGDOC-2.11.1, 
Waste Management, Volume I:
 Management of Radioactive Waste 
[33].


Comment on section 4.11.4


 
4.11.5 Decommissioning plans
 
The application shall contain the proposed plan for the decommissioning of the nuclear facility or
of the site. Planning for decommissioning is an ongoing process that is considered at each
lifecycle stage of the facility. Requirements and guidance on decommissioning are provided in
 REGDOC-2.11.2, 
Decommissioning [34].


A Preliminary Decommissioning Plan (PDP) is required for the siting, construction (including the
 design) and operation lifecycle stages of the facility. The PDP shall document:


 
· the selected decommissioning strategy
 
· main decontamination, dismantling and/or clean-up activities
 
· end-state objectives
 
· an overview of the principal hazards and protection strategies
 
· a waste management strategy
 
· a cost estimate
 
· financial guarantee arrangements


A Detailed Decommissioning Plan (DDP) shall be developed for the decommissioning lifecycle
 stage. The DDP shall document:


 
· the decommissioning strategy
 
· decontamination, dismantling and/or clean-up activities
 
· final end-state objectives
 
· the principle hazards and protection plans
 
· a waste management plan; a cost-estimate
 
· financial guarantee arrangements


A safety assessment shall be developed for the decommissioning lifecycle stage to identify any
radiological or non-radiological hazards to workers, the environment and the public from both
routine decommissioning activities and credible potential accidents during decommissioning. The
safety assessment may be a stand-alone document or may be included in the detailed
 decommissioning plan.


Comment on section 4.11.5


 
4.12 Security
 
The security SCA covers the programs required to implement and support the security
requirements stipulated in the regulations, the licence, orders, or expectations for the facility or
 activity.


 This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraph 3(1)(d), (e), (g), (h) and (i),
12(1)(c), (g), (h) and (j), 17(c) and (e); sections 21, 22, and 23; subsection 28(1); and sections
29 and 30
 
· Class I Nuclear Facilities Regulations, paragraphs 3(a), (b) and (i), 5(h), (i), 6(h), (k) and (l)
and 7(f)
 
· Nuclear Security Regulations
 
· Nuclear Substances and Radiation Devices Regulations, paragraphs 36(1)(a) and (d)


Comment on section 4.12


 
4.12.1 General considerations
 
An applicant who intends on processing, using or storing Category I or II nuclear material should
consult with CNSC staff to identify additional relevant requirements for the site prior to
submitting an application. Applications involving this material will be subject to Part 1 of the
 
Nuclear Security Regulations and its associated prescribed regulatory documents. Additional
relevant requirements include implementing a nuclear response force and addressing the Design
 Basis Threat document for example. For all other facilities, Part 2 of the 
Nuclear Security
 Regulations 
apply.


 
Note: Any information that is considered classified, protected, proprietary or personal, or that is
designated as prescribed information should be clearly identified and submitted in accordance
with the CNSC’s 
Guidance Document on Confidential Filings [35].


For facilities requesting a licence in respect of Category III Nuclear Material, an application for
licence (other than a licence to transport) shall contain the information required by section 3 of
the 
Nuclear Substances and Radiation Devices Regulations. Further, it shall include a description
of the measures to be taken to ensure compliance with subsection 7(3) and sections 7.1 and 7.2 of
the 
Nuclear Security Regulations.
 

The application shall describe the general design approach and adequate provisions in place to
control access and security at the facility.

 

For facilities with nuclear substances meeting or exceeding the thresholds of Category 3 or higher
 as identified in REGDOC-2.12.3, 
Security of Nuclear Substances: Sealed Sources and Category
 I, II and III Nuclear Material 
[5], the licensee shall submit a site security plan. This site security
plan shall provide detail on how the licensee has met the requirements defined in that REGDOC,
including the technical and administrative measures incorporated by the licensee.
The application should describe a security program that meets the requirements of REGDOC-
2.12.3, Security of Nuclear Substances: Sealed Sources and Category I, II and III Nuclear
Material [5].


Comment on section 4.12.1


 
4.12.2 Response arrangements
 
For licensees subject to Part 2 of the Nuclear Security Regulations, the application shall describe
how the security program ensures that off-site response arrangements effectively respond to the
unauthorized removal of nuclear or radioactive material. The application should provide details
regarding the licensee’s arrangements for annual familiarization visits to the nuclear facility by
members of the off-site response force. These arrangements should provide detail on the joint
development of a contingency plan by the licensee and the off-site response force to facilitate the
off-site response force’s effective intervention.


For licensees that process, use, store or transfer nuclear substances that meet or exceed the
threshold of Category 3 nuclear substances, the application should include details regarding the
notification of a local law enforcement agency as required in REGDOC-2.12.3, 
Security of
Nuclear Substances: Sealed Sources and Category I, II and III Nuclear Material 
[5].


Comment on section 4.12.2


 
4.12.3 Security practices
 
The application shall describe the measures in the security program that ensure administrative and
technical measures are implemented, maintained and documented in a security program.


The applicant shall describe how access to prescribed assets is limited to those workers having
the appropriate security clearance, facility site access clearance, or trustworthiness and reliability
verification. Further, the application should identify a process to determine how a valid need-toknow basis will be utilized to determine access to prescribed assets as applicable to the site.


Comment on section 4.12.3


 
4.12.4 Security training and qualification
 
The application shall include adequate provisions indicating all persons with authorized access to
sealed sources or prescribed information at the licensee’s location are made aware of the facility’s
security policies, protocols and practices. These provisions shall identify how the security
awareness program is documented and how it will be annually reviewed. The application shall
also include details on the development of an assured process for ensuring new employees
participate in security awareness training, and refresher training is conducted on a regular basis
(every three years or less) for existing employees.


The application shall describe the duties of any security officers employed or contracted on-site.
The applicant should demonstrate that the security officers are adequately equipped to perform
their assigned duties and tasks.


 This shall include the proposed measures for written procedures and instructions specific to:

 

 
· measures for controlling access to the licensed area
 
· surveillance foot and vehicle patrols
 
· assessment and response to alarms
 
· apprehension and detainment of unarmed intruders
 
· reporting of suspicious activities, including armed intruders, to the local law enforcement
agency
 
· security equipment operation
 
· security training relating to assigned duties



For licensees subject to Part 2 of the Nuclear Security Regulations, the applicant shall describe
their supervisory awareness program identifying that supervisors are trained to recognize
behavioural changes in all personnel, including contractors, that could pose a risk to security at a
facility at which it carries on licensed activities.


Comment on section 4.12.4


 
4.12.5 Cyber security
 
The application should describe a cyber security program. The application should address internal
 and external cyber threats.


The application should describe how the cyber security program is designed, implemented and
maintained as an effective program. The application should provide information on the following
 program elements, including
:


 
· defensive strategy and security architecture
 
· policies and procedures
 
· asset identification and classification
 
· roles and responsibilities of the involved parties
 
· security controls
 
· awareness and training
 
· configuration management
 
· coordination with other programs
 
· incident response, reporting and recovery plan
 
· program review and maintenance
 
· lifecycle approach to cyber assets


Comment on section 4.12.5


 
4.13 Safeguards and non-proliferation
The safeguards and non-proliferation SCA covers the programs and activities required for the
successful implementation of the obligations arising from the Canada/International Atomic
Energy Agency (IAEA) safeguards agreements as well as other measures arising from the 
Treaty
on the Non-Proliferation of Nuclear Weapons 
(IAEA INFCIRC/140) [36].


This section addresses the requirements of the following regulations made under the NSCA:
 
· General Nuclear Safety and Control Regulations, subsection 3(2), paragraphs 3(1)(g) and (h),
10(b) and 12(1)(i), 20(d), and 21(1)(a) and (b); and subsection 23(2)
 
· Class I Nuclear Facilities Regulations, paragraphs 5(h), 6(f) and 7(d)
 
· Nuclear Non-Proliferation Import and Export Control Regulations


 
It also addresses the requirements of the following safeguard agreements:


 
· IAEA INFCIRC/164, Agreement between Government of Canada and IAEA for the
Application of Safeguards in Connection with the Treaty on the Non-Proliferation of Nuclear
 Weapons 
[37]
 
· IAEA INFCIRC/164/Add.1, Protocol Additional to the Agreement between Canada and the
International Atomic Energy Agency for the Application of Safeguards in Connection with the
 Treaty on the Non-Proliferation of Nuclear Weapons 
[38]


Comment on section 4.13


 
4.13.1 General considerations
 
Note: Either before or concurrent with applying for a licence to construct a Class IB processing
facility, the applicant shall complete and submit to the CNSC the IAEA safeguards design
information questionnaire (available upon request from the CNSC International Safeguards
Division). The CNSC encourages applicants to submit the completed questionnaire early,
particularly for novel technologies where safeguards measures have not yet been developed. For
 more information, see REGDOC 2.13.1, 
Safeguards and Nuclear Material Accountancy [39].



The application shall describe how the arrangements address the requirements in REGDOC-
2.13.2, 
Import and Export [40] and REGDOC-2.13.1, Safeguards and Nuclear Material
Accountancy 
[39].


The application should describe measures related to site buildings and structures, operational
parameters and the flow and storage of nuclear material, from the facility’s design and
commissioning phases through to its decommissioning and eventual abandonment.
 

For processing facilities, the non-proliferation program is limited to the tracking and reporting of
foreign obligations and origins of nuclear material.


For the purposes of the application and its review, document ownership will vary between the
 IAEA, the CNSC and the applicant:

· the IAEA is responsible for the generic safeguards approach
· the CNSC is responsible for:
  
· coordinating with the IAEA in developing the generic safeguards approach
  · negotiating the safeguards arrangements with the IAEA for the applicant facility
  · monitoring the applicant’s compliance with safeguards documents, requirements and
obligations
· the applicant is responsible for establishing and implementing the safeguards program
 

Where applicable, the export of nuclear material covered under the non-proliferation regs (spell
out), an separate import/export licence must be obtained for the specific circumstances and
destination.


Comment on section 4.13.1


 
4.13.2 Nuclear accountancy and control
 
The application should describe how the program ensures the collection, storage and reporting of
 information to the CNSC and IAEA. The application should describe measures to ensure that:


 
· nuclear materials are tracked
 
· reports are submitted to the CNSC on:
  
 · the inventory and transfer of nuclear material
 
  · the application of IAEA safeguards


The application should describe adequate provisions for timely submission of accurate reports
and information on nuclear material. Further information is available in REGDOC-2.13.1,
 
Safeguards and Nuclear Material Accountancy [39].


Comment on section 4.13.2


 
4.13.3 Access and assistance to the IAEA
 
The application should describe how the program ensures that the IAEA is able, upon request, to
access the facility for inspections and other verification activities. Additionally, the application
should describe how the program ensures that such activities are supported by facility workers
 and resources.


The application should describe how the effectiveness of safeguards procedures, and assistance to
 the IAEA for site access and inspections, are reviewed.


Comment on section 4.13.3


 
4.13.4 Operational and design information
 
The application should describe:


 
· the processes that collect, store and report relevant operational information to the CNSC and
the IAEA
 
· how the program ensures that the facility’s design information questionnaire is complete and
accurate
 
· how the program ensures that updates provided under the Additional Protocol are reported to
 the CNSC


The application should also describe methods of development and implementation of an
 appropriate safeguards approach based on the facility’s specific designs.


The application should describe how the program engages both the CNSC and the IAEA to
ensure a suitable safeguards approach is taken for its purpose.


 The application should describe adequate provisions for the submission of:


 
· annual operational information
 
· accurate design information of facility structures
 
· processes and procedures


Comment on section 4.13.4


 
4.13.5 Safeguards equipment, containment and surveillance
 
The applicant should demonstrate that adequate resources (for example, power and lighting) are
provided to IAEA equipment and that measures are in place for the protection of IAEA
 equipment and seals.


Comment on section 4.13.5


 
4.14 Packaging and transport
 
The packaging and transport SCA covers programs for the safe packaging and transport of
 nuclear substances to and from the licensed facility.

 

 
This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(e) and 20(a)
 
· Class I Nuclear Facilities Regulations, paragraphs 5(i), 6(e) and (h) and 7(f)
 
· Packaging and Transport of Nuclear Substances Regulations2015


 
It also addresses the requirements of the Transportation of Dangerous Goods Regulations.


Comment on section 4.14


 
4.14.1 Package design and maintenance
 
The application shall describe how the program ensures that all shipping packages are designed
and maintained for the protection and containment of the quantities transported, as per the
 
Packaging and Transport of Nuclear Substances Regulations, 2015, where applicable.


The application shall describe elements such as package certification, package testing, inspection
 and maintenance.


Comment on section 4.14.1


 
4.14.2 Packaging and transport program
 
The applicant shall describe the measures in place to ensure compliance with all requirements of
 the 
Packaging and Transport of Nuclear Substances Regulations, 2015 and the Transportation of
 Dangerous Goods Regulations
.


The application shall describe the measures to ensure that appropriate training is provided for
workers involved in the handling, preparation for transport, and transport of dangerous goods, and
 that training certificates are issued to workers.


Comment on section 4.14.2


 
4.14.3 Registration for use
 
The application shall describe the measures in place to ensure that certified packages are
 registered for use prior to transport.


Comment on section 4.14.3


 
5. Other Regulatory Areas
 
This section addresses the requirements of the following regulations made under the NSCA:


 
· General Nuclear Safety and Control Regulations, paragraphs 3(1)(l) and (m), and sections 29
to 32
 
· Class I Nuclear Facilities Regulations, paragraphs 3(j) and (k)
 
· Canadian Nuclear Safety Commission Cost Recovery Fees Regulations


Comment on section 5


 
5.1 Public information and disclosure program
 
The applicant shall describe how their proposed public information and disclosure program
 (required for all licensees) meets the requirements in REGDOC-3.2.1, 
Public Information
 Disclosure 
[41].


The description shall include how and with what tools the licensee will communicate with the
public, particularly with those persons living in the vicinity of the site, and the general nature and

characteristics of the anticipated effects on the environment and the health and safety of persons
that may result from the operation of the facility.


For new facilities, the applicant should demonstrate that ongoing engagement with appropriate
 parties has been continued from construction activities and integrated into operational activities.


 

Comment on section 5.1


 
5.2 Indigenous engagement
 
The CNSC, as an agent of the Crown, has the responsibility for fulfilling Canada's legal duty to
consult and, where appropriate, to accommodate Indigenous peoples when the CNSC’s decisions
may have had adverse effect on potential or established Indigenous or treaty rights. The CNSC is
committed to meaningful ongoing engagement and consultation with Indigenous groups who
 have an interest in facilities and activities regulated by the CNSC.


 REGDOC-3.2.2, 
Indigenous Engagement [42] provides guidance for licensees whose proposed
projects may raise the Crown's duty to consult. While the CNSC cannot delegate its obligation, it
can delegate procedural aspects of the consultation process to licensees, where appropriate. To
meet CNSC obligations for consultation, the CNSC may use the information collected and
 measures proposed by licensees regarding avoiding, mitigating or offsetting adverse effects.


Comment on section 5.2


 
5.3 Cost recovery and financial guarantees
 
Each facility licensee in Canada has the primary responsibility for ensuring the safety of its
facility, including providing adequate financial resources to support the safety of each facility
 throughout its life.


Comment on section 5.3


 
5.3.1 Cost recovery
 
An operating licence for a processing facility is subject to the requirements of Part 2 of the
 
Canadian Nuclear Safety Commission Cost Recovery Fees Regulations. Any application shall be
accompanied by the prescribed fee, as per the NSCA subsection 24(2). Applicants are responsible
for payment of the annual fees determined by CNSC. Payments are normally requested on a
 quarterly basis and are due to the Receiver General of Canada.


The applicant should discuss the details of the amount and payment plan with the CNSC.


For additional information, refer to the Canadian Nuclear Safety Commission Cost Recovery Fees
 Regulations
.


Comment on section 5.3.1


 
5.3.2 Financial guarantees
 
The application shall describe the financial guarantees for the costs of decommissioning the facility according to the NSCA and the General Nuclear Safety and Control Regulations. The applicant should also provide a cross-reference to the supporting document regarding the value and form of the financial guarantee.


 For more information about financial guarantees and licensing, consult REGDOC-3.3.1, 
Financial Guarantees for Decommissioning of Nuclear Facilities and Termination of Licensed Activities [43].
 

Comment on section 5.3.2


 
Appendix A: Legislative Clauses
 
The information submitted by an applicant for a licence to prepare a site, construct, operate and/or
decommission a Class IB processing facility is based on the relevant clauses from legislation, including
 the 
Nuclear Safety and Control Act (NSCA) and the regulations made under the NSCA. Table A.1 lists
select relevant sections; however, applicants are responsible for ensuring that all requirements under the
 NSCA and regulations for the proposed activities are addressed in an application.


 Table A.1: Clauses in the NSCA and the regulations made under the NSCA, mapped to the relevant
 sections of this licence application guide


Legislation

Clause(s)

Section(s) in this document

Licenced Activity

 

NSCA

24(4)

Every SCA (sections 4.1 through 4.14)

5, Other Matters of Regulatory Interest

All

 

26(a), (e)

Every SCA (sections 4.1 through 4.14)

5, Other Matters of Regulatory Interest

All

 

 

 

 

 

General 

3(1)(a)

3.1.2, Applicant’s name and business address

All

 

Nuclear 

3(1)(b)

3.2.2, Statement of the main purpose

All

 

Safety and Control Regulations

3(1)(c)

3.2.5, Nuclear substances

4.9, Environmental protection

4.11, Waste management

All

 

(GNSCR)

3(1)(d)

3.2.2, Statement of the main purpose

4.4, Safety analysis

4.5, Physical design

4.6, Fitness for service

4.10, Emergency management and fire protection

4.11, Waste management

4.12, Security

All

 

 

3(1)(e)

4.4, Safety analysis

4.5, Physical design

4.6, Fitness for service

4.7, Radiation protection

4.9, Environmental protection

4.11, Waste management

4.12, Security

4.14, Packaging and transport

All

 

 

3(1)(f)

4.7, Radiation protection

All

 

 

3(1)(g)

4.5, Physical design

4.12, Security

4.13, Safeguards and non‑proliferation

All

 

 

3(1)(h)

4.5, Physical design

4.12, Security

4.13, Safeguards and non‑proliferation

All

 

 

3(1)(i)

4.4, Safety analysis

4.5, Physical design

4.6, Fitness for service

4.7, Radiation protection

4.9, Environmental protection

4.10, Emergency management and fire protection (all requirements related to fire)

4.11, Waste management

4.12, Security

All

 

 

3(1)(j)

4.5, Physical design

4.6, Fitness for service

4.11, Waste management

All

 

 

3(1)(k)

3.1.7, Identification of persons responsible for management and control of the licensed activity

4.1, Management system

4.2, Human performance

4.3, Operating performance

All

 

 

3(1)(l)

5, Other matters of regulatory interest

All

 

 

3(1)(m)

5. Other matters of regulatory interest

All

 

 

3(2)

4.13, Safeguards and non‑proliferation

All

 

 

10(b)

4.13, Safeguards and non‑proliferation

All

 

 

12(1)(a)

4.1, Management system

4.2, Human performance management

4.7, Radiation protection

4.10, Emergency management and fire protection

All

 

 

12(1)(b)

4.2, Human performance management

4.7, Radiation protection

4.10, Emergency management and fire protection

All

 

 

12(1)(c)

4.3, Operating performance

4.4, Safety analysis

4.5, Physical design

4.6, Fitness for service

4.7, Radiation protection

4.8, Conventional health and safety

4.9, Environmental protection

4.10, Emergency management and fire protection

4.11, Waste management

4.12, Security

All

 

 

12(1)(d)

4.7, Radiation protection

4.10, Emergency management and fire protection

All

 

 

12(1)(e)

4.2, Human performance management

4.3, Operating performance

4.7, Radiation protection

4.10, Emergency management and fire protection

All

 

 

12(1)(f)

4.3, Operating performance

4.4, Safety analysis

4.5, Physical design

4.6, Fitness for service

4.7, Radiation protection

4.9, Environmental protection

4.10, Emergency management and fire protection

All

 

 

12(1)(g)

4.10, Emergency management and fire protection

4.12, Security

All

 

 

12(1)(h)

4.10, Emergency management and fire protection

4.12, Security

All

 

 

12(1)(i)

4.13, Safeguards and non‑proliferation

All

 

 

12(1)(j)

4.2, Human performance management

4.12, Security

All

 

 

15

3.1.7, Identification of persons responsible for management and control of the licensed activity

4.1, Management system

All

 

 

15(a)

3.1.4, All persons who have authority to interact for the applicant with the CNSC

3.1.9, Legal signing authority

All

 

 

15(b)

3.1.4, All persons who have authority to interact for the applicant with the CNSC

3.1.7, Identification of persons responsible for management and control of the licensed activity

All

 

 

17(a)

4.2, Human performance management

4.3, Operating performance

4.7, Radiation protection

4.8, Conventional health and safety

4.9, Environmental protection

All

 

 

17(b)

4.2, Human performance management

4.3, Operating performance

4.7, Radiation protection

4.8, Conventional health and safety

4.9, Environmental protection

All

 

 

17(c)

4.1, Management system

4.2, Human performance management

4.3, Operating performance

4.7, Radiation protection

4.8, Conventional health and safety

4.9, Environmental protection

4.12, Security

All

 

 

17(d)

4.2, Human performance management

4.3, Operating performance

4.7, Radiation protection

4.8, Conventional health and safety

All

 

 

17(e)

4.1, Management system

4.2, Human performance management

4.3, Operating performance

4.7, Radiation protection

4.8, Conventional health and safety

4.9, Environmental protection

4.12, Security

All

 

 

20(a)

4.14, Packaging and transport

All

 

 

20(d)

4.13, Safeguards and non‑proliferation

All

 

 

21

4.12, Security

All

 

 

21(1)(a)

4.13, Safeguards and non‑proliferation

All

 

 

21(1)(b)

4.13, Safeguards and non‑proliferation

All

 

 

22

4.12, Security

All

 

 

23

4.12, Security

All

 

 

23(2)

4.13, Safeguards and non‑proliferation

All

 

 

27

[…keep a copy of all info relating to the licence that is submitted by the licensee to the Commission… see section 3]

4.1, Management system

All

 

 

28

4.1, Management system

All

 

 

28(1)

4.12, Security

All

 

 

29

4.3, Operational performance

4.7, Radiation protection

4.12, Security

5.1, Reporting requirements

All

 

 

30

4.3, Operating performance

4.12, Security

5.1, Reporting requirements

All

 

 

31

4.3, Operating performance

5.1, Reporting requirements

All

 

 

32

4.3, Operating performance

5.1, Reporting requirements

All

 

 

 

 

 

 

Canadian Nuclear Safety Commission Cost Recovery Fees Regulations

all

5.4, Cost recovery, financial guarantees and insurance

All

 

 

 

 

 

 

Class I Nuclear Facilities Regulations

3(a)

3.2.3, Description of site

4.5, Physical design

4.10, Emergency management and fire protection

4.12, Security

All

 

 

3(b)

3.2.3, Description of site

4.4, Safety analysis

4.5, Physical design

4.12, Security

All

 

 

3(c)

3.1.6, Evidence that the applicant is the owner of the site…

All

 

 

3(d)

4.1, Management system

4.4, Safety analysis

4.5, Physical design

All

 

 

3(e)

3.2.5, Nuclear and hazardous substances

4.8, Conventional health and safety

4.9, Environmental protection

4.11, Waste management

All

 

 

3(f)

4.1, Management system

4.2, Human performance management

4.6, Fitness for service

4.8, Conventional health and safety

4.10, Emergency management and fire protection

4.11, Waste management

All

 

 

3(g)

4.9, Environmental protection

All

 

 

3(h)

4.8, Conventional health and safety

4.9, Environmental protection

All

 

 

3(i)

4.5, Physical design

4.12, Security

All

 

 

3(j)

5, Other matters of regulatory interest

All

 

 

3(k)

4.11, Waste management

All

 

 

4(a)

4.3, Operating performance

4.5, Physical design

To prepare site

 

 

4(b)

4.5, Physical design

To prepare site

 

 

4(c)

4.5, Physical design

4.9, Environmental protection

To prepare site

 

 

4(d)

4.1, Management system

4.5, Physical design

To prepare site

 

 

4(e)

4.8, Conventional health and safety

4.9, Environmental protection

To prepare site

 

 

5(a)

4.5, Physical design

To construct

 

 

5(b)

4.5, Physical design

4.9, Environmental protection

To construct

 

 

5(c)

4.1, Management system

4.3, Operating performance

To construct

 

 

5(d)

4.5, Physical design

4.6, Fitness for service

To construct

 

 

5(e)

4.5, Physical design

4.6, Fitness for service

To construct

 

 

5(f)

4.4, Safety analysis

4.6, Fitness for service

To construct

 

 

5(g)

4.1, Management system

To construct

 

 

5(h)

4.12, Security

4.13, Safeguards and non-proliferation

To construct

 

 

5(i)

4.1, Management system

4.2, Human performance management

4.3, Operating performance

4.4, Safety analysis

4.7, Radiation protection

4.8, Conventional health and safety

4.9, Environmental protection

4.10, Emergency management and fire protection

4.11, Waste management

4.12, Security

4.14, Packaging and transport

To construct

 

 

5(j)

4.4, Safety analysis

4.5, Physical design

4.7, Radiation protection

4.9, Environmental protection

4.11, Waste management

To construct

 

 

5(k)

4.4, Safety analysis

4.7, Radiation protection

4.9, Environmental protection

4.10, Emergency management and fire protection

4.11, Waste management

To construct

 

 

5(l)

4.1, Management system

4.2, Human performance management

4.3, Operating performance

4.7, Radiation protection

To construct

 

 

5(m)

4.2, Human performance management

4.3, Operating performance

4.6, Fitness for service

4.7, Radiation protection

To construct

 

 

6(a)

4.4, Safety analysis

4.5, Physical design

4.6, Fitness for service

To operate

 

 

6(b)

4.4, Safety analysis

4.5, Physical design

4.6, Fitness for service

To operate

 

 

6(c)

4.4, Safety analysis

To operate

 

 

6(d)

4.1, Management system

4.3, Operating performance

4.6, Fitness for service

To operate

 

 

6(e)

4.1, Management system

4.3, Operating performance

4.7, Radiation protection

4.8, Conventional health and safety

4.11, Waste management

4.14, Packaging and transport

To operate

 

 

6(f)

4.13, Safeguards and non-proliferation

To operate

 

 

6(g)

4.1, Management system

4.3, Operating performance

4.5, Physical design

To operate

 

 

6(h)

4.1, Management system

4.2, Human performance

4.3, Operating performance

4.4, Safety analysis

4.5, Physical design

4.7, Radiation protection

4.8, Conventional health and safety

4.9, Environmental protection

4.10, Emergency management and fire protection

4.11, Waste management

4.12, Security

4.14, Packaging and transport

To operate

 

 

6(i)

4.4, Safety analysis

4.5, Physical design

4.7, Radiation protection

4.9, Environmental protection

4.11, Waste management

To operate

 

 

6(j)

4.4, Safety analysis

4.5, Physical design

4.9, Environmental protection

4.11, Waste management

To operate

 

 

6(k)

4.1, Management system

4.2, Human performance management

4.3, Operating performance

4.4, Safety analysis

4.5, Physical design

4.7, Radiation protection

4.9, Environmental protection

4.10, Emergency management and fire protection

4.12, Security

To operate

 

 

6(l)

4.1, Management system

4.2, Human performance management

4.12, Security

To operate

 

 

6(m)

4.1, Management system

4.2, Human performance management

4.5, Physical design

4.6, Fitness for service

4.7, Radiation protection

To operate

 

 

6(n)

4.1, Management system

4.2, Human performance management

4.5, Physical design

4.6, Fitness for service

4.7, Radiation protection

To operate

 

 

7(a)

4.3, Operating performance

4.11, Waste management

To decommission

 

 

7(b)

4.11, Waste management

To decommission

 

 

7(c)

4.1, Management system

4.3, Operating performance

4.11, Waste management

To decommission

 

 

7(d)

4.13, Safeguards and non-proliferation

To decommission

 

 

7(e)

4.7, Radiation protection

4.11, Waste management

To decommission

 

 

7(f)

4.1, Management system

4.2, Human performance

4.3, Operating performance

4.4, Safety analysis

4.5, Physical design

4.7, Radiation protection

4.8, Conventional health and safety

4.9, Environmental protection

4.10, Emergency management and fire protection

4.11, Waste management

4.12, Security

4.14, Packaging and transport

To decommission

 

 

7(g)

4.4, Safety analysis

4.5, Physical design

4.7, Radiation protection

4.9, Environmental protection

4.11, Waste management

To decommission

 

 

7(h)

4.5, Physical design

4.9, Environmental protection

4.11, Waste management

To decommission

 

 

7(i)

4.1, Management system

4.2, Human performance management

4.3, Operating performance

4.5, Physical design

4.7, Radiation protection

4.8, Conventional health and safety

4.9, Environmental protection

4.10, Emergency management and fire protection

To decommission

 

 

7(j)

4.1, Management system

4.2, Human performance management

4.7, Radiation protection

To decommission

 

 

7(k)

4.11, Waste management

To decommission

 

 

14(1)

4.1, Management system

4.9, Environmental protection

4.11, Waste management

All

 

 

14(2)

4.1, Management system

4.2, Human performance management

4.3, Operating performance

4.5, Physical design

4.6, Fitness for service

4.7, Radiation protection

4.9, Environmental protection

4.11, Waste management

To operate

 

 

14(3)

4.1, Management system

4.2, Human performance management

4.3, Operating performance

4.7, Radiation protection

4.11, Waste management

To decommission

 

 

14(4)

4.1, Management system

To operate

To decommission

 

 

14(5)

4.1, Management system

4.2, Human performance management

To operate

To decommission

 

 

 

 

 

 

Nuclear Non-proliferation Import and Export Control Regulations

all

4.13, Safeguards and non‑proliferation

To construct

To operate

To decommission

 

 

 

 

 

 

Nuclear Security 

all

4.5, Physical design

4.12, Security

All

 

Regulations

3(b)

3.2.3, Description of site

All

 

 

16

3.2.3, Description of site

All

 

 

37(1), (2) and (3)

4.1, Management system

All

 

 

38

4.1, Management system

4.2, Human performance management

All

 

 

 

 

 

 

Nuclear 

5

4.7, Radiation protection

All

 

Substances and 

8

4.7, Radiation protection

All

 

Radiation 

20

4.7, Radiation protection

All

 

Devices 

23

4.7, Radiation protection

All

 

Regulations

36(1)(a)

4.1, Management system

4.12, Security

All

 

 

36(1)(b)

4.1, Management system

All

 

 

36(1)(c)

4.1, Management system

All

 

 

36(1)(d)

4.1, Management system

4.12, Security

All

 

 

36(1)(e)

4.1, Management system

All

 

 

 

 

 

 

Packaging and Transport of Nuclear Substances Regulations, 2015

all

4.14, Packaging and transport

All

 

 

 

 

 

 

Radiation Protection Regulations

1(3)

4.3, Operating performance

4.4, Safety analysis

4.5, Physical design

4.6, Fitness for service

4.7, Radiation protection

4.9, Environmental protection

4.11, Waste management

All

 

 

4

4.4, Safety analysis

4.6, Fitness for service

4.7, Radiation protection

4.9, Environmental protection

4.11, Waste management

All

 

 

5-12

4.7, Radiation protection

All

 

 

13

4.3, Operating performance

4.4, Safety analysis

4.6, Fitness for service

4.7, Radiation protection

4.11, Waste management

All

 

 

14

4.3, Operating performance

4.4, Safety analysis

4.6, Fitness for service

4.7, Radiation protection

4.11, Waste management

All

 

 

15

4.3, Operating performance

4.4, Safety analysis

4.6, Fitness for service

4.7, Radiation protection

4.11, Waste management

All

 

 

16

4.7, Radiation protection

All

 

 

20

4.7, Radiation protection

4.11, Waste management

All

 

 

21-23

4.7, Radiation protection

4.11, Waste management

All

 






Comment on appendix A



 
Appendix B: Safety and Control Areas
 
The CNSC’s regulatory requirements and expectations for the safety performance of programs are
grouped into three functional areas and 14 safety and control areas (SCAs). The SCAs are further divided
into specific areas that define the key components of each SCA. Table A shows a list of the functional
areas, SCAs and the specific areas that define the key components of each SCA.


 Table A: The CNSC’s functional areas, safety and control areas, and specific areas

Functional area

Safety and control area (SCA)

Specific area

Management

1. Management system

Management system

 

Organization

 

Performance assessment, improvements and management review

 

Operating experience (OPEX)

 

Change management

 

Safety culture

 

Configuration management

 

Records management

 

Management of contractors

 

Business continuity

 

2. Human performance management

Human performance program

 

Personnel training

 

Personnel certification

 

Initial certification examinations and requalification tests

 

Work organization and job design

 

Fitness for duty

 

3. Operating performance

Conduct of licensed activities

 

Procedures

 

Reporting and trending

 

Outage management performance

 

Safe operating envelope

 

Severe accident management and recovery

 

Accident management and recovery

Facility and equipment

4. Safety analysis

Deterministic safety analysis

Hazard analysis

 

Probabilistic safety assessment

 

Criticality safety

 

Severe accident analysis

 

Management of safety issues (including R&D programs)

 

5. Physical design

Design governance

 

Site characterizations

 

Facility design

 

Structure design

 

System design

 

Components design

 

6. Fitness for service

Equipment fitness for service / equipment performance

 

Maintenance

 

Structural integrity

 

Aging management

 

Chemistry control

 

Periodic inspections and testing

Core control processes

7. Radiation protection

Application of ALARA

Worker dose control

Radiation protection program performance

Radiological hazard control

 

8. Conventional health and safety

Performance

 

Practice

 

Awareness

 

9. Environmental protection

Effluent and emissions control (releases)

 

Environmental management system (EMS)

 

Assessment and monitoring

 

Protection of the public

 

Environmental risk assessment

 

10. Emergency management and fire protection

Conventional emergency preparedness and response

Nuclear emergency preparedness and response

Fire emergency preparedness and response

 

11. Waste management

Waste characterization

 

Waste minimization

 

Waste management practices

 

Decommissioning plans

 

12. Security

Facilities and equipment

 

Response arrangements

 

Security practices

 

Drills and exercises

 

Cyber Security

 

13. Safeguards and non-proliferation

Nuclear material accountancy and control

 

Access and assistance to the IAEA

 

Operational and design information

 

Safeguards equipment, containment and surveillance

 

Import and export

 

14. Packaging and transport

Package design and maintenance

 

Packaging and transport

 

Registration for use


 

Comment on appendix B



 
Appendix C: Regulatory Documents and Industry Standards


C.1 Regulatory documents and industry standards to be applied as requirements for all applicants

Licensees are required to meet these requirements, codes and standards. The application shall include a description of how these documents and standards will be met.

Document source

Document number 

Document title

Related SCAs

CNSC

REGDOC-2.1.2

Safety Culture

1

CNSC

REGDOC-2.2.2

Personnel Training

2, 10

CNSC

REGDOC-2.2.4

Fitness for Duty, Volume III: Nuclear Security Officer Medical, Physical and Psychological Fitness

2, 12

CNSC

REGDOC-2.3.2

Accident Management

3, 10

CNSC

REGDOC-2.4.4

Safety Analysis for Class IB Nuclear Facilities

3, 4

CNSC

REGDOC-2.7.1

Radiation Protection

7

CNSC

REGDOC-2.9.1

Environmental Protection: Environmental Policy, Assessments and Protection Measures

3, 9

CNSC

REGDOC-2.10.1

Nuclear Emergency Preparedness and Response

10

CNSC

REGDOC-2.11.1

Waste Management, Volume I: Management of Radioactive Waste

11

CNSC

REGDOC-2.11.2

Decommissioning

11

CNSC

REGDOC-2.13.1

Safeguards and Nuclear Material Accountancy

3, 13

CNSC

REGDOC-3.2.1

Public Information and Disclosure

N/A

CSA Group

N286

Management system requirements for nuclear facilities

1, 3

CSA Group

N288.1

Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities

3, 9

CSA Group

N288.4

Environmental monitoring programs at Class I nuclear facilities and uranium mines and mills

3, 9

CSA Group

N288.5

Effluent monitoring programs at Class I nuclear facilities and uranium mines and mills

3, 9

CSA Group

N288.6

Environmental risk assessments at Class I nuclear facilities and uranium mines and mills

3, 9

CSA Group

N292.3

Management of low- and intermediate-level radioactive waste

3, 11

CSA Group

N393

Fire protection for facilities that process, handle or store nuclear substances

5, 6, 10

CSA Group

N294

Decommissioning of facilities containing nuclear substances

3, 11

CSA Group

B51

Boiler, Pressure Vessel, and Pressure Piping Code

3, 5, 6


C.2 Regulatory documents and industry standards to be applied as requirements for new facilities and addressed as guidance for existing facilities

In addition to the documents listed in Table C.1, applicants for new facilities are required to meet the
requirements, codes and standards listed in Table C.2. The application shall include a description of how
these documents and standards will be met. For any licence renewals for existing facilities, the application
shall address these documents and standards to the extent practicable (for example, in a periodic safety
 review).

Document
 source

Document
 number

Document title 

Related
 SCAs

CNSC 

REGDOC-2.10.1 

Nuclear Emergency Preparedness and Response 

10

ASME 

B31.1 

Power Piping 

3, 5, 6

ASME 

BPVC 

Boiler and Pressure Vessel Code 

3, 5, 6

CSA Group 

N1600 

General requirements for nuclear emergency management
 programs

10


C.3 Regulatory documents and industry standards to be addressed as guidance


 For all facilities, the application should demonstrate that the guidance in the following regulatory
 documents and industry standards has been considered


Document source

Document number 

Document title

Related SCAs

CNSC

REGDOC-3.2.2

Aboriginal Engagement

N/A

CNSC

REGDOC-3.3.1

Financial Guarantees for Decommissioning of Nuclear Facilities and Termination of Licensed Activities

3, 11

CNSC

REGDOC-2.12.3

Security of Nuclear Substances: Sealed Sources and Category I, II and III Nuclear Material

12, 14

CNSC

REGDOC-2.5.1

General Design Considerations: Human Factors

2, 4, 5

CNSC

REGDOC-2.2.5

Minimum Staff Complement

2, 3

CNSC

REGDOC-2.13.1

Safeguards and Nuclear Material Accountancy

3, 13

ASME

ASME/ANS

RA-Sa-2009

Addenda to ASME/ANS RA-S-2880 Standard for Level 1/ Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications

4

ASME

B31.3

Process Piping Guide

3, 5, 6

ASME

B31.5

Refrigeration Piping and Heat Transfer Components

3, 5, 6

EPRI

TR-1019194

Guidelines for Performance of Internal Flooding Probabilistic Risk Assessment

4

IAEA

INSAG‑4

Safety Series No. 75: Safety Culture

4

U.S. DOD

UFC 3-340‑02

Structures to Resist the Effects of Accidental Explosions

12

U.S. NRC

NUREG-0700

Human-System Interface Design Review Guidelines

2, 3, 5

U.S. NRC

NUREG-0711 Rev. 3

Human Factors Engineering Program Review Model

2, 4, 5


Comment on appendix C

 
 
Glossary
 
For definitions of terms used in this document, see REGDOC-3.6, Glossary of CNSC Terminology, which
 includes terms and definitions used in the 
Nuclear Safety and Control Act and the regulations made under
it, and in CNSC regulatory documents and other publications. REGDOC-3.6 is provided for reference and
 information.

 


Comment on glossary



 
References
 
The CNSC may include references to information on best practices and standards such as those published
by CSA Group. With permission of the publisher, CSA Group, all nuclear-related CSA standards may be
 viewed at no cost through the CNSC Web page “
How to gain free access to all nuclear-related CSA
 standards
”.
 1. International Atomic Energy Agency (IAEA), Specific Safety Requirements No. SSR-4 
Safety of
 Nuclear Fuel Cycle Facilities
, Vienna, Austria, 2017.
 2. CNSC, 
REGDOC-3.5.3, Regulatory Fundamentals, Ottawa, Canada, 2018.
 3. CNSC
, REGDOC-3.5.1, Licensing Process for Class I Nuclear Facilities and Uranium Mines
 and Mills
, Ottawa, Canada, 2017.
 4. CNSC, 
REGDOC-2.9.1, Environmental Protection: Environmental Principles, Assessments and
 Protection Measures
, Ottawa, Canada, 2017.
 5. CNSC, 
REGDOC-2.12.3, Security of Nuclear Substances: Sealed Sources and Category I, II and
 III Nuclear Materials
, Ottawa, Canada, 2019.
 6. CSA Group, CSA N286, 
Management system requirements for nuclear facilities, Toronto,
Canada, 2014.
 7. CNSC, 
REGDOC-2.1.2, Safety Culture, Ottawa, Canada, 2018.
 8. CNSC, 
REGDOC-2.2.2, Personnel Training, Ottawa, Canada, 2016.
 9. CNSC, 
REGDOC-2.2.5, Minimum Staff Complement, Ottawa, Canada, 2019.
 10. CNSC, 
REDOC-2.5.1, General Design Considerations: Human Factors, Ottawa, Canada, 2019.
 11. CNSC, 
REGDOC-2.2.4, Fitness for Duty: Managing Worker Fatigue, Ottawa, Canada, 2017.
 12. CNSC, 
REGDOC-2.2.4, Fitness for Duty, Volume II: Managing Alcohol and Drug Use, Ottawa,
Canada, 2017.
 13. CNSC, 
REGDOC-3.1.2, Reporting Requirements, Volume I: Non-Power Reactor Class I
 Facilities and Uranium Mines and Mills
, Ottawa, Canada, 2018.
 14. CNSC, 
REGDOC-2.4.4, Safety Analysis for Class IB Nuclear Facilities, (under development).
 15. CNSC, 
REGDOC-2.4.3, Nuclear Criticality Safety, Ottawa, Canada, 2019.
 16. IAEA, Specific Safety Requirements No. SSR-1 
Site Evaluation for Nuclear Installations,
Vienna, Austria, 2019.
 17. IAEA, Specific Safety Guide No. SSG-5, 
Safety of Conversion Facilities and Uranium
 Enrichment Facilities
, Vienna, Austria, 2010.
 18. IAEA, SSG-6, 
Safety of Uranium Fuel Fabrication FacilitiesVienna, Austria, 2010.
 

 
19. IAEA, Specific Safety Guide No. SSG-7, Safety of Uranium and Plutonium Mixed Oxide Fuel
 Fabrication Facilities
, Vienna, Austria, 2010.
 20. IAEA, Specific Safety Guide No. SSG-42, 
Safety of Nuclear Fuel Reprocessing Facilities,
Vienna, Austria, 2017.
 21. IAEA, Specific Safety Guide No. SSG-43, 
Safety of Nuclear Fuel Cycle Research and
 Development Facilities
, Vienna, Austria, 2017.
 22. CNSC, 
REGDOC-2.5.6, Design of Rooms Where Unsealed Nuclear Substances Are Handled,
Ottawa, Canada, (under development).
 23. CNSC, 
REGDOC-2.7.1, Radiation Protection, Ottawa, Canada, 2021.
 24. International Organization for Standardization, ISO 13485, 
Medical devices – Quality
 management systems – Requirements for regulatory purpose
s, London, United Kingdom, 2016.
 25. CNSC, 
REGDOC-2.7.2, Dosimetry, Volume I: Ascertaining Occupational Dose, Ottawa, Canada,
2021
 26. CSA Group, CSA N288.6, 
Environmental risk assessments at Class I nuclear facilities and
 uranium mines and mills
, Toronto, Canada, 2017.
 27. CSA Group, CSA B51, 
Boiler, pressure vessel, and pressure piping code, Toronto, Canada,
2019.
 28. CNSC, 
REGDOC-2.8.1, Conventional Health and Safety, Ottawa, Canada, 2019.
 29. CNSC, 
REGDOC-2.9.2, Controlling Releases to the Environment, Ottawa, Canada, (under
development).
 30. CNSC, 
REGDOC-2.10.1, Nuclear Emergency Preparedness and Response, Ottawa, Canada,
2017.
 31. CNSC, 
REGDOC-2.10.2, Fire Protection, Ottawa, Canada, (under development).
 32. CNSC, 
REGDOC-2.11, Framework for Radioactive Waste Management and Decommissioning
 in 
Canada, Ottawa, Canada, 2021.
 33. CNSC, 
REGDOC-2.11.1, Waste Management, Volume I: Management of Radioactive Waste,
Ottawa, Canada, 2021.
 34. CNSC, 
REGDOC-2.11.2, Decommissioning, Ottawa, Canada, 2021.
 35. CNSC, 
Guidance Document on Confidential Filings, Ottawa, Canada, 2014.
 36. IAEA, 
Treaty on the Non-Proliferation of Nuclear Weapons, IAEA INFCIRC/140, 1970.
 37. 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,
 Vienna, Austria, 1972.

 

 
38. IAEA, Protocol Additional to the Agreement between Canada and the International Atomic
 Energy Agency for the Application of Safeguards in Connection with the Treaty on the NonProliferation of Nuclear Weapons
, IAEA INFCIRC/164/Add 1, Vienna, Austria, 2000.
 39. CNSC, 
REGDOC-2.13.1, Safeguards and Nuclear Material Accountancy, Ottawa, Canada, 2018.
 40. CNSC, 
REGDOC-2.13.2, Import and Export, Ottawa, Canada, 2018.
 41. CNSC, 
REGDOC-3.2.1, Public Information and Disclosure, Ottawa, Canada, 2018.
 42. CNSC, 
REGDOC-3.2.2, Indigenous Engagement, Ottawa, Canada, 2018.
 43. CNSC, 
REGDOC-3.3.1, Financial Guarantees for Decommissioning of Nuclear Facilities and
 Termination of Licensed Activities
, Ottawa, Canada, 2021.
 

Comment on references


 
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:

1.0 

Regulated facilities and activities

Series 1.1 

Reactor facilities

1.2 Class IB facilities
1.3 Uranium mines and mills
1.4 Class II facilities
1.5 Certification of prescribed equipment
 1.6 Nuclear substances and radiation devices

2.0 

Safety and control areas

Series 2.1 

Management system

2.2 Human performance management
2.3 Operating performance
2.4 Safety analysis
2.5 Physical design
2.6 Fitness for service
2.7 Radiation protection
2.8 Conventional health and safety
2.9 Environmental protection
2.10 Emergency management and fire protection
2.11 Waste management
2.12 Security
2.13 Safeguards and non-proliferation
 2.14 Packaging and transport

3.0 

Other regulatory areas

Series 3.1 

Reporting requirements

3.2 Public and Indigenous engagement
3.3 Financial guarantees
3.4 Commission proceedings
3.5 CNSC processes and practices
3.6 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 for
 the latest 
list of regulatory documents.






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Page published: 12 October 2021, 13:53