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Report Card on Nuclear Power Plant Performance as of January 2007
CNSC staff assesses licensee programs (“P”) and their implementation (“I”) separately, according to five ratings:
B = Meets requirements
C = Below requirements
D = Significantly below requirements
E = Unacceptable
Safety Area/Program |
P or |
Bruce |
Darlington |
Pickering |
Gentilly-2 |
Point |
|||
I |
A |
B |
A |
B |
|||||
Operating Performance |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
B |
B |
B |
||
Organization and Plant |
P |
B |
B |
B |
B |
B |
B |
B |
|
Management |
I |
A |
A |
B |
C |
B |
B |
B |
|
Operations |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
B |
B |
B |
||
Occupational Health and |
P |
B |
B |
B |
B |
B |
B |
B |
|
Safety (non-radiological) |
I |
A |
B |
B |
B |
B |
B |
B |
|
Performance Assurance |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
B |
B |
B |
||
Quality Management |
P |
C |
C |
B |
B |
B |
B |
B |
|
I |
C |
B |
B |
B |
B |
B |
B |
||
Human Factors |
P |
B |
B |
B |
B |
B |
B |
C |
|
I |
B |
B |
B |
C |
B |
B |
C |
||
Training, Examination, |
P |
B |
B |
B |
B |
B |
B |
B |
|
and Certification |
I |
B |
B |
B |
B |
B |
B |
B |
|
Design and Analysis |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
B |
B |
B |
||
Safety Analysis |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
B |
B |
B |
||
Safety Issues |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
B |
B |
B |
||
Design |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
C |
B |
B |
||
Equipment Fitness |
P |
B |
B |
B |
B |
B |
B |
B |
|
for Service |
I |
B |
B |
B |
B |
B |
B |
B |
|
Maintenance |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
C |
B |
B |
B |
C |
B |
B |
||
Structural Integrity |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
B |
B |
B |
||
Reliability |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
B |
B |
B |
||
Equipment Qualification |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
C |
B |
B |
B |
B |
||
Emergency |
P |
A |
A |
A |
A |
A |
A |
A |
|
Preparedness |
I |
A |
A |
A |
A |
A |
B |
B |
|
Environmental |
P |
B |
B |
B |
B |
B |
B |
B |
|
Protection |
I |
B |
B |
B |
B |
B |
B |
B |
|
Radiation Protection |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
A |
B |
B |
B |
B |
||
Site Security |
P |
Secret |
|||||||
I |
Secret |
||||||||
Safeguards |
P |
B |
B |
B |
B |
B |
B |
B |
|
I |
B |
B |
B |
B |
B |
B |
B |
||
Note: “C” grades are highlighted.
S-337, Design Requirements for Nuclear Power Plants |
This document provides new design categorization information based on years of regulatory experience and international information. The contents of this document were a priority in 2006-07, and the document will be released for consultation in the first quarter of 2007-08. |
S-336, CNSC Safeguards and Nuclear Non-Proliferation Reporting Requirements |
This document describes the reporting requirements to attain uniformity of licensee accounting records and reports of controlled nuclear substances, including special fissionable and source material, equipment and information. This draft regulatory standard was issued in September 2006 for public comment, and the comment period closed in December 2006. Issuance is planned for early 2008. |
G-320, Assessing the Long-Term Safety of Radioactive Waste Management |
This document was issued in 2006 and assists applicants for new licences and for licence renewals in assessing the long-term safety of radioactive waste management on the environment and on the health and safety of people. The document addresses long-term care and maintenance considerations, post-decommissioning objectives, assessment criteria, assessment strategies and level of detail, the selection of time frames and definition of assessment scenarios, and identification of receptors and critical groups. |
G-144, Trip Parameter Acceptance Criteria for Safety Analysis of CANDU Nuclear Power Plants |
This document was issued in May 2006. It provides guidance to licensees who operate CANDU nuclear power plants regarding reactor trip parameters to preclude direct or consequential failures of reactor fuel or reactor pressure tubes. |
G-306, Severe Accident Management Program for Nuclear Reactors |
This document was issued in May 2006 and provides guidance to licensees on the development and implementation of a severe accident management program. |
G-360, Life Extension of Nuclear Power Plants |
This document informs licensees about the steps and phases to consider when undertaking a project to extend the life of a nuclear power plant. The document addresses key considerations for establishing project scope, as well as managing and executing the project. It was issued for public comment in May 2006 and the comment period closed in July 2006. The document is scheduled for issuance in late 2007. |
G–341, Control Of The Export And Import Of Risk-Significant Sealed Sources |
The CNSC implemented an enhanced export and import control program for risk-significant sealed sources at the end of 2006-07. The CNSC issued this regulatory document in February 2007 for consultation and will accept comments until December 2007. The document is scheduled for publication by the end of 2007-08. |
P-325, Nuclear Emergency Management |
This regulatory policy was issued in May 2006. It provides guiding principles and direction for CNSC staff activities relating to nuclear emergency management. |
Commission documentation is available on the CNSC Web site at www.nuclearsafety.gc.ca
Class IA Nuclear Facilities
Atomic Energy of Canada Limited:
Bruce Power Inc.:
Hydro-Québec:
La Corporation de l’École Polytechnique:
New Brunswick Power Nuclear Corporation:
Ontario Power Generation Inc.:
Class IB Nuclear Facilities
Cameco Corporation:
588972 Alberta Limited, operated as Enviropac:
MDS Nordion:
SRB Technologies (Canada) Inc.:
Zircatec Precision Industries Inc.:
TRIUMF Accelerators Inc.:
Uranium Mines and Mills
AREVA Resources Canada Inc.:
Cameco Corporation:
COGEMA Resources Inc.:
Rio Algom Limited:
Waste Management Facilities
Cameco Corporation:
Hydro-Québec:
Low-Level Radioactive Waste Management Office:
Ontario Power Generation Inc.:
Information Sources
For further information or to request publications, contact:
Canadian Nuclear Safety Commission
Office of Communications and Regulatory Affairs
280 Slater Street, P.O. Box 1046, Station B
Ottawa, Ontario K1P 5S9
Telephone: 613-995-5894 or 1-800-668-5284 (within Canada) Fax: 613-995-5086
e-mail: info@cnsc-ccsn.gc.ca
The following information is available on the CNSC Web site at www.nuclearsafety.gc.ca
Information on the plans, priorities, and activities of the CNSC may be found in:
The CNSC administers the following Acts and associated regulations:
For further information you may also consult the CNSC Web site at www.nuclearsafety.gc.ca
[1] The Canadian Nuclear Safety Commission or CNSC refers to the total organization. The tribunal component is referred to as the Commission and the staff component as CNSC staff.
[2] Type I inspections are on-site audits and evaluations of a licensee’s programs, processes and practices. Type II inspections are routine (item-by-item) checks and rounds that typically focus on the outputs, or performance of licensee programs, processes and practices. Findings from Type II inspections play a key role in identifying where a Type I inspection may be required to determine systemic problems in licensee programs, processes or practices.
[3] Compliance and licensing results are based on a subset of the performance data available.
[4] Using the CNSC’s risk-informed approach to regulation, initial priority was given to the completion of reports whose results were of greater significance.
[5] CNSC workload increases were observed as a result of the rapid expansion of nuclear medicine facilities in Canadian hospitals
[6] For power reactors, unless major issues arise, findings from field inspections and control room inspections will be reported on a quarterly basis, within 40 business days of end of quarter.
[7] The screening and hearing processes do not apply to operations of the Directorate of Nuclear Substances Regulation.
[8] The magnitude of public interventions in some licensing decisions required an extension of the time to complete the hearing process.
[9] All reports experienced delays of a few days due to delays in final approvals and in document production. All delays were pre-cleared and were acceptable to the Treasury Board Secretariat.