REGDOC-3.6, Glossary of CNSC Terminology - Glossary - L

With respect to nuclear material accounting, a unique three- or four-digit number used to clearly identify information (for example, hazardous materials).

See personal air sampler.

An object that has been decommissioned from a nuclear facility, that is internally contaminated with nuclear substances meeting the requirements applicable to an SCO‑I or SCO‑II as set out in the IAEA Regulations and that cannot be transported in a type of package described in these Regulations due to its dimensions. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

See leak before break.

large-break loss-of-coolant accident; see loss-of-coolant accident.

licence conditions handbook

lifecycle management plan; see aging management program / aging management plan

See low dispersible radioactive material.

Leakage from a flaw in a pressurized component (such as a pipe) during normal operation of a nuclear reactor, detected early enough for the reactor to be shut down and depressurized before the flaw grows large enough to cause a rupture.

With respect to sealed sources (including sealed sources within prescribed equipment) or nuclear substances used as shielding, a method of verifying the integrity of the encapsulation of the sealed source or ensuring that the nuclear substance used for shielding is not readily removable from the surface of that shielding.

A change in behaviour that occurs as a result of the acquisition of knowledge, skills or safety-related attributes.

A work environment where people continually build on their capability to reach their goals. In a learning organization, new and challenging ways of interacting and behaving are encouraged in order to meet future organizational challenges, and everyone has the opportunity to make sense of their work together.

In Canada, legacy sites specifically refer to research and demonstration facilities, locations or sites dating back to the birth of nuclear technologies in Canada for which decommissioning was not planned as part of the design.

A guide that instructors use to ensure that training is specific and goal oriented.

linear energy transfer

See low-enriched uranium.

A licence issued under section 24. (Source: Nuclear Safety and Control Act)

Note: This legal document issued by the Commission or a designated officer allows an activity (defined under section 26) to be carried out. The NSCA authorizes the Commission and, in some cases, designated officers to grant licences for purposes listed in section 26 of the NSCA.

A particular use of nuclear substances as described in the Canadian Nuclear Safety Commission Cost Recovery Fees Regulations .

An activity described in any of paragraphs 26(a) to (f) of the Act that a licence authorizes the licensee to carry on. (Sources: General Nuclear Safety and Control Regulations ; Radiation Protection Regulations )

OR

An activity described in paragraph 26(e) of the Act that a licence authorizes the licensee to carry on in relation to a Class I nuclear facility. (Source: Class I Nuclear Facilities Regulations )

OR

An activity described in paragraph 26(a), (c) or (e) of the Act that a licence authorizes the licensee to carry on in relation to a Class II nuclear facility or Class II prescribed equipment. (Source: Class II Nuclear Facilities and Prescribed Equipment Regulations )

OR

An activity described in any of paragraphs 26(a) to (c) of the Act that a licence authorizes the licensee to carry on in relation to a nuclear substance or a radiation device. (Source: Nuclear Substances and Radiation Devices Regulations )

OR

An activity described in paragraph 26(e) of the Act that a licence authorizes the licensee to carry on in relation to a uranium mine or mill. (Source: Uranium Mines and Mills Regulations )

A limit that is part of the licensing basis and, if exceeded, represents a loss of control of part of the licensee’s program(s) or control measure(s). Exceeding a licensed limit indicates that the licensee is operating outside their licensing basis for normal operation, but does not necessarily imply an unreasonable risk to the environment, to the health and safety of persons or to national security. Exceeding a licensed limit is a non compliance and triggers a requirement for the licensee to take specific action.

Note: The licensed limits may include any limits specified in the licensing basis.

A limit that is part of the licensing basis and, if exceeded, represents a loss of control of part of the licensee’s environmental protection program(s) or control measure(s). Exceeding a licensed release limit indicates that the licensee is operating outside their licensing basis for normal operation, but does not necessarily imply an unreasonable risk to the environment or to the health and safety of persons. Exceeding a licensed release limit is a non compliance and triggers a requirement for the licensee to take specific action.

Note: In the regulations below, a person may be an individual or organization.

A person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Act. (Sources: General Nuclear Safety and Control Regulations ; Radiation Protection Regulations )

OR

A person who is licensed to carry on an activity described in paragraph 26(e) of the Act in relation to a Class I nuclear facility. (Source: Class I Nuclear Facilities Regulations )

OR

A person who is licensed to carry on an activity described in any of paragraphs 26(a), (c) or (e) of the Act in relation to a Class II nuclear facility or Class II prescribed equipment. (Source: Class II Nuclear Facilities and Prescribed Equipment Regulations )

OR

A person who is licensed to carry on an activity described in any of paragraphs 26(a) to (c) of the Act in relation to a nuclear substance or a radiation device. (Source: Nuclear Substances and Radiation Devices Regulations )

OR

Means

1. in this section and sections 2 to 7.2, a person who is licensed to carry on an activity described in any of paragraphs 26(a), (b), (e) or (f) of the Act in relation to Category I, II or III nuclear material or a nuclear power plant;
2. in sections 7.3 to 38, a person who is licensed to carry on an activity described in any of paragraphs 26(a), (b), (e) or (f) of the Act in relation to a high-security site; and
3. in Part 2, a person who is licensed to carry on an activity described in any of paragraphs 26(a), (b) or (e) of the Act in relation to a nuclear facility set out in column 2 of Schedule 2.

(Source: Nuclear Security Regulations )

Note: In paragraph (a) above, “in this section” refers to section 1 of the Nuclear Security Regulations .

OR

A person who is licensed to carry on an activity described in paragraph 26(e) of the Act in relation to a uranium mine or mill. (Source: Uranium Mines and Mills Regulations )

Licensee documents for which the licensee is required to notify the CNSC, in writing, when changes are made. These documents are typically identified in the licence conditions handbook.

Activities for processing and assessing an application related to a licence or certificate or a request for an approval prior to issuing, denying, renewing, amending or replacing the licence, certificate or approval. This includes similar work prior to suspending or revoking a licence or certificate.

A set of requirements and documents for a regulated facility or activity comprising:

• the regulatory requirements set out in the applicable laws and regulations
• the conditions and safety and control measures described in the facility’s or activity’s licence and the documents directly referenced in that licence
• the safety and control measures described in the licence application and the documents needed to support that licence application

See aging management program / aging management plan.

The various stages of a nuclear facility’s lifespan, including site selection, site preparation, construction, operation, decommissioning and abandonment.

A planning process for decommissioning that begins in the design and construction phases of a facility, remains responsive to new information obtained during operations, culminates in a detailed plan for CNSC approval at the end of operations, and remains flexible and adaptive to conditions encountered during the actual decommissioning process.

An assumption, used in a deterministic safety analysis, that, prior to a postulated accident, a nuclear facility was operating with some of the important plant operating parameters being at their safety limits, while some of the models used to describe the event may be conservative. Note: LOE does not necessarily mean an impossible plant operating state. However, depending on the number and nature of the conservative assumptions made in the analysis, the event may become highly improbable, if not physically impossible.

With respect to environmental protection, a radiation protection principle that specifies the value of a quantity used in certain activities or circumstances that must not be exceeded, such as the public dose limit.

large loss-of-coolant accident; see loss-of-coolant accident

long-lived radioactive dust

See low-level waste.

See loss-of-coolant accident.

With respect to nuclear substances and radiation devices, any room, area, enclosure, land or base(s) of operations the licensee occupies where the licensee uses or stores nuclear substances for more than 90 consecutive days per calendar year. The location may be identified by a postal address or global positioning system coordinates.

Any installation or location, other than a facility, where nuclear material is customarily used in amounts of one effective kilogram or less and is subject to full nuclear material accounting and reporting.

For exposure devices, the condition of a sealed source assembly, with either an exposure container or source changer, in the secured and locked position.

See limit of operating envelope.

See location outside facilities.

The use of sealed sources to obtain subsurface geological information.

With respect to disposal of radioactive waste or of mineralized waste rock and tailings, any period of time after which active institutional controls can be expected to cease.

The long‑term management of radioactive nuclear waste by means of storage or disposal, including handling, treatment, conditioning or transport for the purpose of storage or disposal. Also called long‑term waste management.

The operation, beyond the originally intended operating life of a reactor facility, which has been justified by a safety assessment that considers life‑limiting processes and features for structures, systems and components.

A state in which fuel in the core or the spent fuel pool is submerged in water, the associated reactivity is controlled to remain subcritical, and a long-term decay heat removal from the fuel is achieved and maintained.

See long‑term management of nuclear waste.

A type of reactor accident that results from a loss of coolant due to a break in the primary heat transport system.

The number of calendar days, recommended by a physician or other healthcare professional, that an employee is unable to work beyond the day of injury or illness. Lost time ends as of the date that the employee is deemed fit to work either full or restricted work, or up to a maximum of 180 calendar days for any individual case.

An injury or illness resulting in lost days beyond the date of injury as a direct result of an occupational injury or illness incident.

Has the same meaning as in the IAEA Regulations. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

Enriched uranium containing less than 20 percent by weight of isotope uranium‑235, uranium‑233, or combined uranium‑233 and uranium‑235.

Radioactive solid waste that contains material with radionuclide content above established clearance levels and exemption quantities, but that generally has limited amounts of long‑lived activity.

Has the same meaning as in the IAEA Regulations. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

last person out

low‑pressure service water open system

large release frequency

Has the meaning assigned by the definition “low specific activity (LSA) material” in the IAEA Regulations. (Source: Packaging and Transport of Nuclear Substances Regulations, 2015 )

See long‑term operation.

light‑water reactor