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CSA N292.8:21 Characterization of radioactive waste and irradiated fuel
standard by CSA Group, 08/01/2021
Preface
This is the first edition of CSA N292.8, Characterization of radioactive waste and irradiated fuel. This Standard works in concert with CSA N292.0, General principles for the management of radioactive waste and irradiated fuel, which specifies common requirements for the management of radioactive waste and irradiated fuel.
This Standard reflects the operating experience of the Canadian nuclear industry, best practices, and international experience and guidance. The CSA N-series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system.
This Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements. Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety and Control Act and its supporting Regulations.
Scope
1.1 General This Standard pertains to the characterization of radioactive waste and irradiated fuel. This Standard a) specifies the overall requirements for establishing and implementing a waste characterization strategy, program, and plan; b) specifies methodologies for the sampling and characterization of radioactive waste and irradiated fuel; c) provides guidance for the timing of waste characterization planning and execution; d) provides guidance on waste characterization during nuclear decommissioning and site remediation; and e) provides guidance for reporting of waste characterization results. Note: In this Standard, both the terms waste and radioactive waste are used to refer to radioactive waste and irradiated fuel.
1.2 Steps in the management of waste This Standard applies to waste characterization during all steps in the management of radioactive waste and irradiated fuel, including a) generation; b) handling; c) processing; d) transport; e) storage; and f) disposal. Note: The objectives of waste characterization could be different for the various steps in the management of waste, and so the waste characterization data required could also vary to support these objectives.
1.3 Waste container This Standard provides guidance on a) the characterization of stored waste (e.g., contained within waste containers), including the interactions between the waste and waste containers; and b) the characterization of waste not contained in a waste container, such as waste from site remediation and in-situ decommissioning.
1.4 Exclusions This Standard excludes characterization of nonradioactive waste, naturally occurring radioactive material (NORM) and technologically enhanced, naturally occurring radioactive material (TENORM), and uranium mine and mill tailings. Notes: 1) Nonradioactive waste refers to that which is cleared or exempt from nuclear regulatory control. See CSA N292.5 for guidance on the requirements for exemption and clearance. 2) Users of this Standard within Canada are reminded that management of hazardous wastes is a matter of provincial jurisdiction unless the waste is transported across provincial or national borders, in which case federal jurisdiction would apply. For mixed waste, requirements under the federal AHJ also apply.
This Standard is not intended to supersede requirements of the AHJ pertaining to the characterization of conventional hazardous properties of radioactive waste and, in certain cases, it might not satisfy these requirements. For those jurisdictions that follow the system of classification developed by the U.S. EPA, guidance on characterization of hazardous waste is available in references including U.S. EPA SW-846, U.S. EPA 530-R-12-001, and provincial requirements. 3) For guidance on the characterization of NORM and TENORM, see Lehto and Hou (2011) and LAnnunziata (2020). 1.5 CSA N292.0 This Standard is used in conjunction with CSA N292.0.
1.6 Users This Standard applies to waste organizations or facilities that generate, handle, process, transport, store, and dispose of radioactive waste and irradiated fuel, including nuclear power reactors, research institutes, medical facilities, manufacturing facilities, laboratories, and industrial facilities. Notes: 1) Waste organizations can refer to waste generators, waste brokers, waste receivers, waste processors, and waste management facility operators. 2) This Standard may be applied by other facilities using a graded approach. 3) See Clause 4.1.3 of CSA N286 regarding application of the graded approach.
1.7 Terminology In this Standard, shall is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the Standard; should is used to express a recommendation or that which is advised, but not required; and may is used to express an option or that which is permissible within the limits of the Standard. Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material. Notes to tables and figures are considered part of the table or figure and may be written as requirements. Annexes are designated normative (mandatory) or informative (non-mandatory) to define their application.
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CSA N292.8:21
August 2021
Title: Characterization of radioactive waste and irradiated fuel
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CSA N292.8:21
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Published in August 2021 by CSA Group
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Technical Committee on Radioactive Waste Management 3
Subcommittee on Characterization of Radioactive Waste and Irradiated Fuel 5
Preface 7
Scope 8
General 8
Steps in the management of waste 8
Waste container 8
Exclusions 8
1.5 CSA N292.0 9
Users 9
Terminology 9
Reference publications 9
Definitions and abbreviations 13
Definitions 13
Abbreviations 14
Application of other CSA Standards 14
Roles and responsibilities 14
Waste generator 14
Responsibility 14
Waste characterization planning 15
Waste characterization planning for waste with no receiver 15
Waste receiver 15
Responsibility 15
Verification 15
Waste characterization planning 15
Receipt of waste 15
Waste processor 15
Re-characterization of waste 15
Production of secondary waste 15
Waste characterization planning 16
General 16
Waste characterization strategy 16
General 16
Objectives 17
Use of waste characterization data 17
Waste characterization program 17
General 17
Objectives 17
Graded approach 18
Safety and control areas 18
Stored waste 18
Legacy waste 18
Waste characterization plan 19
Stages of waste characterization 19
Components of a waste characterization plan 20
Objectives 20
Determination of waste characterization information 21
Data collection and quality control 22
Assessment of objectives 23
Timing of waste characterization efforts 24
General 24
Waste characterization planning 24
Extent of waste characterization 24
Resource efficiency 24
Consideration of objectives 25
Consideration of potential future changes 25
Waste characterization data to demonstrate compliance 25
Waste characterization data to support management of radioactive waste 25
Waste characterization data for disposition 25
Waste characterization data for site remediation 25
Waste characterization implementation 26
Waste characterization methods and techniques 26
General 26
Characterization of physical properties 26
Characterization of chemical and biological properties 26
Characterization of radiological properties 26
Non-destructive characterization methods 26
Destructive characterization methods 27
Representative sampling 28
Analysis and interpretation of waste characterization data 29
Sample analysis 29
Interpretation of waste characterization data 30
Reporting of results 31
Documents and records 31
General 31
Quality management program 32
Retention of records 32
Retention of waste characterization data 32
Annex A (informative) — Application of DQO and DQA processes 33 Annex B (informative) — Methods of waste characterization 42 Annex C (informative) — Example laboratory QMS requirements 57
Annex D (informative) — Example applications of waste characterization 58
K. Gillin Vysus Group, Sundbyberg, Sweden
Category: Service Industry
Chair
Suryanarayan Kinectrics Inc.,
Toronto, Ontario, Canada
Category: Service Industry
Vice-Chair
Abraham SNC-Lavalin Nuclear Inc., Mississauga, Ontario, Canada
Non-voting
P. Burton Canadian Nuclear Safety Commission (CNSC), Ottawa, Ontario, Canada
Category: Government and/or Regulatory Authority
C. Campbell New Brunswick Power (NB Power), Lepreau, New Brunswick, Canada Category: Owner/Operator/Producer
M. W. Chapman Canadian Nuclear Laboratories Limited (CNL),
Chalk River, Ontario, Canada
Category: Owner/Operator/Producer
P. A. D’Aubin Nordion Inc.,
Ottawa, Ontario, Canada
Category: Service Industry
N. C. Garisto ARCADIS Canada Inc., Richmond Hill, Ontario, Canada
Category: Supplier/Fabricator/Contractor
R. Harrison Bruce Power,
Tiverton, Ontario, Canada
Category: Owner/Operator/Producer
B. M. Ikeda Ontario Tech University, Oshawa, Ontario, Canada Category: General Interest
J. Mecke Natural Resources Canada (NRCan), Ottawa, Ontario, Canada
Non-voting
A. Murchison Nuclear Waste Management Organization (NWMO), Toronto, Ontario, Canada
Non-voting
N. Persaud Kinectrics Inc.,
Toronto, Ontario, Canada
Non-voting
R. Prokopowicz Kinectrics Inc.,
Toronto, Ontario, Canada
Non-voting
F. Rodrigues Ontario Power Generation (OPG), Pickering, Ontario, Canada
Category: Owner/Operator/Producer
T. P. Smith Cameco Corporation Fuel Services Division, Port Hope, Ontario, Canada
Category: Supplier/Fabricator/Contractor
M. E. Stephens Retired professional,
Deep River, Ontario, Canada
Category: General Interest
J. D. Swann Department of National Defence, Ottawa, Ontario, Canada
Non-voting
F. Tourneur University Health Network, Toronto, Ontario, Canada Category: General Interest
P. W. Yuen Natural Resources Canada (NRCan), Ottawa, Ontario, Canada
Category: Government and/or Regulatory Authority
X. Zhang Nuclear Waste Management Organization (NWMO), Toronto, Ontario, Canada
Category: Supplier/Fabricator/Contractor
D. Mendolia CSA Group,
Toronto, Ontario, Canada
Project Manager
K. Liberda Nuclear Waste Management Organization (NWMO), Toronto, Ontario, Canada
Chair
R. Peters Cameco Corporation,
Port Hope, Ontario, Canada
Vice-Chair
P. Andrade Ontario Power Generation (OPG), Pickering, Ontario, Canada
C. Bellman Calian Ltd.,
Ottawa, Ontario, Canada
J. Brewer New Brunswick Power (NB Power), Lepreau, New Brunswick, Canada
C. Campbell New Brunswick Power (NB Power), Lepreau, New Brunswick, Canada
N. Chan Canadian Nuclear Laboratories Limited (CNL), Chalk River, Ontario, Canada
P. A. D’Aubin Nordion Inc.,
Ottawa, Ontario, Canada
M. Dinesen Ontario Power Generation (OPG), Pickering, Ontario, Canada
R. Harrison Bruce Power,
Tiverton, Ontario, Canada
M. Herod Canadian Nuclear Safety Commission (CNSC), Ottawa, Ontario, Canada
B. M. Ikeda Ontario Tech University, Oshawa, Ontario, Canada
R. Prokopowicz Kinectrics Inc.,
Toronto, Ontario, Canada
F. Rodrigues Ontario Power Generation (OPG), Pickering, Ontario, Canada
S. Suryanarayan Kinectrics Inc.,
Toronto, Ontario, Canada
S. Thompson Canadian Nuclear Safety Commission (CNSC), Ottawa, Ontario, Canada
P. W. Yuen Natural Resources Canada (NRCan), Ottawa, Ontario, Canada
Y. Zhuang Candu Energy Inc., Mississauga, Ontario, Canada
D. Mendolia CSA Group,
Toronto, Ontario, Canada
Project Manager
This is the first edition of CSA N292.8, Characterization of radioactive waste and irradiated fuel.
This Standard works in concert with CSA N292.0, General principles for the management of radioactive waste and irradiated fuel, which specifies common requirements for the management of radioactive waste and irradiated fuel.
This Standard reflects the operating experience of the Canadian nuclear industry, best practices, and international experience and guidance.
The CSA N-series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system. This Standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements.
Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety and Control Act and its supporting Regulations.
This Standard was prepared by the Subcommittee on Characterization of Radioactive Waste and Irradiated Fuel, under the jurisdiction of the Technical Committee on Radioactive Waste Management and the Strategic Steering Committee on Nuclear Standards, and has been formally approved by the Technical Committee.
Notes:
Use of the singular does not exclude the plural (and vice versa) when the sense allows.
Although the intended primary application of this Standard is stated in its Scope, it is important to note that it remains the responsibility of the users of the Standard to judge its suitability for their particular purpose.
This Standard was developed by consensus, which is defined by CSA Policy governing standardization — Code of good practice for standardization as “substantial agreement. Consensus implies much more than a simple majority, but not necessarily unanimity”. It is consistent with this definition that a member may be included in the Technical Committee list and yet not be in full agreement with all clauses of this Standard.
To submit a request for interpretation of this Standard, please send the following information to inquiries@csagroup.org and include “Request for interpretation” in the subject line:
define the problem, making reference to the specific clause, and, where appropriate, include an illustrative sketch;
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CSA N292.8:21
Scope
General
This Standard pertains to the characterization of radioactive waste and irradiated fuel. This Standard
specifies the overall requirements for establishing and implementing a waste characterization strategy, program, and plan;
specifies methodologies for the sampling and characterization of radioactive waste and irradiated fuel;
provides guidance for the timing of waste characterization planning and execution;
provides guidance on waste characterization during nuclear decommissioning and site remediation; and
provides guidance for reporting of waste characterization results.
Note: In this Standard, both the terms “waste” and “radioactive waste” are used to refer to “radioactive waste and irradiated fuel”.
Steps in the management of waste
This Standard applies to waste characterization during all steps in the management of radioactive waste and irradiated fuel, including
generation;
handling;
processing;
transport;
storage; and
disposal.
Note: The objectives of waste characterization could be different for the various steps in the management of waste, and so the waste characterization data required could also vary to support these objectives.
Waste container
This Standard provides guidance on
the characterization of stored waste (e.g., contained within waste containers), including the interactions between the waste and waste containers; and
the characterization of waste not contained in a waste container, such as waste from site remediation and in-situ decommissioning.
Exclusions
This Standard excludes characterization of nonradioactive waste, naturally occurring radioactive material (NORM) and technologically enhanced, naturally occurring radioactive material (TENORM), and uranium mine and mill tailings.
Notes:
1) Nonradioactive waste refers to that which is cleared or exempt from nuclear regulatory control. See CSA N292.5 for guidance on the requirements for exemption and clearance.