CSA N292.0:19

General principles for the management of radioactive waste and irradiated fuel

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CSA N292.0:19

March 2019

Title: General principles for the management of radioactive waste and irradiated fuel

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CSA N292.0:19

General principles for the management of radioactive waste and irradiated fuel

®A trademark of the Canadian Standards Association, operating as “CSA Group”

Published in March 2019 by CSA Group

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ISBN 978-1-4883-1764-4

© 2019 Canadian Standards Association

All rights reserved. No part of this publication may be reproduced in any form whatsoever without the prior permission of the publisher.

Contents

Technical Committee on Radioactive Waste Management 5

Subcommittee on Management of Low- and Intermediate-Level Radioactive Waste 7

Preface 8

0 Introduction 10

1. Overview 10

2. Users 11

1. Scope 12

   
   

2. Reference publications 12

   
   

3. Definitions and abbreviations 16

   1. Definitions 16

   2. Abbreviations 23

      
      

4. General requirements 23

   1. General 23

      1. Issues and responsibilities 25

      2. Step interdependence 25

      3. Safety measures 25

      4. ALARA principle 25

      5. Safety approach 25

      6. Non-radiological hazards 25

   2. Responsibilities 26

      1. Waste organizations 26

      2. Waste generator 26

      3. Waste receiver 26

      4. Operator of a waste management facility 26

   3. Human factors 27

   4. Organizational structure 27

   5. Radioactive waste management program 27

      1. General 27

      2. Scope 27

      3. Optimization for disposal 28

      4. Handling 28

      5. Programs, procedures, and policies 28

      6. Minimization of waste 28

      7. Integration and support 28

      8. Control of wastes 28

      9. Safety concerns 28

      10. Associated programs 29

      11. Procedures 29

   6. Quality assurance 29

   7. Records management 30

   8. Minimizing waste generation 31

      1. General 31

      2. Generation 32

      3. Waste classification 32

      4. Waste characterization 32

      5. Waste segregation 33

      6. Operating practices for minimization and segregation 34

   9. Waste containment 34

      1. Containment system 34

      2. Waste packages 35

   10. Safety 37

       1. General 37

       2. Nuclear safety requirements 38

       3. Nuclear criticality safety analysis 38

       4. Radiological safety 39

       5. Industrial safety 40

       6. Safety assessment 40

   11. Waste acceptance criteria (WAC) 42

   12. Physical security and safeguards 43

       1. Security 43

       2. Safeguards 44

   13. Training 44

   14. Environmental management system (EMS) 44

   15. Emergency preparedness 45

       1. Planning for emergency situations 45

       2. Emergency response plan 45

       3. Emergency response plan verification 45

   16. Aging management program 45

   17. Decommissioning planning 46

       
       

5. Specific requirements 46

   1. Assessment of hazards 46

   2. Free liquids 46

   3. Chemical toxicity 46

   4. Radiation dose rates and radiation stability 47

   5. Thermal stability 47

   6. Gas generation potential 47

   7. Reactivity with the environment 48

      
      

6. Processing 48

   
   

7. Waste management facility 48

   1. General 48

   2. Facility site 49

      1. Site selection for new facilities 49

      2. Site characterization 49

   3. Design considerations 49

      1. General 49

      2. Design selections 50

      3. Removal of water 50

   4. Facility management 50

      1. Non-routine activities 50

      2. Flood management 50

      3. Periodic monitoring 50

      4. Technological obsolescence 51

      5. Knowledge retention 51

      6. External collaboration 52

   5. Unauthorized or inadvertent access 52

   6. Necessary services and equipment 52

   7. Barrier system and containment 52

   8. Minimization of events or accidents 53

   9. Radiological control zones 53

   10. Radiation monitors 53

   11. Mechanical equipment and instrumentation systems design 53

   12. Inspection and maintenance 53

   13. Handling operations 54

   14. Decontamination of waste-handling equipment 54

   15. Storage system or processing system design 54

   16. Fire suppression 54

   17. Emergency response personnel access 54

   18. Evacuation routes 55

   19. Emergency power supply and distribution system 55

   20. Communication equipment 55

   21. Loads and conditions 55

   22. Potentially radioactive drainage 55

   23. Records 55

       1. General requirements 55

       2. Specific requirements 55

   24. Operational practices 56

   25. Procedures 56

   26. Operational limits 56

   27. Facility storage plan 56

       
       

8. Containment system design 56

   
   

9. Waste package design 57

   1. General 57

      1. Package function 57

         
         

         9.1.2	Multi-function package	57
         9.1.3	Standardized containers	57
         9.1.4	Package properties 57
         9.2	Storage package 58
         9.3	Disposal package 58
         9.4	Package qualification tests	59

         
         

10. Package labelling and records 59

    1. Package labelling 59

    2. Waste package and characterization records 60

11. Waste handling 61

    1. General 61

    2. Handling precautions 61

    3. Facility equipment 61

       
       

12. Storage 61

Annex A (informative) — Radioactive waste classification, exemption, clearance, and storage for decay 63

Annex B (informative) — Methods of waste characterization 67

Annex C (informative) — Bibliography 74

Preface

This is the second edition of CSA N292.0, General principles for the management of radioactive waste and irradiated fuel. It supersedes the previous edition, published in 2014.

Changes to this edition include the following:

1. The scope of this Standard has been expanded to include the management of other radioactive materials.

2. Guidance has been provided on the re-characterization of radioactive materials, optimization for disposal, and safety assessments.

3. Further guidance and requirements for containment systems, waste packages, and storage sites have been provided.

4. Further guidance for waste management facilities has been provided for design, site selection, site characterization, non-routine activities, flood management, periodic monitoring, technological obsolescence, knowledge retention, and external collaboration.

5. Terminology and requirements have been updated for harmonization with the CSA N292 series of Standards.

   
   

   This Standard is part of a series of Standards on radioactive waste management. It specifies common requirements for the management of radioactive waste and irradiated fuel, and is used in concert with all CSA Standards that apply to the management of radioactive waste and irradiated fuel (e.g.,

   CSA N292.1, CSA N292.2, CSA N292.3, CSA N292.5, CSA N292.6, and CSA N294).

   
   

   Users of this Standard are reminded that the site selection, design, manufacture, construction, installation, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the Nuclear Safety and Control Act and its Regulations. The Canadian Nuclear Safety Commission might impose additional requirements to those specified in this Standard.

   
   

   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 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 may provide more specific direction for those requirements.

   
   

   This Standard was prepared by the Subcommittee on Management of Low- and Intermediate-Level Radioactive Waste, 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:

   1. Use of the singular does not exclude the plural (and vice versa) when the sense allows.

   2. 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.

   3. 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.

   4. 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:

      1. define the problem, making reference to the specific clause, and, where appropriate, include an illustrative sketch;

      2. provide an explanation of circumstances surrounding the actual field condition; and

      3. where possible, phrase the request in such a way that a specific “yes” or “no” answer will address the issue.

         Committee interpretations are processed in accordance with the CSA Directives and guidelines governing standardization and are available on the Current Standards Activities page at standardsactivities.csa.ca.

   5. This Standard is subject to review within five years from the date of publication. Suggestions for its improvement will be referred to the appropriate committee. To submit a proposal for change, please send the following information to inquiries@csagroup.org and include “Proposal for change” in the subject line:

      1. Standard designation (number);

      2. relevant clause, table, and/or figure number;

      3. wording of the proposed change; and

      4. rationale for the change.

CSA N292.0:19

General principles for the management of radioactive waste and irradiated fuel

0 Introduction

1. Overview

   Radioactive waste and irradiated fuel (also referred to as “radioactive material” in this Standard) are generated in the nuclear fuel cycle and from the use of radioisotopes in medicine, industry, institutions, and research. Approaches for managing radioactive waste and irradiated fuel vary depending on characteristics of the material involved. Consideration of all steps during the management of radioactive material in the early phases of waste management provides additional possible exit paths. Management activities include, but are not limited to, handling, packaging, transportation, processing and storage, care-taking/monitoring, and long-term management of radioactive waste.

   After radioactive waste and irradiated fuel are generated and packaged, the radioactive material can be moved between various safe, contained, and isolated states (i.e., conditions). It can be

   1. transferred or transported directly to storage or disposal states;

   2. in transition between storage and disposal states; or

   3. released from radioactive waste management through an exit path.

      Interim steps for the management of radioactive material are selected to optimize options for final radioactive waste disposal later. If interim steps, such as preparation and storage, are not carefully planned, they could impact future exit opportunities. Optimization of safety, dose, cost, etc., should also be considered when selecting strategies to avoid or minimize repeated handling or reworking of waste at future steps.

      Note: For the purposes of this Standard, Figure 1 illustrates the states, transitions, and potential exit paths involved in managing radioactive waste and irradiated fuel.

      Figure 1

      Diagram of states, transitions, and exit paths

      (See Clauses 0.1 and 3.1.)

      
      

      TRANSITION

      Interim

      or short- term storage

      (<50 years)

      TRANSITION

      TRANSITION

      Long-

      term storage (>50 years)

      Disposal

      Legend:

      • State

      • Transition

      • Exit paths

      Possible exit paths

      • Removal of non-radioactive

        • conventional waste

        • hazardous waste

      • Removal for reuse/recycle

      • Reuse of contaminated equipment on a licensed site

      • Exemption

      • Clearance

      
      

      Notes:

      1. Transition might or might not involve physical movement of the radioactive material, and as such, two or more of the states might occur at the same site.

      2. Some sites might consider irradiated fuel a radioactive waste (specifically high-level radioactive waste).

   
   

2. Users

This Standard is intended to be used by individuals and organizations that are associated with

1. the generation, handling, characterization, processing, transportation, or other management of radioactive waste and irradiated fuel; and

2. the siting, design, construction, commissioning, operation, and decommissioning of storage or disposal facilities for radioactive waste and irradiated fuel.

Note: Radioactive waste and irradiated fuel are collectively referred to in this Standard as “radioactive materials”.

1. Scope

   
   

   1.1

   This Standard specifies common requirements for the management of radioactive waste and irradiated fuel from generation to storage or disposal.

   Note: This includes management of mixed waste, which can have other management requirements.

   
   

   1.2

   This Standard is used in concert with all CSA standards that apply to the management of radioactive waste and irradiated fuel.

   Note: For example, CSA N292.1, CSA N292.2, CSA N292.3, CSA N292.5, CSA N292.6, and CSA N294.

   
   

   1.3

   This Standard applies to waste organizations or facilities of all sizes that generate, possess, manage, process, transport, and dispose radioactive waste and irradiated fuel, including nuclear power reactors, research institutes, medical facilities, manufacturing facilities, laboratories, and industrial facilities.

   Note: Waste organizations can refer to waste generators, waste brokers, waste receivers, waste processors, and waste management facility operators.

   
   

   1.4

   The following types of radioactive waste are not addressed in this Standard:

   1. naturally occurring radioactive material (NORM) and technologically enhanced, naturally occurring radioactive material (TENORM); and

   2. uranium mine and mill tailings.

   Note: While this Standard is not applicable to the management of mine and mill tailings, the principles in this Standard can be useful for their management.

   
   

   1.5

   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.

   
   

2. Reference publications

This Standard refers to the following publications, and where such reference is made, it shall be to the editions listed below, including all amendments published thereto.

Note: For additional references that might be useful to the user, see Annex C.