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CSA N294-09 (R2019) Decommissioning of facilities containing nuclear substances, Includes Update No. 1 (2014)

standard by CSA Group, 07/01/2009

Full Description

Scope

1.1 This Standard applies to the decommissioning of licensed facilities and other locations where nuclear substances are managed, possessed, or stored.

Notes:
(1) Users are responsible for determining the extent to which this Standard applies to a given facility or location and for consulting the associated regulatory requirements.
(2) Annexes E, F, and G contain recommended approaches for the decommissioning of mine waste rock and mill tailings, complex sites, and small facilities other than Class I or II, respectively.

1.2 This Standard does not apply to the decommissioning of facilities or equipment involving only
(a) naturally occurring radioactive material (NORM);
(b) technologically enhanced, naturally occurring radioactive material (TENORM); or
(c) radiation-emitting devices, including those consumer and medical devices regulated under the Radiation Emitting Devices Act and similar industrial radiation-emitting devices regulated by the provinces.

Note: This Standard provides guidance that might be useful for facilities covering the materials and equipment specified in this Clause.

1.3 In CSA Standards, "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; "may" is used to express an option or that which is permissible within the limits of the standard; and "can" is used to express possibility or capability. 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 N294:09, Decommissioning of facilities containing nuclear substances

CSA N294:09

(reaffirmed 2019)


Decommissioning of facilities containing nuclear substances


REVISED AUGUST 2014

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    Revision History

    CSA N294-09, Decommissioning of facilities containing nuclear substances


    Update No. 1 — August 2014

    Revision symbol (in margin)

    Preface

    Clauses 0, 1, 2, 5, 7.8.2, E.2.3.1, and I.3.2

    Annexes H and K Figure 1


    Standards Update Service

    CSA N294:09

    July 2009


    Title: Decommissioning of facilities containing nuclear substances

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CSA N294:09

Decommissioning of facilities containing nuclear substances





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


Published in July 2009 by CSA Group

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ISBN 978-1-55491-209-4


© 2009 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 the Decommissioning of Nuclear Facilities 4


Preface 6


0 Introduction 7

    1. General 7

    2. Background 7

    3. Application 7

    4. Interface with other CSA Group Standards 7


  1. Scope 8


  2. Reference publications 8


  3. Definitions 12


  4. Responsibilities 15

    1. General 15

    2. Rehabilitating part of a facility 16


  5. Decommissioning phases 16


  6. Phase 1 — Planning for decommissioning 17

    1. Decommissioning strategy 17

      1. General 17

      2. Decommissioning strategy options 18

      3. Planning considerations 18

    2. Planning for decommissioning throughout the facility life cycle 18

      1. General 18

      2. Design and construction 19

      3. Commissioning 19

      4. Operation and maintenance 19

      5. Final shutdown 19

    3. Initial decommissioning plan 19

      1. General 19

      2. Ongoing review and revision 20


  7. Phase 2 — Preparation for decommissioning 20

    1. General 20

    2. Notification 20

    3. Permanent shutdown 20

    4. Safe shutdown state 21

      1. General 21

      2. Removal of materials and preparation of systems 21

      3. Surveillance and maintenance 21

    5. Assessment of the state of the facility after shutdown 21

      1. General 21

      2. Investigation and assessment 21

      3. Sources of information 21

    6. Safety assessment of the decommissioning 21

    7. Changes to the decommissioning strategy 22

    8. Final decommissioning plan 22

      1. General 22

      2. Content 22

      3. Waste management plan 23

      4. Human resources plan 24

    9. Requirements for licensed nuclear facilities 24

    10. Public communication 24

      1. General 24

      2. Target audiences 25

      3. Requirements for licensed nuclear facilities 25


  8. Phase 3 — Execution of decommissioning 25

    1. Commencement of decommissioning activities 25

    2. Methods and techniques 26

      1. General 26

      2. Decontamination 26

      3. Dismantling and demolition 27

      4. Surveys 27

    3. Support programs 27

    4. Interim end-state report 28

    5. Periods of storage with surveillance 28


  9. Phase 4 — Completion of decommissioning 28

    1. General 28

    2. Final end state 28

      1. General 28

      2. Final surveys 29

      3. Final end-state report 29

    3. Release of licensed facilities from regulatory control 29


  10. Institutional controls following decommissioning 29

    1. General 29

    2. Type and duration 29

    3. Protective measures 30


  11. Decommissioning records 30

    1. Contents 30

    2. Retention period 30


Annex A (informative) — Preliminary decommissioning plan 32

Annex B (informative) — Financial aspects of decommissioning nuclear facilities 35

Annex C (informative) — Surveys 40

Annex D (informative) — Final end-state report 46

Annex E (informative) — Recommended approaches for the decommissioning of mine waste rock and mill tailings 49

Annex F (informative) — Decommissioning of complex sites 52

Annex G (informative) — Decommissioning of small facilities (other than Class I or Class II) 57

Annex H (informative) — Defining end state objectives for decommissioning 61

Annex I (informative) — Planning for decommissioning throughout the life cycle of the facility 65

Annex J (informative) — Bibliography 68

Annex K (informative) — Decommissioning of high energy reactor facilities 73

Technical Committee on the Decommissioning of Nuclear Facilities


M. Stephens Atomic Energy of Canada Limited, Chalk River, Ontario

Chair



D. Howard Canadian Nuclear Safety Commission, Ottawa, Ontario

Vice-Chair



J. Kennard Nuclear Waste Management Organization, Toronto, Ontario

Vice-Chair



F. Allen Department of National Defence, Ottawa, Ontario


D. Allinson Atomic Energy of Canada Limited, Port Hope, Ontario

Associate



M. Attas Atomic Energy of Canada Limited, Pinawa, Manitoba

Associate


A. Baweja Health Canada, Ottawa, Ontario


D. Burgess Cameco Corporation, Port Hope, Ontario


L. DeLong NB Power Nuclear Corporation, Lepreau, New Brunswick


R. Ferch Ottawa, Ontario


D. Gibson Ontario Power Generation, Toronto, Ontario


M. Grey Candesco Corporation, Toronto, Ontario


G. Griffiths TLG Services Inc.,

Bridgewater, Connecticut, USA

R. Ilson Dalhousie University, Halifax, Nova Scotia


N. Jayawardene AMEC Nuclear Safety Solutions,

Toronto, Ontario


S. Kenny Atomic Energy of Canada Limited, Chalk River, Ontario

Associate


A. Krukowski SNC-Lavalin Nuclear Inc., Oakville, Ontario


D. Metcalfe Natural Resources Canada, Ottawa, Ontario


S. Oue Canadian Nuclear Safety Commission, Ottawa, Ontario

Associate


A. Rosaasen AREVA Resources Canada Inc., Saskatoon, Saskatchewan


S. Sonoc University of Toronto, Toronto, Ontario


C. Vollrath Burlington, Ontario


S. Wang Canadian Standards Association, Mississauga, Ontario

Project Manager


A. Kwong Canadian Standards Association, Mississauga, Ontario

Project Manager


In addition to the Technical Committee, the following people made valuable contributions to the development of this Standard:

    1. Helbrecht, CNSC Consultant, East St. Paul, Manitoba

      AECL Decommissioning Staff at Chalk River Laboratories, Ontario AECL Decommissioning Staff at Whiteshell Laboratories, Manitoba

      Cameco Technical Staff in Saskatoon, Saskatchewan and Port Hope, Ontario

      The members of the Technical Committee who developed the 1992 draft Standard for nuclear decommissioning

      ① Preface

      This is the first edition of CSA N294, Decommissioning of facilities containing nuclear substances.

      This Standard was developed in response to a need for direction on decommissioning consistent with Canadian and international recommendations. It incorporates current best practices and existing regulatory requirements. This Standard also draws on the decommissioning experience of the Canadian nuclear industry.


      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 specific 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.


      Users of this Standard are reminded that additional and site-specific requirements might be specified by federal, provincial, or municipal authorities. This Standard should not be considered as a replacement for the requirements contained in the Nuclear Safety and Control Act and its Regulations or in other legislation, standards, or guides.


      This Standard was prepared by the Technical Committee on the Decommissioning of Nuclear Facilities, under the jurisdiction of 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 N294:09

Decommissioning of facilities containing nuclear substances

① 0 Introduction

Note: The information in Clause 0 is informative.


    1. General

      This Standard is one of the CSA N-Series of Standards, a set of Standards which provide an interlinked set of requirements for the management of nuclear facilities. This Standard provides direction on defining, planning and executing decommissioning work, and supports the requirements identified in CSA N286, Management system requirements for nuclear facilities.


    2. Background

      This Standard was developed to consolidate and incorporate into one document, decommissioning principles, Canadian and international decommissioning experience, international guidance, and regulatory expectations that could be applied to the decommissioning of all facilities and sites where nuclear substances were used or stored.

      The Standard is consistent with and supplements current Canadian policy and regulatory guidance as follows:

      • CNSC Regulatory Policy P-290, Managing Radioactive Waste (July 2004);

      • CNSC Regulatory Guide G-219, Decommissioning Planning for Licensed Activities (June 2000); and

      • CNSC Regulatory Guide G-206, Financial Guarantees for the Decommissioning of Licensed Activities (June 2000).


    3. Application

      The application of this Standard is intended for all nuclear decommissioning activities in Canada and is mandatory when referenced as a requirement in a CNSC licence or via another regulatory requirement. The Standard is intended to be appropriate for use in decommissioning facilities and sites under CNSC licences, military facilities regulated by the Director Nuclear Safety, and non-licensed facilities and sites containing nuclear substances.


      The main body of this Standard provides the requirements for the management of decommissioning; the Annexes have been developed to provide information related to specific aspects of decommissioning.


    4. Interface with other CSA Group Standards

This Standard has been developed to capture nuclear decommissioning requirements, but recognizes that the process of decommissioning is complex and interface with other CSA N-Series Standards will be required.


It is recommended that the user of this Standard consider reviewing the following CSA N-Series Standards to determine if the requirements contained within these Standards affect and influence their decommissioning:

  • N285 series on pressure retaining components and systems;