IAEA Safety Standards Regulations for the Safe Transport of

IAEA Safety Standards

Regulations for the

Safe Transport of

Radioactive Material

2012 Edition

for protecting people and the environment

No. SSR-6

Specific Safety Requirements

This publication has been superseded by SSR-6 (Rev. 1).

IAEA SAFETY STANDARDS AND RELATED PUBLICATIONS

IAEA SAFETY STANDARDS

Under the terms of Article III of its Statute, the IAEA is authorized to establish or adopt

standards of safety for protection of health and minimization of danger to life and property, and

to provide for the application of these standards.

The publications by means of which the IAEA establishes standards are issued in the

IAEA Safety Standards Series. This series covers nuclear safety, radiation safety, transport

safety and waste safety. The publication categories in the series are Safety Fundamentals,

Safety Requirements and Safety Guides.

Information on the IAEA’s safety standards programme is available at the IAEA Internet

site

http://www-ns.iaea.org/standards/

The site provides the texts in English of published and draft safety standards. The texts

of safety standards issued in Arabic, Chinese, French, Russian and Spanish, the IAEA Safety

Glossary and a status report for safety standards under development are also available. For

further information, please contact the IAEA at PO Box 100, 1400 Vienna, Austria.

All users of IAEA safety standards are invited to inform the IAEA of experience in their

use (e.g. as a basis for national regulations, for safety reviews and for training courses) for the

purpose of ensuring that they continue to meet users’ needs. Information may be provided via

the IAEA Internet site or by post, as above, or by email to Ofﬁ [email protected].

RELATED PUBLICATIONS

The IAEA provides for the application of the standards and, under the terms of Articles III

and VIII.C of its Statute, makes available and fosters the exchange of information relating

to peaceful nuclear activities and serves as an intermediary among its Member States for this

purpose.

Reports on safety and protection in nuclear activities are issued as Safety Reports,

which provide practical examples and detailed methods that can be used in support of the

safety standards.

Other safety related IAEA publications are issued as Radiological Assessment

Reports, the International Nuclear Safety Group’s INSAG Reports, Technical Reports and

TECDOCs. The IAEA also issues reports on radiological accidents, training manuals and

practical manuals, and other special safety related publications.

Security related publications are issued in the IAEA Nuclear Security Series.

The IAEA Nuclear Energy Series comprises informational publications to encourage

and assist research on, and the development and practical application of, nuclear energy for

peaceful purposes. It includes reports and guides on the status of and advances in technology,

and on experience, good practices and practical examples in the areas of nuclear power, the

nuclear fuel cycle, radioactive waste management and decommissioning.

This publication has been superseded by SSR-6 (Rev. 1).

REGULATIONS FOR THE

SAFE TRANSPORT OF

RADIOACTIVE MATERIAL

2012 Edition

This publication has been superseded by SSR-6 (Rev. 1).

The following States are Members of the International Atomic Energy Agency:

The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the

IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The

Headquarters of the Agency are situated in Vienna. Its principal objective is “to accelerate and enlarge the

contribution of atomic energy to peace, health and prosperity throughout the world’’.

AFGHANISTAN

ALBANIA

ALGERIA

ANGOLA

ARGENTINA

ARMENIA

AUSTRALIA

AUSTRIA

AZERBAIJAN

BAHRAIN

BANGLADESH

BELARUS

BELGIUM

BELIZE

BENIN

BOLIVIA

BOSNIA AND HERZEGOVINA

BOTSWANA

BRAZIL

BULGARIA

BURKINA FASO

BURUNDI

CAMBODIA

CAMEROON

CANADA

CENTRAL AFRICAN 

REPUBLIC

CHAD

CHILE

CHINA

COLOMBIA

CONGO

COSTA RICA

CÔTE D’IVOIRE

CROATIA

CUBA

CYPRUS

CZECH REPUBLIC

DEMOCRATIC REPUBLIC 

OF THE CONGO

DENMARK

DOMINICA

DOMINICAN REPUBLIC

ECUADOR

EGYPT

EL SALVADOR

ERITREA

ESTONIA

ETHIOPIA

FINLAND

FRANCE

GABON

GEORGIA

GERMANY

GHANA

GREECE

GUATEMALA

HAITI

HOLY SEE

HONDURAS

HUNGARY

ICELAND

INDIA

INDONESIA

IRAN, ISLAMIC REPUBLIC OF

IRAQ

IRELAND

ISRAEL

ITALY

JAMAICA

JAPAN

JORDAN

KAZAKHSTAN

KENYA

KOREA, REPUBLIC OF

KUWAIT

KYRGYZSTAN

LAO PEOPLE’S DEMOCRATIC

REPUBLIC

LATVIA

LEBANON

LESOTHO

LIBERIA

LIBYA

LIECHTENSTEIN

LITHUANIA

LUXEMBOURG

MADAGASCAR

MALAWI

MALAYSIA

MALI

MALTA

MARSHALL ISLANDS

MAURITANIA

MAURITIUS

MEXICO

MONACO

MONGOLIA

MONTENEGRO

MOROCCO

MOZAMBIQUE

MYANMAR

NAMIBIA

NEPAL

NETHERLANDS

NEW ZEALAND

NICARAGUA

NIGER

NIGERIA

NORWAY

OMAN

PAKISTAN

PALAU

PANAMA

PAPUA NEW GUINEA

PARAGUAY

PERU

PHILIPPINES

POLAND

PORTUGAL

QATAR

REPUBLIC OF MOLDOVA

ROMANIA

RUSSIAN FEDERATION

RWANDA

SAUDI ARABIA

SENEGAL

SERBIA

SEYCHELLES

SIERRA LEONE

SINGAPORE

SLOVAKIA

SLOVENIA

SOUTH AFRICA

SPAIN

SRI LANKA

SUDAN

SWEDEN

SWITZERLAND

SYRIAN ARAB REPUBLIC

TAJIKISTAN

THAILAND

THE FORMER YUGOSLAV 

REPUBLIC OF MACEDONIA

TUNISIA

TURKEY

UGANDA

UKRAINE

UNITED ARAB EMIRATES

UNITED KINGDOM OF 

GREAT BRITAIN AND 

NORTHERN IRELAND

UNITED REPUBLIC 

OF TANZANIA

UNITED STATES OF AMERICA

URUGUAY

UZBEKISTAN

VENEZUELA

VIETNAM

YEMEN

ZAMBIA

ZIMBABWE

This publication has been superseded by SSR-6 (Rev. 1).

REGULATIONS FOR THE

SAFE TRANSPORT OF

RADIOACTIVE MATERIAL

2012 Edition

SPECIFIC SAFETY REQUIREMENTS

his Safety Requirements publication includes

a CD-ROM containing the IAEA Safety Glossary:

2007 Edition (2007) and the Fundamental Safety Principles (2006),

each in Arabic, Chinese, English, French, Russian and Spanish versions.

The CD-ROM is also available for purchase separately.

See: http://www-pub.iaea.org/MTCD/publications/publications.asp

INTERNATIONAL ATOMIC ENERGY AGENCY

VIENNA, 2012

IAEA SAFETY STANDARDS SERIES No. SSR-6

This publication has been superseded by SSR-6 (Rev. 1).

IAEA Library Cataloguing in Publication Data

Regulations for the safe transport of radioactive material : specific safety

requirements. — 2012 edition. — Vienna : International Atomic Energy

Agency, 2012.

p. ; 24 cm. — (IAEA safety standard series, ISSN 1020–525X ;

no. SSR-6)

STI/PUB/1570

ISBN 978–92–0–133310–0

Includes bibliographical references.

1. Radiation sources. 2. Radioactive substances — Safety regulations.

3. Radioactive substances — Packaging. I. International Atomic Energy

Agency. II. Series.

IAEAL 12–00777

All IAEA scientific and technical publications are protected by the terms of

the Universal Copyright Convention as adopted in 1952 (Berne) and as revised in

1972 (Paris). The copyright has since been extended by the World Intellectual

Property Organization (Geneva) to include electronic and virtual intellectual

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to royalty agreements. Proposals for non-commercial reproductions and

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should be addressed to the IAEA Publishing Section at:

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Printed by the IAEA in Austria

October 2012

STI/PUB/1570

This publication has been superseded by SSR-6 (Rev. 1).

FOREWORD

by Yukiya Amano

Director General

The IAEA’s Statute authorizes the Agency to “establish or adopt…

standards of safety for protection of health and minimization of danger to life and

property” — standards that the IAEA must use in its own operations, and which

States can apply by means of their regulatory provisions for nuclear and radiation

safety. The IAEA does this in consultation with the competent organs of the

United Nations and with the specialized agencies concerned. A comprehensive

set of high quality standards under regular review is a key element of a stable and

sustainable global safety regime, as is the IAEA’s assistance in their application.

The IAEA commenced its safety standards programme in 1958. The

emphasis placed on quality, fitness for purpose and continuous improvement has

led to the widespread use of the IAEA standards throughout the world. The Safety

Standards Series now includes unified Fundamental Safety Principles, which

represent an international consensus on what must constitute a high level of

protection and safety. With the strong support of the Commission on Safety

Standards, the IAEA is working to promote the global acceptance and use of its

standards.

Standards are only effective if they are properly applied in practice. The

IAEA’s safety services encompass design, siting and engineering safety,

operational safety, radiation safety, safe transport of radioactive material and safe

management of radioactive waste, as well as governmental organization,

regulatory matters and safety culture in organizations. These safety services assist

Member States in the application of the standards and enable valuable experience

and insights to be shared.

Regulating safety is a national responsibility, and many States have decided

to adopt the IAEA’s standards for use in their national regulations. For parties to

the various international safety conventions, IAEA standards provide a

consistent, reliable means of ensuring the effective fulfilment of obligations

under the conventions. The standards are also applied by regulatory bodies and

operators around the world to enhance safety in nuclear power generation and in

nuclear applications in medicine, industry, agriculture and research.

Safety is not an end in itself but a prerequisite for the purpose of the

protection of people in all States and of the environment — now and in the future.

The risks associated with ionizing radiation must be assessed and controlled

without unduly limiting the contribution of nuclear energy to equitable and

sustainable development. Governments, regulatory bodies and operators

everywhere must ensure that nuclear material and radiation sources are used

beneficially, safely and ethically. The IAEA safety standards are designed to

facilitate this, and I encourage all Member States to make use of them.

This publication has been superseded by SSR-6 (Rev. 1).

NOTE BY THE SECRETARIAT

The IAEA safety standards reflect an international consensus on what

constitutes a high level of safety for protecting people and the environment from

harmful effects of ionizing radiation. The process of developing, reviewing and

establishing the IAEA standards involves the IAEA Secretariat and all Member

States, many of which are represented on the four IAEA safety standards

committees and the IAEA Commission on Safety Standards.

The IAEA standards, as a key element of the global safety regime, are kept

under regular review by the Secretariat, the safety standards committees and the

Commission on Safety Standards. The Secretariat gathers information on

experience in the application of the IAEA standards and information gained from

the follow-up of events for the purpose of ensuring that the standards continue to

meet users’ needs. The present publication reflects feedback and experience

accumulated until 2010 and it has been subject to the rigorous review process for

standards.

Lessons that may be learned from studying the accident at the Fukushima

Daiichi nuclear power plant in Japan following the disastrous earthquake and

tsunami of 11 March 2011 will be reflected in this IAEA safety standard as

revised and issued in the future.

This publication has been superseded by SSR-6 (Rev. 1).

THE IAEA SAFETY STANDARDS

BACKGROUND

Radioactivity is a natural phenomenon and natural sources of radiation are

features of the environment. Radiation and radioactive substances have many

beneficial applications, ranging from power generation to uses in medicine, industry

and agriculture. The radiation risks to workers and the public and to the environment

that may arise from these applications have to be assessed and, if necessary,

controlled.

Activities such as the medical uses of radiation, the operation of nuclear

installations, the production, transport and use of radioactive material, and the

management of radioactive waste must therefore be subject to standards of safety.

Regulating safety is a national responsibility. However, radiation risks may

transcend national borders, and international cooperation serves to promote and

enhance safety globally by exchanging experience and by improving capabilities to

control hazards, to prevent accidents, to respond to emergencies and to mitigate any

harmful consequences.

States have an obligation of diligence and duty of care, and are expected to

fulfil their national and international undertakings and obligations.

International safety standards provide support for States in meeting their

obligations under general principles of international law, such as those relating to

environmental protection. International safety standards also promote and assure

confidence in safety and facilitate international commerce and trade.

A global nuclear safety regime is in place and is being continuously improved.

IAEA safety standards, which support the implementation of binding international

instruments and national safety infrastructures, are a cornerstone of this global

regime. The IAEA safety standards constitute a useful tool for contracting parties to

assess their performance under these international conventions.

THE IAEA SAFETY STANDARDS

The status of the IAEA safety standards derives from the IAEA’s Statute, which

authorizes the IAEA to establish or adopt, in consultation and, where appropriate, in

collaboration with the competent organs of the United Nations and with the

specialized agencies concerned, standards of safety for protection of health and

minimization of danger to life and property, and to provide for their application.

With a view to ensuring the protection of people and the environment from

harmful effects of ionizing radiation, the IAEA safety standards establish

This publication has been superseded by SSR-6 (Rev. 1).

fundamental safety principles, requirements and measures to control the radiation

exposure of people and the release of radioactive material to the environment, to

restrict the likelihood of events that might lead to a loss of control over a nuclear

reactor core, nuclear chain reaction, radioactive source or any other source of

radiation, and to mitigate the consequences of such events if they were to occur. The

standards apply to facilities and activities that give rise to radiation risks, including

nuclear installations, the use of radiation and radioactive sources, the transport of

radioactive material and the management of radioactive waste.

Safety measures and security measures

have in common the aim of protecting

human life and health and the environment. Safety measures and security measures

must be designed and implemented in an integrated manner so that security measures

do not compromise safety and safety measures do not compromise security.

The IAEA safety standards reflect an international consensus on what

constitutes a high level of safety for protecting people and the environment from

harmful effects of ionizing radiation. They are issued in the IAEA Safety Standards

Series, which has three categories (see Fig. 1).

Safety Fundamentals

Safety Fundamentals present the fundamental safety objective and principles of

protection and safety, and provide the basis for the safety requirements.

Safety Requirements

An integrated and consistent set of Safety Requirements establishes the

requirements that must be met to ensure the protection of people and the environment,

both now and in the future. The requirements are governed by the objective and

principles of the Safety Fundamentals. If the requirements are not met, measures must

be taken to reach or restore the required level of safety. The format and style of the

requirements facilitate their use for the establishment, in a harmonized manner, of a

national regulatory framework. Requirements, including numbered ‘overarching’

requirements, are expressed as ‘shall’ statements. Many requirements are not

addressed to a specific party, the implication being that the appropriate parties are

responsible for fulfilling them.

Safety Guides

Safety Guides provide recommendations and guidance on how to comply with

the safety requirements, indicating an international consensus that it is necessary to

take the measures recommended (or equivalent alternative measures). The Safety

See also publications issued in the IAEA Nuclear Security Series.

This publication has been superseded by SSR-6 (Rev. 1).

Guides present international good practices, and increasingly they reflect best

practices, to help users striving to achieve high levels of safety. The recommendations

provided in Safety Guides are expressed as ‘should’ statements.

APPLICATION OF THE IAEA SAFETY STANDARDS

The principal users of safety standards in IAEA Member States are regulatory

bodies and other relevant national authorities. The IAEA safety standards are also

used by co-sponsoring organizations and by many organizations that design,

construct and operate nuclear facilities, as well as organizations involved in the use of

radiation and radioactive sources.

The IAEA safety standards are applicable, as relevant, throughout the entire

lifetime of all facilities and activities — existing and new — utilized for peaceful

purposes and to protective actions to reduce existing radiation risks. They can be used

by States as a reference for their national regulations in respect of facilities and

activities.

Part 1. Governmental, Legal and

Regulatory Framework for Safety

Part 2. Leadership and Management

for Safety

Part 3. Radiation Protection and

Safety of Radiation Sources

Part 4. Safety Assessment for

Facilities and Activities

Part 5. Predisposal Management

of Radioactive Waste

Part 6. Decommissioning and

Termination of Activities

Part 7. Emergency Preparedness

and Response

1. Site Evaluation for

Nuclear Installations

2. Safety of Nuclear Power Plants

2/1 Design

2/2 Commissioning and Operation

3. Safety of Research Reactors

4. Safety of Nuclear Fuel

Cycle Facilities

5. Safety of Radioactive Waste

Disposal Facilities

6. Safe Transport of

Radioactive Material

General Safety Requirements Specific Safety Requirements

Safety Fundamentals

Fundamental Safety Principles

Collection of Safety Guides

FIG. 1. The long term structure of the IAEA Safety Standards Series.

This publication has been superseded by SSR-6 (Rev. 1).

The IAEA’s Statute makes the safety standards binding on the IAEA in relation

to its own operations and also on States in relation to IAEA assisted operations.

The IAEA safety standards also form the basis for the IAEA’s safety review

services, and they are used by the IAEA in support of competence building, including

the development of educational curricula and training courses.

International conventions contain requirements similar to those in the IAEA

safety standards and make them binding on contracting parties. The IAEA safety

standards, supplemented by international conventions, industry standards and

detailed national requirements, establish a consistent basis for protecting people and

the environment. There will also be some special aspects of safety that need to be

assessed at the national level. For example, many of the IAEA safety standards, in

particular those addressing aspects of safety in planning or design, are intended to

apply primarily to new facilities and activities. The requirements established in the

IAEA safety standards might not be fully met at some existing facilities that were

built to earlier standards. The way in which IAEA safety standards are to be applied

to such facilities is a decision for individual States.

The scientific considerations underlying the IAEA safety standards provide an

objective basis for decisions concerning safety; however, decision makers must also

make informed judgements and must determine how best to balance the benefits of an

action or an activity against the associated radiation risks and any other detrimental

impacts to which it gives rise.

DEVELOPMENT PROCESS FOR THE IAEA SAFETY STANDARDS

The preparation and review of the safety standards involves the IAEA

Secretariat and four safety standards committees, for nuclear safety (NUSSC),

radiation safety (RASSC), the safety of radioactive waste (WASSC) and the safe

transport of radioactive material (TRANSSC), and a Commission on Safety

Standards (CSS) which oversees the IAEA safety standards programme (see Fig. 2).

All IAEA Member States may nominate experts for the safety standards

committees and may provide comments on draft standards. The membership of the

Commission on Safety Standards is appointed by the Director General and includes

senior governmental officials having responsibility for establishing national

standards.

A management system has been established for the processes of planning,

developing, reviewing, revising and establishing the IAEA safety standards.

It articulates the mandate of the IAEA, the vision for the future application of the

This publication has been superseded by SSR-6 (Rev. 1).

safety standards, policies and strategies, and corresponding functions and

responsibilities.

INTERACTION WITH OTHER INTERNATIONAL ORGANIZATIONS

The findings of the United Nations Scientific Committee on the Effects of

Atomic Radiation (UNSCEAR) and the recommendations of international expert

bodies, notably the International Commission on Radiological Protection (ICRP), are

taken into account in developing the IAEA safety standards. Some safety standards

are developed in cooperation with other bodies in the United Nations system or other

specialized agencies, including the Food and Agriculture Organization of the United

Nations, the United Nations Environment Programme, the International Labour

Organization, the OECD Nuclear Energy Agency, the Pan American Health

Organization and the World Health Organization.

Secretariat and

consultants:

drafting of new or revision

of existing safety standard

Draft

Endorsement

by the CSS

Final draft

Review by

safety standards

committee(s)

Member States

Comments

Draft

Outline and work plan

prepared by the Secretariat;

review by the safety standards

committees and the CSS

FIG. 2. The process for developing a new safety standard or revising an existing standard.

This publication has been superseded by SSR-6 (Rev. 1).

INTERPRETATION OF THE TEXT

Safety related terms are to be understood as defined in the IAEA Safety

Glossary (see

http://www-ns.iaea.org/standards/safety-glossary.htm

). Otherwise,

words are used with the spellings and meanings assigned to them in the latest edition

of The Concise Oxford Dictionary. For Safety Guides, the English version of the text

is the authoritative version.

The background and context of each standard in the IAEA Safety Standards

Series and its objective, scope and structure are explained in Section 1, Introduction,

of each publication.

Material for which there is no appropriate place in the body text (e.g. material

that is subsidiary to or separate from the body text, is included in support of

statements in the body text, or describes methods of calculation, procedures or limits

and conditions) may be presented in appendices or annexes.

An appendix, if included, is considered to form an integral part of the safety

standard. Material in an appendix has the same status as the body text, and the IAEA

assumes authorship of it. Annexes and footnotes to the main text, if included, are used

to provide practical examples or additional information or explanation. Annexes and

footnotes are not integral parts of the main text. Annex material published by the

IAEA is not necessarily issued under its authorship; material under other authorship

may be presented in annexes to the safety standards. Extraneous material presented in

annexes is excerpted and adapted as necessary to be generally useful.

This publication has been superseded by SSR-6 (Rev. 1).

CONTENTS

SECTION I. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

Background (101–103) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

Objective (104–105) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

Scope (106–110) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

Structure (111). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

SECTION II. DEFINITIONS (201–249) . . . . . . . . . . . . . . . . . . . . . . . . 5

SECTION III. GENERAL PROVISIONS. . . . . . . . . . . . . . . . . . . . . . . . 15

Radiation protection (301–303) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

Emergency response (304–305) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

Management system (306) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16

Compliance assurance (307–308) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16

Non-compliance (309). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16

Special arrangement (310) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17

Training (311–315) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17

SECTION IV. ACTIVITY LIMITS AND CLASSIFICATION . . . . . . . 21

General provisions (401). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21

Basic radionuclide values (402) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21

Determination of basic radionuclide values (403–407) . . . . . . . . . . . . . . . . 21

Classification of material (408–420). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 47

Classification of packages (421–433) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51

Special arrangement (434) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55

SECTION V. REQUIREMENTS AND CONTROLS

FOR TRANSPORT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57

Requirements before the first shipment (501). . . . . . . . . . . . . . . . . . . . . . . . 57

Requirements before each shipment (502–503) . . . . . . . . . . . . . . . . . . . . . . 57

Transport of other goods (504–506) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58

Other dangerous properties of contents (507) . . . . . . . . . . . . . . . . . . . . . . . . 59

Requirements and controls for contamination and

for leaking packages (508–514). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59

This publication has been superseded by SSR-6 (Rev. 1).

Requirements and controls for transport of excepted packages

(515–516). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60

Requirements and controls for transport of LSA material and

SCO in industrial packages or unpackaged (517–522) . . . . . . . . . . . . 61

Determination of transport index (523–524). . . . . . . . . . . . . . . . . . . . . . . . . 62

Determination of criticality safety index for consignments,

freight containers and overpacks (525) . . . . . . . . . . . . . . . . . . . . . . . . 63

Limits on transport index, criticality safety index and

radiation levels for packages and overpacks (526–528) . . . . . . . . . . . 64

Categories (529) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64

Marking, labelling and placarding (530–544). . . . . . . . . . . . . . . . . . . . . . . . 65

Consignor’s responsibilities (545–561) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73

Transport and storage in transit (562–581) . . . . . . . . . . . . . . . . . . . . . . . . . . 79

Customs operations (582) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 86

Undeliverable consignments (583) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 86

Retention and availability of transport documents by carriers (584–588) . . . 86

SECTION VI. REQUIREMENTS FOR RADIOACTIVE

MATERIAL AND FOR PACKAGINGS

AND PACKAGES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89

Requirements for radioactive material (601–605) . . . . . . . . . . . . . . . . . . . . 89

Requirements for material excepted from fissile classification (606). . . . . . 90

General requirements for all packagings and packages (607–618). . . . . . . . 90

Additional requirements for packages transported by air (619–621) . . . . . . 92

Requirements for excepted packages (622) . . . . . . . . . . . . . . . . . . . . . . . . . 92

Requirements for industrial packages (623–630) . . . . . . . . . . . . . . . . . . . . . 92

Requirements for packages containing uranium hexafluoride (631–634) . . . 95

Requirements for Type A packages (635–651). . . . . . . . . . . . . . . . . . . . . . . 96

Requirements for Type B(U) packages (652–666) . . . . . . . . . . . . . . . . . . . . 98

Requirements for Type B(M) packages (667–668). . . . . . . . . . . . . . . . . . . . 100

Requirements for Type C packages (669–672). . . . . . . . . . . . . . . . . . . . . . . 101

Requirements for packages containing fissile material (673–686) . . . . . . . . 102

SECTION VII. TEST PROCEDURES . . . . . . . . . . . . . . . . . . . . . . . . . . . 109

Demonstration of compliance (701–702) . . . . . . . . . . . . . . . . . . . . . . . . . . . 109

Leaching test for LSA-III material and low dispersible

radioactive material (703) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 109

Tests for special form radioactive material (704–711) . . . . . . . . . . . . . . . . . 110

This publication has been superseded by SSR-6 (Rev. 1).

Tests for low dispersible radioactive material (712). . . . . . . . . . . . . . . . . . . 112

Tests for packages (713–737) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 112

SECTION VIII. APPROVAL AND ADMINISTRATIVE

REQUIREMENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 119

General (801–802). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 119

Approval of special form radioactive material and

low dispersible radioactive material (803–804). . . . . . . . . . . . . . . . . . 120

Approval of material excepted from fissile classification (805–806) . . . . . . 120

Approval of package designs (807–816). . . . . . . . . . . . . . . . . . . . . . . . . . . . 121

Approval of alternative activity limits for an exempt consignment

of instruments or articles (817–818) . . . . . . . . . . . . . . . . . . . . . . . . . . 123

Transitional arrangements (819–823) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 124

Notification and registration of serial numbers (824) . . . . . . . . . . . . . . . . . . 126

Approval of shipments (825–828). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 126

Approval of shipments under special arrangement (829–831) . . . . . . . . . . . 127

Competent authority certificates of approval (832–833) . . . . . . . . . . . . . . . 128

Contents of certificates of approval (834–839). . . . . . . . . . . . . . . . . . . . . . . 131

Validation of certificates (840) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 137

REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 139

ANNEX I: SUMMARY OF APPROVAL AND

PRIOR NOTIFICATION REQUIREMENTS . . . . . . . . . . . . 141

ANNEX II: CONVERSION FACTORS AND PREFIXES . . . . . . . . . . . 147

ANNEX III: SUMMARY OF CONSIGNMENTS REQUIRING

EXCLUSIVE USE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 149

CONTRIBUTORS TO DRAFTING AND REVIEW (2012). . . . . . . . . . . . 151

BODIES FOR THE ENDORSEMENT OF

IAEA SAFETY STANDARDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 159

INDEX . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 163

LIST OF TABLES

Table 1. Excerpts from the list of UN numbers, proper shipping

names and descriptions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22

Table 2. Basic radionuclide values . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25

This publication has been superseded by SSR-6 (Rev. 1).

Table 3. Basic radionuclide values for unknown radionuclides

or mixtures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46

Table 4. Activity limits for excepted packages. . . . . . . . . . . . . . . . . . . . 51

Table 5. Industrial package requirements for LSA material

and SCO . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62

Table 6. Conveyance activity limits for LSA material and SCO

in industrial packages or unpackaged. . . . . . . . . . . . . . . . . . . . 63

Table 7. Multiplication factors for tanks, freight containers and

unpackaged LSA-I and SCO-I . . . . . . . . . . . . . . . . . . . . . . . . . 64

Table 8. Categories of packages, overpacks and freight containers . . . . 65

Table 9. UN marking for packages and overpacks. . . . . . . . . . . . . . . . . 66

Table 10. Transport index limits for freight containers and

conveyances not under exclusive use . . . . . . . . . . . . . . . . . . . . 81

Table 11. CSI limits for freight containers and

conveyances containing fissile material . . . . . . . . . . . . . . . . . . 82

Table 12. Insolation data. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99

Table 13. Values of Z for calculation of CSI in accordance

with para. 674 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103

Table 14. Free drop distance for testing packages to

normal conditions of transport . . . . . . . . . . . . . . . . . . . . . . . . . 114

This publication has been superseded by SSR-6 (Rev. 1).

Section I

INTRODUCTION

BACKGROUND

101. These Regulations establish standards of safety which provide an

acceptable level of control of the radiation, criticality and thermal hazards to

persons, property and the environment that are associated with the transport of

radioactive material. These Regulations are based on the Fundamental Safety

Principles, Safety Fundamentals No. SF-1 [1], jointly sponsored by the European

Atomic Energy Community (EAEC), the Food and Agriculture Organization of

the United Nations (FAO), the IAEA, the International Labour Organization

(ILO), the International Maritime Organization (IMO), the OECD Nuclear

Energy Agency (NEA), the Pan American Health Organization (PAHO), the

United Nations Environment Programme (UNEP) and the World Health

Organization (WHO), and on the International Basic Safety Standards for

Protection against Ionizing Radiation and for the Safety of Radiation Sources,

Safety Series No. 115 [2], jointly sponsored by the FAO, the IAEA, the ILO, the

NEA, the PAHO and the WHO. Thus, compliance with these Regulations is

deemed to satisfy the principles of the Basic Safety Standards in respect of

transport. In accordance with Ref. [1], the prime responsibility for safety must

rest with the person or organization responsible for facilities and activities that

give rise to radiation risks.

102. This Safety Standard is supplemented by a hierarchy of Safety Guides,

including: Advisory Material for the IAEA Regulations for the Safe Transport of

Radioactive Material, IAEA Safety Standards Series No. TS-G-1.1 (Rev. 1) [3];

Planning and Preparing for Emergency Response to Transport Accidents

Involving Radioactive Material, IAEA Safety Standards Series No. TS-G-1.2

(ST-3) [4]; Compliance Assurance for the Safe Transport of Radioactive

Material, IAEA Safety Standards Series No. TS-G-1.5 [5]; The Management

System for the Safe Transport of Radioactive Material, IAEA Safety Standards

Series No. TS-G-1.4 [6]; and Radiation Protection Programmes for the Transport

of Radioactive Material, IAEA Safety Standards Series No. TS-G-1.3 [7].

103. In certain parts of these Regulations, a particular action is prescribed, but

the responsibility for carrying out the action is not specifically assigned to any

particular person. Such responsibility may vary according to the laws and

customs of different countries and the international conventions into which these

This publication has been superseded by SSR-6 (Rev. 1).

SECTION I

countries have entered. For the purpose of these Regulations, it is not necessary to

make this assignment, but only to identify the action itself. It remains the

prerogative of each government to assign this responsibility.

OBJECTIVE

104. The objective of these Regulations is to establish requirements that must be

satisfied to ensure safety and to protect persons, property and the environment

from the effects of radiation in the transport of radioactive material. This

protection is achieved by requiring:

(a) Containment of the radioactive contents;

(b) Control of external radiation levels;

(d) Prevention of damage caused by heat.

These requirements are satisfied firstly by applying a graded approach to contents

limits for packages and conveyances and to performance standards applied to

package designs, depending upon the hazard of the radioactive contents.

Secondly, they are satisfied by imposing conditions on the design and operation

of packages and on the maintenance of packagings, including consideration of

the nature of the radioactive contents. Finally, they are satisfied by requiring

administrative controls, including, where appropriate, approval by competent

authorities.

105. In the transport of radioactive material, the safety of persons and the

protection of property and the environment are assured when these Regulations

are complied with. Confidence in this regard is achieved through management

system and compliance assurance programmes.

SCOPE

106. These Regulations apply to the transport of radioactive material by all

modes on land, water, or in the air, including transport that is incidental to the use

of the radioactive material. Transport comprises all operations and conditions

associated with, and involved in, the movement of radioactive material; these

include the design, manufacture, maintenance and repair of packaging, and the

preparation, consigning, loading, carriage including in-transit storage, unloading

and receipt at the final destination of loads of radioactive material and packages.

This publication has been superseded by SSR-6 (Rev. 1).

INTRODUCTION

A graded approach is applied in specifying the performance standards in these

Regulations, which are characterized in terms of three general severity levels:

(a) Routine conditions of transport (incident free);

(b) Normal conditions of transport (minor mishaps);

107. These Regulations do not apply to any of the following:

(a) Radioactive material that is an integral part of the means of transport.

(b) Radioactive material moved within an establishment that is subject to

appropriate safety regulations in force in the establishment and where the

movement does not involve public roads or railways.

for diagnosis or treatment.

(d) Radioactive material in or on a person who is to be transported for medical

treatment because the person has been subject to accidental or deliberate

intake of radioactive material or to contamination.

(e) Radioactive material in consumer products that have received regulatory

approval, following their sale to the end user.

(f) Natural material and ores containing naturally occurring radionuclides,

which may have been processed, provided the activity concentration of the

material does not exceed 10 times the values specified in Table 2, or

calculated in accordance with paras 403(a) and 404–407. For natural

materials and ores containing naturally occurring radionuclides that are not

in secular equilibrium the calculation of the activity concentration shall be

performed in accordance with para. 405.

(g) Non-radioactive solid objects with radioactive substances present on any

surface in quantities not in excess of the levels defined in para. 214.

108. These Regulations do not specify controls such as routeing or physical

protection that may be instituted for reasons other than radiological safety. Any

such controls shall take into account radiological and non-radiological hazards,

and shall not detract from the standards of safety that these Regulations are

intended to provide.

109. Measures should be taken to ensure that radioactive material is kept secure

in transport so as to prevent theft or damage and to ensure that control of the

material is not relinquished inappropriately (see Annex I).

This publication has been superseded by SSR-6 (Rev. 1).

SECTION I

110. For radioactive material having subsidiary risks, and for transport of

radioactive material with other dangerous goods, the relevant transport

regulations for dangerous goods shall apply in addition to these Regulations.

STRUCTURE

111. This publication is structured so that Section II defines the terms that are

required for the purposes of these Regulations; Section III provides general

provisions; Section IV provides activity limits and material restrictions used

throughout these Regulations; Section V provides requirements and controls for

transport; Section VI provides requirements for radioactive material and for

packagings and packages; Section VII provides requirements for test procedures;

and Section VIII provides requirements for approvals and administration.

This publication has been superseded by SSR-6 (Rev. 1).

Section II

DEFINITIONS

The following definitions shall apply for the purposes of these Regulations:

and A

201. A

shall mean the activity value of special form radioactive material that is

listed in Table 2 or derived in Section IV and is used to determine the activity

limits for the requirements of these Regulations. A

shall mean the activity value

of radioactive material, other than special form radioactive material, that is listed

in Table 2 or derived in Section IV and is used to determine the activity limits for

the requirements of these Regulations.

Aircraft

202. Cargo aircraft shall mean any aircraft, other than a passenger aircraft, that

is carrying goods or property.

203. Passenger aircraft shall mean an aircraft that carries any person other than

a crew member, a carrier’s employee in an official capacity, an authorized

representative of an appropriate national authority, or a person accompanying a

consignment or other cargo.

Approval

204. Multilateral approval shall mean approval by the relevant competent

authority of the country of origin of the design or shipment, as applicable, and

also, where the consignment is to be transported through or into any other

country, approval by the competent authority of that country.

205. Unilateral approval shall mean an approval of a design that is required to

be given by the competent authority of the country of origin of the design only.

Carrier

206. Carrier shall mean any person, organization or government undertaking the

carriage of radioactive material by any means of transport. The term includes

both carriers for hire or reward (known as common or contract carriers in some

This publication has been superseded by SSR-6 (Rev. 1).

SECTION II

countries) and carriers on own account (known as private carriers in some

countries).

Competent authority

207. Competent authority shall mean any body or authority designated or

otherwise recognized as such for any purpose in connection with these

Regulations.

Compliance assurance

208. Compliance assurance shall mean a systematic programme of measures

applied by a competent authority that is aimed at ensuring that the provisions of

these Regulations are met in practice.

Confinement system

209. Confinement system shall mean the assembly of fissile material and

packaging components specified by the designer and agreed to by the competent

authority as intended to preserve criticality safety.

Consignee

210. Consignee shall mean any person, organization or government that is

entitled to take delivery of a consignment.

Consignment

211. Consignment shall mean any package or packages, or load of radioactive

material, presented by a consignor for transport.

Consignor

212. Consignor shall mean any person, organization or government that prepares

a consignment for transport.

Containment system

213. Containment system shall mean the assembly of components of the

packaging specified by the designer as intended to retain the radioactive material

during transport.

This publication has been superseded by SSR-6 (Rev. 1).

DEFINITIONS

Contamination

214. Contamination shall mean the presence of a radioactive substance on a

surface in quantities in excess of 0.4 Bq/cm

for beta and gamma emitters and low

toxicity alpha emitters, or 0.04 Bq/cm

for all other alpha emitters.

215. Non-fixed contamination shall mean contamination that can be removed

from a surface during routine conditions of transport.

216. Fixed contamination shall mean contamination other than non-fixed

contamination.

Conveyance

217. Conveyance shall mean:

(a) For transport by road or rail: any vehicle.

(b) For transport by water: any vessel, or any hold, compartment, or defined

deck area of a vessel.

Criticality safety index

218. Criticality safety index (CSI) assigned to a package, overpack or freight

container containing fissile material shall mean a number that is used to provide

control over the accumulation of packages, overpacks or freight containers

containing fissile material.

Defined deck area

219. Defined deck area shall mean the area of the weather deck of a vessel, or of

a vehicle deck of a roll-on/roll-off ship or ferry, that is allocated for the stowage

of radioactive material.

Design

220. Design shall mean the description of fissile material excepted under

para. 417(f), special form radioactive material, low dispersible radioactive

material, package or packaging that enables such an item to be fully identified.

The description may include specifications, engineering drawings, reports

This publication has been superseded by SSR-6 (Rev. 1).

SECTION II

demonstrating compliance with regulatory requirements, and other relevant

documentation.

Exclusive use

221. Exclusive use shall mean the sole use, by a single consignor, of a

conveyance or of a large freight container, in respect of which all initial,

intermediate and final loading and unloading and shipment are carried out in

accordance with the directions of the consignor or consignee, where so required

by these Regulations.

Fissile nuclides and fissile material

222. Fissile nuclides shall mean uranium-233, uranium-235, plutonium-239 and

plutonium-241. Fissile material shall mean a material containing any of the

fissile nuclides. Excluded from the definition of fissile material are the following:

(a) Natural uranium or depleted uranium that is unirradiated;

(b) Natural uranium or depleted uranium that has been irradiated in thermal

reactors only;

(d) Any combination of (a), (b) and/or (c).

These exclusions are only valid if there is no other material with fissile nuclides

in the package or in the consignment if shipped unpackaged.

Freight container — small, large

223. Freight container shall mean an article of transport equipment that is of a

permanent character and accordingly strong enough to be suitable for repeated

use; specially designed to facilitate the transport of goods, by one or other modes

of transport, without intermediate reloading, designed to be secured and/or

readily handled, having fittings for these purposes. The term “freight container”

does not include the vehicle.

A small freight container shall mean a freight container that has an internal

volume of not more than 3 m

. A large freight container shall mean a freight

container that has an internal volume of more than 3 m

This publication has been superseded by SSR-6 (Rev. 1).

DEFINITIONS

Intermediate bulk container

224. Intermediate bulk container (IBC) shall mean a portable packaging that:

(a) Has a capacity of not more than 3 m

;

(b) Is designed for mechanical handling;

by tests.

Low dispersible radioactive material

225. Low dispersible radioactive material shall mean either a solid radioactive

material or a solid radioactive material in a sealed capsule, that has limited

dispersibility and is not in powder form.

Low specific activity material

226. Low specific activity (LSA) material shall mean radioactive material that by

its nature has a limited specific activity, or radioactive material for which limits

of estimated average specific activity apply. External shielding materials

surrounding the LSA material shall not be considered in determining the

estimated average specific activity.

Low toxicity alpha emitters

227. Low toxicity alpha emitters are: natural uranium, depleted uranium, natural

thorium, uranium-235, uranium-238, thorium-232, thorium-228 and thorium-230

when contained in ores or physical and chemical concentrates; or alpha emitters

with a half-life of less than 10 days.

Management system

228. Management system shall mean a set of interrelated or interacting elements

(system) for establishing policies and objectives and enabling the objectives to be

achieved in an efficient and effective manner.

Maximum normal operating pressure

229. Maximum normal operating pressure shall mean the maximum pressure

above atmospheric pressure at mean sea level that would develop in the

containment system in a period of one year under the conditions of temperature

This publication has been superseded by SSR-6 (Rev. 1).

SECTION II

and solar radiation corresponding to environmental conditions in the absence of

venting, external cooling by an ancillary system, or operational controls during

transport.

Overpack

230. Overpack shall mean an enclosure used by a single consignor to contain one

or more packages and to form one unit for convenience of handling and stowage

during transport.

Package

231. Package shall mean the complete product of the packing operation,

consisting of the packaging and its contents prepared for transport. The types of

package covered by these Regulations that are subject to the activity limits and

material restrictions of Section IV and meet the corresponding requirements are:

(a) Excepted package;

(b) Industrial package Type 1 (Type IP-1);

(d) Industrial package Type 3 (Type IP-3);

(e) Type A package;

(f) Type B(U) package;

(g) Type B(M) package;

(h) Type C package.

Packages containing fissile material or uranium hexafluoride are subject to

additional requirements.

Packaging

232. Packaging shall mean one or more receptacles and any other components or

materials necessary for the receptacles to perform the containment and other

safety functions.

Radiation level

233. Radiation level shall mean the corresponding dose rate expressed in

millisieverts per hour or microsieverts per hour.

This publication has been superseded by SSR-6 (Rev. 1).

DEFINITIONS

Radiation protection programme

234. Radiation protection programme shall mean systematic arrangements that

are aimed at providing adequate consideration of radiation protection measures.

Radioactive contents

235. Radioactive contents shall mean the radioactive material together with any

contaminated or activated solids, liquids and gases within the packaging.

Radioactive material

236. Radioactive material shall mean any material containing radionuclides

where both the activity concentration and the total activity in the consignment

exceed the values specified in paras 402–407.

Shipment

237. Shipment shall mean the specific movement of a consignment from origin

to destination.

Special arrangement

238. Special arrangement shall mean those provisions, approved by the

competent authority, under which consignments that do not satisfy all the

applicable requirements of these Regulations may be transported.

Special form radioactive material

239. Special form radioactive material shall mean either an indispersible solid

radioactive material or a sealed capsule containing radioactive material.

Specific activity

240. Specific activity of a radionuclide shall mean the activity per unit mass of

that nuclide. The specific activity of a material shall mean the activity per unit

mass of the material in which the radionuclides are essentially uniformly

distributed.

This publication has been superseded by SSR-6 (Rev. 1).

SECTION II

Surface contaminated object

241. Surface contaminated object (SCO) shall mean a solid object that is not

itself radioactive but which has radioactive material distributed on its surface.

Tank

242. Ta nk shall mean a portable tank (including a tank container), a road tank

vehicle, a rail tank wagon or a receptacle that contains solids, liquids, or gases,

having a capacity of not less than 450 L when used for the transport of gases.

Through or into

243. Through or into shall mean through or into the countries in which a

consignment is transported but specifically excludes countries over which a

consignment is carried by air, provided that there are no scheduled stops in those

countries.

Transport index

244. Transport index (TI) assigned to a package, overpack or freight container,

or to unpackaged LSA-I or SCO-I, shall mean a number that is used to provide

control over radiation exposure.

Unirradiated thorium

245. Unirradiated thorium shall mean thorium containing not more than 10

–7

of uranium-233 per gram of thorium-232.

Unirradiated uranium

246. Unirradiated uranium shall mean uranium containing not more than

2 × 10

Bq of plutonium per gram of uranium-235, not more than 9 × 10

Bq of

fission products per gram of uranium-235 and not more than 5 × 10

–3

g of

uranium-236 per gram of uranium-235.

Uranium — natural, depleted, enriched

247. Natural uranium shall mean uranium (which may be chemically separated)

containing the naturally occurring distribution of uranium isotopes

(approximately 99.28% uranium-238 and 0.72% uranium-235, by mass).

This publication has been superseded by SSR-6 (Rev. 1).

DEFINITIONS

Depleted uranium shall mean uranium containing a lesser mass percentage of

uranium-235 than natural uranium. Enriched uranium shall mean uranium

containing a greater mass percentage of uranium-235 than 0.72%. In all cases, a

very small mass percentage of uranium-234 is present.

Vehicle

248. Ve hi cle shall mean a road vehicle (including an articulated vehicle, i.e. a

tractor and semi-trailer combination), railroad car or railway wagon. Each trailer

shall be considered as a separate vehicle.

Vessel

249. Ve ss el shall mean any seagoing vessel or inland waterway craft used for

carrying cargo.

This publication has been superseded by SSR-6 (Rev. 1).

Section III

GENERAL PROVISIONS

RADIATION PROTECTION

301. Doses to persons shall be below the relevant dose limits. Protection and

safety shall be optimized in order that the magnitude of individual doses, the

number of persons exposed and the likelihood of incurring exposure shall be kept

as low as reasonably achievable, economic and social factors being taken into

account, within the restriction that the doses to individuals are subject to dose

constraints. A structured and systematic approach shall be adopted and shall

include consideration of the interfaces between transport and other activities.

302. A radiation protection programme shall be established for the transport of

radioactive material. The nature and extent of the measures to be employed in the

programme shall be related to the magnitude and likelihood of radiation

exposures. The programme shall incorporate the requirements of paras 301,

303–305, 311 and 562. Programme documents shall be available, on request, for

inspection by the relevant competent authority.

303. For occupational exposures arising from transport activities, where it is

assessed that the effective dose either:

(a) Is likely to be between 1 and 6 mSv in a year, a dose assessment programme

via workplace monitoring or individual monitoring shall be conducted; or

(b) Is likely to exceed 6 mSv in a year, individual monitoring shall be

conducted.

When individual monitoring or workplace monitoring is conducted, appropriate

records shall be kept.

EMERGENCY RESPONSE

304. In the event of accidents or incidents during the transport of radioactive

material, emergency provisions, as established by relevant national and/or

international organizations, shall be observed to protect persons, property and the

environment. Appropriate guidelines for such provisions are contained in

Ref. [4].

This publication has been superseded by SSR-6 (Rev. 1).

SECTION III

305. Emergency procedures shall take into account the formation of other

dangerous substances that may result from the reaction between the contents of a

consignment and the environment in the event of an accident.

MANAGEMENT SYSTEM

306. A management system based on international, national or other standards

acceptable to the competent authority shall be established and implemented for

all activities within the scope of the Regulations, as identified in para. 106, to

ensure compliance with the relevant provisions of these Regulations.

Certification that the design specification has been fully implemented shall be

available to the competent authority. The manufacturer, consignor or user shall be

prepared:

(a) To provide facilities for inspection during manufacture and use;

(b) To demonstrate compliance with these Regulations to the competent

authority.

Where competent authority approval is required, such approval shall take into

account and be contingent upon the adequacy of the management system.

COMPLIANCE ASSURANCE

307. The competent authority shall assure compliance with these Regulations.

308. The relevant competent authority shall arrange for periodic assessments of

the radiation doses to persons due to the transport of radioactive material, to

ensure that the system of protection and safety complies with the Basic Safety

Standards [2].

NON-COMPLIANCE

309. In the event of non-compliance with any limit in these Regulations

applicable to radiation level or contamination:

(a) The consignor, consignee, carrier and any organization involved during

transport who may be affected, as appropriate, shall be informed of the

non-compliance by:

This publication has been superseded by SSR-6 (Rev. 1).

GENERAL PROVISIONS

(i) The carrier if the non-compliance is identified during transport; or

(ii) The consignee if the non-compliance is identified at receipt.

(b) The carrier, consignor or consignee, as appropriate, shall:

(i) Take immediate steps to mitigate the consequences of the non-

compliance;

(ii) Investigate the non-compliance and its causes, circumstances and

consequences;

(iii) Take appropriate action to remedy the causes and circumstances that

led to the non-compliance and to prevent a recurrence of circumstances

similar to those that led to the non-compliance;

(iv) Communicate to the relevant competent authority(ies) on the causes of

the non-compliance and on corrective or preventive actions taken or to

be taken.

relevant competent authority(ies), respectively, shall be made as soon as

practicable and it shall be immediate whenever an emergency exposure

situation has developed or is developing.

SPECIAL ARRANGEMENT

310. Consignments for which conformity with the other provisions of these

Regulations is impracticable shall not be transported except under special

arrangement. Provided the competent authority is satisfied that conformity with

the other provisions of these Regulations is impracticable and that the requisite

standards of safety established by these Regulations have been demonstrated

through means alternative to the other provisions, the competent authority may

approve special arrangement transport operations for single or a planned series of

multiple consignments. The overall level of safety in transport shall be at least

equivalent to that which would be provided if all the applicable requirements had

been met. For consignments of this type, multilateral approval shall be required.

TRAINING

311. Workers shall receive appropriate training concerning radiation protection,

including the precautions to be observed in order to restrict their occupational

exposure and the exposure of other persons who might be affected by their

actions.

This publication has been superseded by SSR-6 (Rev. 1).

SECTION III

312. Persons engaged in the transport of radioactive material shall receive

training in the contents of these Regulations commensurate with their

responsibilities.

313. Individuals such as those who classify radioactive material; pack

radioactive material; mark and label radioactive material; prepare transport

documents for radioactive material; offer or accept radioactive material for

transport; carry or handle radioactive material in transport; mark or placard or

load or unload packages of radioactive material into or from transport vehicles,

bulk packagings or freight containers; or are otherwise directly involved in the

transport of radioactive material as determined by the competent authority; shall

receive the following training:

(a) General awareness/familiarization training:

(i) Each person shall receive training designed to provide familiarity with

the general provisions of these Regulations.

(ii) Such training shall include a description of the categories of

radioactive material; labelling, marking, placarding and packaging and

segregation requirements; a description of the purpose and content of

the radioactive material transport document; and a description of

available emergency response documents.

(b) Function specific training: Each person shall receive detailed training

concerning specific radioactive material transport requirements that are

applicable to the function that person performs;

release and the functions performed, each person shall receive training on:

(i) Methods and procedures for accident avoidance, such as proper use of

package handling equipment and appropriate methods of stowage of

radioactive material.

(ii) Available emergency response information and how to use it.

(iii) General dangers presented by the various categories of radioactive

material and how to prevent exposure to those hazards, including, if

appropriate, the use of personal protective clothing and equipment.

(iv) Immediate procedures to be followed in the event of an unintentional

release of radioactive material, including any emergency response

procedures for which the person is responsible and personal protection

procedures to be followed.

314. Records of all safety training undertaken shall be kept by the employer and

made available to the employee if requested.

This publication has been superseded by SSR-6 (Rev. 1).

GENERAL PROVISIONS

315. The training required in para. 313 shall be provided or verified upon

employment in a position involving radioactive material transport and shall be

periodically supplemented with retraining as deemed appropriate by the

competent authority.

This publication has been superseded by SSR-6 (Rev. 1).

Section IV

ACTIVITY LIMITS AND CLASSIFICATION

GENERAL PROVISIONS

401. Radioactive material shall be assigned to one of the UN numbers specified

in Table 1 in accordance with paras 408–434.

BASIC RADIONUCLIDE VALUES

402. The following basic values for individual radionuclides are given in Table 2:

(a) A

and A

in TBq;

(b) Activity concentration limits for exempt material in Bq/g;

DETERMINATION OF BASIC RADIONUCLIDE VALUES

403. For individual radionuclides:

(a) That are not listed in Table 2, the determination of the basic radionuclide

values referred to in para. 402 shall require multilateral approval. For these

radionuclides, activity concentrations for exempt material and activity limits

for exempt consignments shall be calculated in accordance with the principles

established in the BSS [2]. It is permissible to use an A

value calculated using

a dose coefficient for the appropriate lung absorption type, as recommended

by the International Commission on Radiological Protection, if the chemical

forms of each radionuclide under both normal and accident conditions of

transport are taken into consideration. Alternatively, the radionuclide values

in Table 3 may be used without obtaining competent authority approval.

(b) In instruments or articles in which the radioactive material is enclosed in or

is included as a component part of the instrument or other manufactured

article and which meets para. 423(c), alternative basic radionuclide values

to those in Table 2 for the activity limit for an exempt consignment are

permitted and shall require multilateral approval. Such alternative

activity

limits for an exempt consignment shall be calculated in accordance with the

principles set out in the BSS [2].

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

TABLE 1. EXCERPTS FROM THE LIST OF UN NUMBERS, PROPER

SHIPPING NAMES AND DESCRIPTIONS

Assignment of

UN numbers

PROPER SHIPPING NAME

and description

Excepted package

UN 2908 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE —

EMPTY PACKAGING

UN 2909 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE —

ARTICLES MANUFACTURED FROM NATURAL URANIUM

or DEPLETED URANIUM or NATURAL THORIUM

UN 2910 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE —

LIMITED QUANTITY OF MATERIAL

UN 2911 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE —

INSTRUMENTS or ARTICLES

UN 3507 URANIUM HEXAFLUORIDE, RADIOACTIVE MATERIAL,

EXCEPTED PACKAGE, less than 0.1 kg per package, non-fissile

or fissile-excepted

Low specific activity material

UN 2912 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY 

(LSA-I), non-fissile or fissile-excepted

UN 3321 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY

(LSA-II), non-fissile or fissile-excepted

UN 3322 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY

(LSA-III), non-fissile or fissile-excepted

UN 3324 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY

(LSA-II), FISSILE

UN 3325 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY

(LSA-III), FISSILE

Surface contaminated objects

UN 2913 RADIOACTIVE MATERIAL, SURFACE CONTAMINATED

OBJECTS (SCO-I or SCO-II), non-fissile or fissile-excepted

UN 3326 RADIOACTIVE MATERIAL, SURFACE CONTAMINATED

OBJECTS (SCO-I or SCO-II), FISSILE

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

Type A package

UN 2915 RADIOACTIVE MATERIAL, TYPE A PACKAGE, non-special

form, non-fissile or fissile-excepted

UN 3327 RADIOACTIVE MATERIAL, TYPE A PACKAGE, FISSILE,

non-special form

UN 3332 RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL

FORM, non-fissile or fissile-excepted

UN 3333 RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL

FORM, FISSILE

Type B(U) package

UN 2916 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, non-

fissile or fissile-excepted

UN 3328 RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, FISSILE

Type B(M) package

UN 2917 RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE, non-

fissile or fissile-excepted

UN 3329 RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE, FISSILE

Type C package

UN 3323 RADIOACTIVE MATERIAL, TYPE C PACKAGE, non-fissile or

fissile-excepted

UN 3330 RADIOACTIVE MATERIAL, TYPE C PACKAGE, FISSILE

Special arrangement

UN 2919 RADIOACTIVE MATERIAL, TRANSPORTED UNDER

SPECIAL ARRANGEMENT, non-fissile or fissile-excepted

UN 3331 RADIOACTIVE MATERIAL, TRANSPORTED UNDER

SPECIAL ARRANGEMENT, FISSILE

Uranium hexafluoride

UN 2977 RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE,

FISSILE

TABLE 1. EXCERPTS FROM THE LIST OF UN NUMBERS, PROPER

SHIPPING NAMES AND DESCRIPTIONS (cont.)

Assignment of

UN numbers

PROPER SHIPPING NAME

and description

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

404. In the calculations of

and

for a radionuclide not listed in Table 2, a single

radioactive decay chain in which the radionuclides are present in their naturally

occurring proportions, and in which no daughter nuclide has a half-life either longer

than 10 days or longer than that of the parent nuclide, shall be considered as a single

radionuclide; and the activity to be taken into account and the

value to be

applied shall be that corresponding to the parent nuclide of that chain. In the case of

radioactive decay chains in which any daughter nuclide has a half-life either longer

than 10 days or longer than that of the parent nuclide, the parent and such daughter

nuclides shall be considered as mixtures of different nuclides.

405. For mixtures of radionuclides, the basic radionuclide values referred to in

para. 402 may be determined as follows:

where

f(i)

is the fraction of activity or activity concentration of radionuclide i in the

mixture.

X(i) is the appropriate value of A

or A

, or the activity concentration limit for

exempt material or the activity limit for an exempt consignment as

appropriate for the radionuclide i.

is the derived value of A

or A

, or the activity concentration limit for

exempt material or the activity limit for an exempt consignment in the case

of a mixture.

Text continued on p. 46

UN 2978 RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE,

non-fissile or fissile-excepted

The “PROPER SHIPPING NAME” is found in the column “PROPER SHIPPING NAME

and description” and is restricted to that part shown in CAPITAL LETTERS. In the cases of

UN 2909, UN 2911, UN 2913 and UN 3326, where alternative proper shipping names are

separated by the word “or”, only the relevant proper shipping name shall be used.

The term “fissile-excepted” refers only to material excepted under para. 417.

TABLE 1. EXCERPTS FROM THE LIST OF UN NUMBERS, PROPER

SHIPPING NAMES AND DESCRIPTIONS (cont.)

Assignment of

UN numbers

PROPER SHIPPING NAME

and description



()

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

TABLE 2. BASIC RADIONUCLIDE VALUES

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

Actinium (89)

Ac-225 (a) 8 × 10

–1

6 × 10

–3

1 × 10

Ac-227 (a) 9 × 10

–1

9 × 10

–5

1 × 10

–1

1 × 10

Ac-228 6 × 10

–1

5 × 10

–1

1 × 10

Silver (47)

Ag-105 2 × 10

2 × 10

1 × 10

Ag-108m (a) 7 × 10

–1

7 × 10

–1

1 × 10

(b) 1 × 10

(b)

Ag-110m (a) 4 × 10

–1

4 × 10

–1

1 × 10

Ag-111 2 × 10

6 × 10

–1

1 × 10

Aluminium (13)

Al-26 1 × 10

–1

1 × 10

–1

1 × 10

Americium (95)

Am-241 1 × 10

1 × 10

–3

1 × 10

Am-242m (a) 1 × 10

1 × 10

–3

1 × 10

(b) 1 × 10

(b)

Am-243 (a) 5 × 10

1 × 10

–3

1 × 10

(b) 1 × 10

(b)

Argon (18)

Ar-37 4 × 10

4 × 10

1 × 10

Ar-39 4 × 10

2 × 10

1 × 10

Ar-41 3 × 10

–1

3 × 10

–1

1 × 10

Arsenic (33)

As-72 3 × 10

–1

3 × 10

–1

1 × 10

As-73 4 × 10

4 × 10

1 × 10

As-74 1 × 10

9 × 10

–1

1 × 10

As-76 3 × 10

–1

3 × 10

–1

1 × 10

As-77 2 × 10

7 × 10

–1

1 × 10

Astatine (85)

At-211 (a) 2 × 10

5 × 10

–1

1 × 10

For footnotes see pp. 43–46

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Gold (79)

Au-193 7 × 10

2 × 10

1 × 10

Au-194 1 × 10

1 × 10

Au-195 1 × 10

6 × 10

1 × 10

Au-198 1 × 10

6 × 10

–1

1 × 10

Au-199 1 × 10

6 × 10

–1

1 × 10

Barium (56)

Ba-131 (a) 2 × 10

2 × 10

1 × 10

Ba-133 3 × 10

3 × 10

1 × 10

Ba-133m 2 × 10

6 × 10

–1

1 × 10

Ba-140 (a) 5 × 10

–1

3 × 10

–1

1 × 10

(b) 1 × 10

(b)

Beryllium (4)

Be-7 2 × 10

2 × 10

1 × 10

Be-10 4 × 10

6 × 10

–1

1 × 10

Bismuth (83)

Bi-205 7 × 10

–1

7 × 10

–1

1 × 10

Bi-206 3 × 10

–1

3 × 10

–1

1 × 10

Bi-207 7 × 10

–1

7 × 10

–1

1 × 10

Bi-210 1 × 10

6 × 10

–1

1 × 10

Bi-210m (a) 6 × 10

–1

2 × 10

–2

1 × 10

Bi-212 (a) 7 × 10

–1

6 × 10

–1

1 × 10

(b) 1 × 10

(b)

Berkelium (97)

Bk-247 8 × 10

8 × 10

–4

1 × 10

Bk-249 (a) 4 × 10

3 × 10

–1

1 × 10

Bromine (35)

Br-76 4 × 10

–1

4 × 10

–1

1 × 10

Br-77 3 × 10

3 × 10

1 × 10

Br-82 4 × 10

–1

4 × 10

–1

1 × 10

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

Carbon (6)

C-11 1 × 10

6 × 10

–1

1 × 10

C-14 4 × 10

3 × 10

1 × 10

Calcium (20)

Ca-41 Unlimited Unlimited 1 × 10

1 × 10

Ca-45 4 × 10

1 × 10

Ca-47 (a) 3 × 10

3 × 10

–1

1 × 10

Cadmium (48)

Cd-109 3 × 10

2 × 10

1 × 10

Cd-113m 4 × 10

5 × 10

–1

1 × 10

Cd-115 (a) 3 × 10

4 × 10

–1

1 × 10

Cd-115m 5 × 10

–1

5 × 10

–1

1 × 10

Cerium (58)

Ce-139 7 × 10

2 × 10

1 × 10

Ce-141 2 × 10

6 × 10

–1

1 × 10

Ce-143 9 × 10

–1

6 × 10

–1

1 × 10

Ce-144 (a) 2 × 10

–1

2 × 10

–1

1 × 10

(b) 1 × 10

(b)

Californium (98)

Cf-248 4 × 10

6 × 10

–3

1 × 10

Cf-249 3 × 10

8 × 10

–4

1 × 10

Cf-250 2 × 10

2 × 10

–3

1 × 10

Cf-251 7 × 10

7 × 10

–4

1 × 10

Cf-252 1 × 10

–1

3 × 10

–3

1 × 10

Cf-253 (a) 4 × 10

4 × 10

–2

1 × 10

Cf-254 1 × 10

–3

1 × 10

–3

1 × 10

Chlorine (17)

Cl-36 1 × 10

6 × 10

–1

1 × 10

For footnotes see pp. 43–46

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Cl-38 2 × 10

–1

2 × 10

–1

1 × 10

Curium (96)

Cm-240 4 × 10

2 × 10

–2

1 × 10

Cm-241 2 × 10

1 × 10

Cm-242 4 × 10

1 × 10

–2

1 × 10

Cm-243 9 × 10

1 × 10

–3

1 × 10

Cm-244 2 × 10

2 × 10

–3

1 × 10

Cm-245 9 × 10

9 × 10

–4

1 × 10

Cm-246 9 × 10

9 × 10

–4

1 × 10

Cm-247 (a) 3 × 10

1 × 10

–3

1 × 10

Cm-248 2 × 10

–2

3 × 10

–4

1 × 10

Cobalt (27)

Co-55 5 × 10

–1

5 × 10

–1

1 × 10

Co-56 3 × 10

–1

3 × 10

–1

1 × 10

Co-57 1 × 10

1 × 10

Co-58 1 × 10

1 × 10

Co-58m 4 × 10

4 × 10

1 × 10

Co-60 4 × 10

–1

4 × 10

–1

1 × 10

Chromium (24)

Cr-51 3 × 10

3 × 10

1 × 10

Caesium (55)

Cs-129 4 × 10

4 × 10

1 × 10

Cs-131 3 × 10

3 × 10

1 × 10

Cs-132 1 × 10

1 × 10

Cs-134 7 × 10

–1

7 × 10

–1

1 × 10

Cs-134m 4 × 10

6 × 10

–1

1 × 10

Cs-135 4 × 10

1 × 10

Cs-136 5 × 10

–1

5 × 10

–1

1 × 10

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

Cs-137 (a) 2 × 10

6 × 10

–1

1 × 10

(b) 1 × 10

(b)

Copper (29)

Cu-64 6 × 10

1 × 10

Cu-67 1 × 10

7 × 10

–1

1 × 10

Dysprosium (66)

Dy-159 2 × 10

2 × 10

1 × 10

Dy-165 9 × 10

–1

6 × 10

–1

1 × 10

Dy-166 (a) 9 × 10

–1

3 × 10

–1

1 × 10

Erbium (68)

Er-169 4 × 10

1 × 10

Er-171 8 × 10

–1

5 × 10

–1

1 × 10

Europium (63)

Eu-147 2 × 10

2 × 10

1 × 10

Eu-148 5 × 10

–1

5 × 10

–1

1 × 10

Eu-149 2 × 10

2 × 10

1 × 10

Eu-150 (short lived) 2 × 10

7 × 10

–1

1 × 10

Eu-150 (long lived) 7 × 10

–1

7 × 10

–1

1 × 10

Eu-152 1 × 10

1 × 10

Eu-152m 8 × 10

–1

8 × 10

–1

1 × 10

Eu-154 9 × 10

–1

6 × 10

–1

1 × 10

Eu-155 2 × 10

3 × 10

1 × 10

Eu-156 7 × 10

–1

7 × 10

–1

1 × 10

Fluorine (9)

F-18 1 × 10

6 × 10

–1

1 × 10

Iron (26)

Fe-52 (a) 3 × 10

–1

3 × 10

–1

1 × 10

Fe-55 4 × 10

4 × 10

1 × 10

For footnotes see pp. 43–46

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Fe-59 9 × 10

–1

9 × 10

–1

1 × 10

Fe-60 (a) 4 × 10

2 × 10

–1

1 × 10

Gallium (31)

Ga-67 7 × 10

3 × 10

1 × 10

Ga-68 5 × 10

–1

5 × 10

–1

1 × 10

Ga-72 4 × 10

–1

4 × 10

–1

1 × 10

Gadolinium (64)

Gd-146 (a) 5 × 10

–1

5 × 10

–1

1 × 10

Gd-148 2 × 10

2 × 10

–3

1 × 10

Gd-153 1 × 10

9 × 10

1 × 10

Gd-159 3 × 10

6 × 10

–1

1 × 10

Germanium (32)

Ge-68 (a) 5 × 10

–1

5 × 10

–1

1 × 10

Ge-71 4 × 10

4 × 10

1 × 10

Ge-77 3 × 10

–1

3 × 10

–1

1 × 10

Hafnium (72)

Hf-172 (a) 6 × 10

–1

6 × 10

–1

1 × 10

Hf-175 3 × 10

3 × 10

1 × 10

Hf-181 2 × 10

5 × 10

–1

1 × 10

Hf-182 Unlimited Unlimited 1 × 10

1 × 10

Mercury (80)

Hg-194 (a) 1 × 10

1 × 10

Hg-195m (a) 3 × 10

7 × 10

–1

1 × 10

Hg-197 2 × 10

1 × 10

Hg-197m 1 × 10

4 × 10

–1

1 × 10

Hg-203 5 × 10

1 × 10

Holmium (67)

Ho-166 4 × 10

–1

4 × 10

–1

1 × 10

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

Ho-166m 6 × 10

–1

5 × 10

–1

1 × 10

Iodine (53)

I-123 6 × 10

3 × 10

1 × 10

I-124 1 × 10

1 × 10

I-125 2 × 10

3 × 10

1 × 10

I-126 2 × 10

1 × 10

I-129 Unlimited Unlimited 1 × 10

1 × 10

I-131 3 × 10

7 × 10

–1

1 × 10

I-132 4 × 10

–1

4 × 10

–1

1 × 10

I-133 7 × 10

–1

6 × 10

–1

1 × 10

I-134 3 × 10

–1

3 × 10

–1

1 × 10

I-135 (a) 6 × 10

–1

6 × 10

–1

1 × 10

Indium (49)

In-111 3 × 10

3 × 10

1 × 10

In-113m 4 × 10

2 × 10

1 × 10

In-114m (a) 1 × 10

5 × 10

–1

1 × 10

In-115m 7 × 10

1 × 10

Iridium (77)

Ir-189 (a) 1 × 10

1 × 10

Ir-190 7 × 10

–1

7 × 10

–1

1 × 10

Ir-192 1 × 10

–1

1 × 10

Ir-194 3 × 10

–1

3 × 10

–1

1 × 10

Potassium (19)

K-40 9 × 10

–1

9 × 10

–1

1 × 10

K-42 2 × 10

–1

2 × 10

–1

1 × 10

K-43 7 × 10

–1

6 × 10

–1

1 × 10

For footnotes see pp. 43–46

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Krypton (36)

Kr-79 4 × 10

2 × 10

1 × 10

Kr-81 4 × 10

4 × 10

1 × 10

Kr-85 1 × 10

1 × 10

Kr-85m 8 × 10

3 × 10

1 × 10

Kr-87 2 × 10

–1

2 × 10

–1

1 × 10

Lanthanum (57)

La-137 3 × 10

6 × 10

1 × 10

La-140 4 × 10

–1

4 × 10

–1

1 × 10

Lutetium (71)

Lu-172 6 × 10

–1

6 × 10

–1

1 × 10

Lu-173 8 × 10

8 × 10

1 × 10

Lu-174 9 × 10

9 × 10

1 × 10

Lu-174m 2 × 10

1 × 10

Lu-177 3 × 10

7 × 10

–1

1 × 10

Magnesium (12)

Mg-28 (a) 3 × 10

–1

3 × 10

–1

1 × 10

Manganese (25)

Mn-52 3 × 10

–1

3 × 10

–1

1 × 10

Mn-53 Unlimited Unlimited 1 × 10

1 × 10

Mn-54 1 × 10

1 × 10

Mn-56 3 × 10

–1

3 × 10

–1

1 × 10

Molybdenum (42)

Mo-93 4 × 10

2 × 10

1 × 10

Mo-99 (a) 1 × 10

6 × 10

–1

1 × 10

Nitrogen (7)

N-13 9 × 10

–1

6 × 10

–1

1 × 10

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

Sodium (11)

Na-22 5 × 10

–1

5 × 10

–1

1 × 10

Na-24 2 × 10

–1

2 × 10

–1

1 × 10

Niobium (41)

Nb-93m 4 × 10

3 × 10

1 × 10

Nb-94 7 × 10

–1

7 × 10

–1

1 × 10

Nb-95 1 × 10

1 × 10

Nb-97 9 × 10

–1

6 × 10

–1

1 × 10

Neodymium (60)

Nd-147 6 × 10

6 × 10

–1

1 × 10

Nd-149 6 × 10

–1

5 × 10

–1

1 × 10

Nickel (28)

Ni-59 Unlimited Unlimited 1 × 10

1 × 10

Ni-63 4 × 10

3 × 10

1 × 10

Ni-65 4 × 10

–1

4 × 10

–1

1 × 10

Neptunium (93)

Np-235 4 × 10

4 × 10

1 × 10

Np-236 (short lived) 2 × 10

2 × 10

1 × 10

Np-236 (long lived) 9 × 10

2 × 10

–2

1 × 10

Np-237 2 × 10

2 × 10

–3

1 × 10

(b) 1 × 10

(b)

Np-239 7 × 10

4 × 10

–1

1 × 10

Osmium (76)

Os-185 1 × 10

1 × 10

Os-191 1 × 10

2 × 10

1 × 10

Os-191m 4 × 10

3 × 10

1 × 10

Os-193 2 × 10

6 × 10

–1

1 × 10

Os-194 (a) 3 × 10

–1

3 × 10

–1

1 × 10

For footnotes see pp. 43–46

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Phosphorus (15)

P-32 5 × 10

–1

5 × 10

–1

1 × 10

P-33 4 × 10

1 × 10

Protactinium (91)

Pa-230 (a) 2 × 10

7 × 10

–2

1 × 10

Pa-231 4 × 10

4 × 10

–4

1 × 10

Pa-233 5 × 10

7 × 10

–1

1 × 10

Lead (82)

Pb-201 1 × 10

1 × 10

Pb-202 4 × 10

2 × 10

1 × 10

Pb-203 4 × 10

3 × 10

1 × 10

Pb-205 Unlimited Unlimited 1 × 10

1 × 10

Pb-210 (a) 1 × 10

5 × 10

–2

1 × 10

(b) 1 × 10

(b)

Pb-212 (a) 7 × 10

–1

2 × 10

–1

1 × 10

(b) 1 × 10

(b)

Palladium (46)

Pd-103 (a) 4 × 10

4 × 10

1 × 10

Pd-107 Unlimited Unlimited 1 × 10

1 × 10

Pd-109 2 × 10

5 × 10

–1

1 × 10

Promethium (61)

Pm-143 3 × 10

3 × 10

1 × 10

Pm-144 7 × 10

–1

7 × 10

–1

1 × 10

Pm-145 3 × 10

1 × 10

Pm-147 4 × 10

2 × 10

1 × 10

Pm-148m (a) 8 × 10

–1

7 × 10

–1

1 × 10

Pm-149 2 × 10

6 × 10

–1

1 × 10

Pm-151 2 × 10

6 × 10

–1

1 × 10

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

Polonium (84)

Po-210 4 × 10

2 × 10

–2

1 × 10

Praseodymium (59)

Pr-142 4 × 10

–1

4 × 10

–1

1 × 10

Pr-143 3 × 10

6 × 10

–1

1 × 10

Platinum (78)

Pt-188 (a) 1 × 10

8 × 10

–1

1 × 10

Pt-191 4 × 10

3 × 10

1 × 10

Pt-193 4 × 10

4 × 10

1 × 10

Pt-193m 4 × 10

5 × 10

–1

1 × 10

Pt-195m 1 × 10

5 × 10

–1

1 × 10

Pt-197 2 × 10

6 × 10

–1

1 × 10

Pt-197m 1 × 10

6 × 10

–1

1 × 10

Plutonium (94)

Pu-236 3 × 10

3 × 10

–3

1 × 10

Pu-237 2 × 10

2 × 10

1 × 10

Pu-238 1 × 10

1 × 10

–3

1 × 10

Pu-239 1 × 10

1 × 10

–3

1 × 10

Pu-240 1 × 10

1 × 10

–3

1 × 10

Pu-241 (a) 4 × 10

6 × 10

–2

1 × 10

Pu-242 1 × 10

1 × 10

–3

1 × 10

Pu-244 (a) 4 × 10

–1

1 × 10

–3

1 × 10

Radium (88)

Ra-223 (a) 4 × 10

–1

7 × 10

–3

1 × 10

(b) 1 × 10

(b)

Ra-224 (a) 4 × 10

–1

2 × 10

–2

1 × 10

(b) 1 × 10

(b)

Ra-225 (a) 2 × 10

–1

4 × 10

–3

1 × 10

For footnotes see pp. 43–46

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Ra-226 (a) 2 × 10

–1

3 × 10

–3

1 × 10

(b) 1 × 10

(b)

Ra-228 (a) 6 × 10

–1

2 × 10

–2

1 × 10

(b) 1 × 10

(b)

Rubidium (37)

Rb-81 2 × 10

8 × 10

–1

1 × 10

Rb-83 (a) 2 × 10

2 × 10

1 × 10

Rb-84 1 × 10

1 × 10

Rb-86 5 × 10

–1

5 × 10

–1

1 × 10

Rb-87 Unlimited Unlimited 1 × 10

1 × 10

Rb (natural) Unlimited Unlimited 1 × 10

1 × 10

Rhenium (75)

Re-184 1 × 10

1 × 10

Re-184m 3 × 10

1 × 10

Re-186 2 × 10

6 × 10

–1

1 × 10

Re-187 Unlimited Unlimited 1 × 10

1 × 10

Re-188 4 × 10

–1

4 × 10

–1

1 × 10

Re-189 (a) 3 × 10

6 × 10

–1

1 × 10

Re (natural) Unlimited Unlimited 1 × 10

1 × 10

Rhodium (45)

Rh-99 2 × 10

2 × 10

1 × 10

Rh-101 4 × 10

3 × 10

1 × 10

Rh-102 5 × 10

–1

5 × 10

–1

1 × 10

Rh-102m 2 × 10

2 × 10

1 × 10

Rh-103m 4 × 10

4 × 10

1 × 10

Rh-105 1 × 10

8 × 10

–1

1 × 10

Radon (86)

Rn-222 (a) 3 × 10

–1

4 × 10

–3

1 × 10

(b) 1 × 10

(b)

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

Ruthenium (44)

Ru-97 5 × 10

5 × 10

1 × 10

Ru-103 (a) 2 × 10

2 × 10

1 × 10

Ru-105 1 × 10

6 × 10

–1

1 × 10

Ru-106 (a) 2 × 10

–1

2 × 10

–1

1 × 10

(b) 1 × 10

(b)

Sulphur (16)

S-35 4 × 10

3 × 10

1 × 10

Antimony (51)

Sb-122 4 × 10

–1

4 × 10

–1

1 × 10

Sb-124 6 × 10

–1

6 × 10

–1

1 × 10

Sb-125 2 × 10

1 × 10

Sb-126 4 × 10

–1

4 × 10

–1

1 × 10

Scandium (21)

Sc-44 5 × 10

–1

5 × 10

–1

1 × 10

Sc-46 5 × 10

–1

5 × 10

–1

1 × 10

Sc-47 1 × 10

7 × 10

–1

1 × 10

Sc-48 3 × 10

–1

3 × 10

–1

1 × 10

Selenium (34)

Se-75 3 × 10

3 × 10

1 × 10

Se-79 4 × 10

2 × 10

1 × 10

Silicon (14)

Si-31 6 × 10

–1

6 × 10

–1

1 × 10

Si-32 4 × 10

5 × 10

–1

1 × 10

Samarium (62)

Sm-145 1 × 10

1 × 10

Sm-147 Unlimited Unlimited 1 × 10

1 × 10

For footnotes see pp. 43–46

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Sm-151 4 × 10

1 × 10

Sm-153 9 × 10

6 × 10

–1

1 × 10

Tin (50)

Sn-113 (a) 4 × 10

2 × 10

1 × 10

Sn-117m 7 × 10

4 × 10

–1

1 × 10

Sn-119m 4 × 10

3 × 10

1 × 10

Sn-121m (a) 4 × 10

9 × 10

–1

1 × 10

Sn-123 8 × 10

–1

6 × 10

–1

1 × 10

Sn-125 4 × 10

–1

4 × 10

–1

1 × 10

Sn-126 (a) 6 × 10

–1

4 × 10

–1

1 × 10

Strontium (38)

Sr-82 (a) 2 × 10

–1

2 × 10

–1

1 × 10

Sr-85 2 × 10

2 × 10

1 × 10

Sr-85m 5 × 10

5 × 10

1 × 10

Sr-87m 3 × 10

3 × 10

1 × 10

Sr-89 6 × 10

–1

6 × 10

–1

1 × 10

Sr-90 (a) 3 × 10

–1

3 × 10

–1

1 × 10

(b) 1 × 10

(b)

Sr-91 (a) 3 × 10

–1

3 × 10

–1

1 × 10

Sr-92 (a) 1 × 10

3 × 10

–1

1 × 10

Tritium (1)

T(H-3) 4 × 10

4 × 10

1 × 10

Tantalum (73)

Ta-178 (long lived) 1 × 10

8 × 10

–1

1 × 10

Ta-179 3 × 10

3 × 10

1 × 10

Ta-182 9 × 10

–1

5 × 10

–1

1 × 10

Terbium (65)

Tb-157 4 × 10

4 × 10

1 × 10

Tb-158 1 × 10

1 × 10

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

Tb-160 1 × 10

6 × 10

–1

1 × 10

Technetium (43)

Tc-95m (a) 2 × 10

2 × 10

1 × 10

Tc-96 4 × 10

–1

4 × 10

–1

1 × 10

Tc-96m (a) 4 × 10

–1

4 × 10

–1

1 × 10

Tc-97 Unlimited Unlimited 1 × 10

1 × 10

Tc-97m 4 × 10

1 × 10

Tc-98 8 × 10

–1

7 × 10

–1

1 × 10

Tc-99 4 × 10

9 × 10

–1

1 × 10

Tc-99m 1 × 10

4 × 10

1 × 10

Tellurium (52)

Te-121 2 × 10

2 × 10

1 × 10

Te-121m 5 × 10

3 × 10

1 × 10

Te-123m 8 × 10

1 × 10

Te-125m 2 × 10

9 × 10

–1

1 × 10

Te-127 2 × 10

7 × 10

–1

1 × 10

Te-127m (a) 2 × 10

5 × 10

–1

1 × 10

Te-129 7 × 10

–1

6 × 10

–1

1 × 10

Te-129m (a) 8 × 10

–1

4 × 10

–1

1 × 10

Te-131m (a) 7 × 10

–1

5 × 10

–1

1 × 10

Te-132 (a) 5 × 10

–1

4 × 10

–1

1 × 10

Thorium (90)

Th-227 1 × 10

5 × 10

–3

1 × 10

Th-228 (a) 5 × 10

–1

1 × 10

–3

1 × 10

(b) 1 × 10

(b)

Th-229 5 × 10

5 × 10

–4

1 × 10

(b) 1 × 10

(b)

Th-230 1 × 10

1 × 10

–3

1 × 10

Th-231 4 × 10

2 × 10

–2

1 × 10

For footnotes see pp. 43–46

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Th-232

Unlimited Unlimited 1 × 10

1 × 10

Th-234 (a) 3 × 10

–1

3 × 10

–1

1 × 10

(b) 1 × 10

(b)

Th (natural) Unlimited Unlimited 1 × 10

(b) 1 × 10

(b)

Titanium (22)

Ti-44 (a) 5 × 10

–1

4 × 10

–1

1 × 10

Thallium (81)

Tl-200 9 × 10

–1

9 × 10

–1

1 × 10

Tl-201 1 × 10

4 × 10

1 × 10

Tl-202 2 × 10

2 × 10

1 × 10

Tl-204 1 × 10

7 × 10

–1

1 × 10

Thulium (69)

Tm-167 7 × 10

8 × 10

–1

1 × 10

Tm-170 3 × 10

6 × 10

–1

1 × 10

Tm-171 4 × 10

4 × 10

1 × 10

Uranium (92)

U-230 (fast lung

absorption) (a)(d)

4 × 10

1 × 10

–1

1 × 10

(b) 1 × 10

(b)

U-230 (medium lung

absorption) (a)(e)

4 × 10

–3

1 × 10

U-230 (slow lung

absorption) (a)(f)

3 × 10

–3

1 × 10

U-232 (fast lung

absorption) (d)

4 × 10

1 × 10

–2

1 × 10

(b) 1 × 10

(b)

U-232 (medium lung

absorption) (e)

4 × 10

7 × 10

–3

1 × 10

U-232 (slow lung

absorption) (f)

1 × 10

–3

1 × 10

U-233 (fast lung

absorption) (d)

4 × 10

9 × 10

–2

1 × 10

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

U-233 (medium lung

absorption) (e)

4 × 10

2 × 10

–2

1 × 10

U-233 (slow lung

absorption) (f)

4 × 10

6 × 10

–3

1 × 10

U-234 (fast lung

absorption) (d)

4 × 10

9 × 10

–2

1 × 10

U-234 (medium lung

absorption) (e)

4 × 10

2 × 10

–2

1 × 10

U-234 (slow lung

absorption) (f)

4 × 10

6 × 10

–3

1 × 10

U-235 (all lung absorption

types) (a)(d)(e)(f)

Unlimited Unlimited 1 × 10

(b) 1 × 10

(b)

U-236 (fast lung

absorption) (d)

Unlimited Unlimited 1 × 10

1 × 10

U-236 (medium lung

absorption) (e)

4 × 10

2 × 10

–2

1 × 10

U-236 (slow lung

absorption) (f)

4 × 10

6 × 10

–3

1 × 10

U-238 (all lung absorption

types) (d)(e)(f)

Unlimited Unlimited 1 × 10

(b) 1 × 10

(b)

U (natural) Unlimited Unlimited 1 × 10

(b) 1 × 10

(b)

U (enriched to 20% or

less) (g)

Unlimited Unlimited 1 × 10

1 × 10

U (depleted) Unlimited Unlimited 1 × 10

1 × 10

Vanadium (23)

V-48 4 × 10

–1

4 × 10

–1

1 × 10

V-49 4 × 10

4 × 10

1 × 10

For footnotes see pp. 43–46

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Tungsten (74)

W-178 (a) 9 × 10

5 × 10

1 × 10

W-181 3 × 10

3 × 10

1 × 10

W-185 4 × 10

8 × 10

–1

1 × 10

W-187 2 × 10

6 × 10

–1

1 × 10

W-188 (a) 4 × 10

–1

3 × 10

–1

1 × 10

Xenon (54)

Xe-122 (a) 4 × 10

–1

4 × 10

–1

1 × 10

Xe-123 2 × 10

7 × 10

–1

1 × 10

Xe-127 4 × 10

2 × 10

1 × 10

Xe-131m 4 × 10

4 × 10

1 × 10

Xe-133 2 × 10

1 × 10

Xe-135 3 × 10

2 × 10

1 × 10

Yttrium (39)

Y-87 (a) 1 × 10

1 × 10

Y-88 4 × 10

–1

4 × 10

–1

1 × 10

Y-90 3 × 10

–1

3 × 10

–1

1 × 10

Y-91 6 × 10

–1

6 × 10

–1

1 × 10

Y-91m 2 × 10

2 × 10

1 × 10

Y-92 2 × 10

–1

2 × 10

–1

1 × 10

Y-93 3 × 10

–1

3 × 10

–1

1 × 10

Ytterbium (70)

Yb-169 4 × 10

1 × 10

Yb-175 3 × 10

9 × 10

–1

1 × 10

Zinc (30)

Zn-65 2 × 10

2 × 10

1 × 10

Zn-69 3 × 10

6 × 10

–1

1 × 10

Zn-69m (a) 3 × 10

6 × 10

–1

1 × 10

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

(a) A

and/or A

values for these parent radionuclides include contributions from their

progeny with half-lives less than 10 days, as listed in the following:

Mg-28 Al-28

Ar-42 K-42

Ca-47 Sc-47

Ti-44 Sc-44

Fe-52 Mn-52m

Fe-60 Co-60m

Zn-69m Zn-69

Ge-68 Ga-68

Rb-83 Kr-83m

Sr-82 Rb-82

Sr-90 Y-90

Sr-91 Y-91m

Sr-92 Y-92

Y-87 Sr-87m

Zr-95 Nb-95m

Zr-97 Nb-97m, Nb-97

Mo-99 Tc-99m

Tc-95m Tc-95

Tc-96m Tc-96

Ru-103 Rh-103m

Ru-106 Rh-106

Pd-103 Rh-103m

Ag-108m Ag-108

Ag-110m Ag-110

Cd-115 In-115m

In-114m In-114

Zirconium (40)

Zr-88 3 × 10

3 × 10

1 × 10

Zr-93 Unlimited Unlimited 1 × 10

(b) 1 × 10

(b)

Zr-95 (a) 2 × 10

8 × 10

–1

1 × 10

Zr-97 (a) 4 × 10

–1

4 × 10

–1

1 × 10

(b) 1 × 10

(b)

TABLE 2. BASIC RADIONUCLIDE VALUES (cont.)

Radionuclide

(atomic number)

Activity

concentration

limit for

exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

Table 2, footnote (a) (cont.)

Sn-113 In-113m

Sn-121m Sn-121

Sn-126 Sb-126m

Te-118 Sb-118

Te-127m Te-127

Te-129m Te-129

Te-131m Te-131

Te-132 I-132

I-135 Xe-135m

Xe-122 I-122

Cs-137 Ba-137m

Ba-131 Cs-131

Ba-140 La-140

Ce-144 Pr-144m, Pr-144

Pm-148m Pm-148

Gd-146 Eu-146

Dy-166 Ho-166

Hf-172 Lu-172

W-178 Ta-178

W-188 Re-188

Re-189 Os-189m

Os-194 Ir-194

Ir-189 Os-189m

Pt-188 Ir-188

Hg-194 Au-194

Hg-195m Hg-195

Pb-210 Bi-210

Pb-212 Bi-212, Tl-208, Po-212

Bi-210m Tl-206

Bi-212 Tl-208, Po-212

At-211 Po-211

Rn-222 Po-218, Pb-214, At-218, Bi-214, Po-214

Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Po-211, Tl-207

Ra-224 Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212

Ra-225 Ac-225, Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209

Ra-226 Rn-222, Po-218, Pb-214, At-218, Bi-214, Po-214

Ra-228 Ac-228

Ac-225 Fr-221, At-217, Bi-213, Tl-209, Po-213, Pb-209

Ac-227 Fr-223

Th-228 Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208, Po-212

Th-234 Pa-234m, Pa-234

Pa-230 Ac-226, Th-226, Fr-222, Ra-222, Rn-218, Po-214

U-230 Th-226, Ra-222, Rn-218, Po-214

U-235 Th-231

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

Table 2, footnote (a) (cont.)

Pu-241 U-237

Pu-244 U-240, Np-240m

Am-242m Am-242, Np-238

Am-243 Np-239

Cm-247 Pu-243

Bk-249 Am-245

Cf-253 Cm-249

(b) Parent nuclides and their progeny included in secular equilibrium are listed in the

following:

Sr-90 Y-90

Zr-93 Nb-93m

Zr-97 Nb-97

Ru-106 Rh-106

Ag-108m Ag-108

Cs-137 Ba-137m

Ce-144 Pr-144

Ba-140 La-140

Bi-212 Tl-208 (0.36), Po-212 (0.64)

Pb-210 Bi-210, Po-210

Pb-212 Bi-212, Tl-208 (0.36), Po-212 (0.64)

Rn-222 Po-218, Pb-214, Bi-214, Po-214

Ra-223 Rn-219, Po-215, Pb-211, Bi-211, Tl-207

Ra-224 Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)

Ra-226 Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210

Ra-228 Ac-228

Th-228 Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)

Th-229 Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209

Th-natural Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208

(0.36), Po-212 (0.64)

Th-234 Pa-234m

U-230 Th-226, Ra-222, Rn-218, Po-214

U-232 Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212

(0.64)

U-235 Th-231

U-238 Th-234, Pa-234m

U-natural Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214,

Bi-214, Po-214, Pb-210, Bi-210, Po-210

Np-237 Pa-233

Am-242m Am-242

Am-243 Np-239

measurement of the radiation level at a prescribed distance from the source.

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

(d) These values apply only to compounds of uranium that take the chemical form of UF

and UO

(NO

)

in both normal and accident conditions of transport.

(e) These values apply only to compounds of uranium that take the chemical form of UO

, UCl

and hexavalent compounds in both normal and accident conditions of

transport.

(f) These values apply to all compounds of uranium other than those specified in (d) and (e)

above.

(g) These values apply to unirradiated uranium only.

406. When the identity of each radionuclide is known but the individual

activities of some of the radionuclides are not known, the radionuclides may be

grouped and the lowest radionuclide value, as appropriate for the radionuclides in

each group, may be used in applying the formulas in paras 405 and 430. Groups

may be based on the total alpha activity and the total beta/gamma activity when

these are known, using the lowest radionuclide values for the alpha emitters or

beta/gamma emitters, respectively.

407. For individual radionuclides or for mixtures of radionuclides for which

relevant data are not available, the values shown in Table 3 shall be used.

TABLE 3. BASIC RADIONUCLIDE VALUES FOR UNKNOWN

RADIONUCLIDES OR MIXTURES

Radioactive content A

Activity

concentration

limit for exempt

material

Activity

limit for

an exempt

consignment

(TBq) (TBq) (Bq/g) (Bq)

Only beta or gamma emitting

nuclides are known to be present

0.1 0.02 1 × 10

1 × 10

Alpha emitting nuclides,

but no neutron emitters are

known to be present

0.2 9 × 10

–5

1 × 10

–1

1 × 10

Neutron emitting nuclides are

known to be present or no

relevant data are available

0.001 9 × 10

–5

1 × 10

–1

1 × 10

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

CLASSIFICATION OF MATERIAL

Low specific activity material

408. Radioactive material may only be classified as LSA material if the

conditions of paras 226, 409–411 and 517–522 are met.

409. LSA material shall be in one of three groups:

(a) LSA-I:

(i) Uranium and thorium ores and concentrates of such ores, and other

ores containing naturally occurring radionuclides.

(ii) Natural uranium, depleted uranium, natural thorium or their

compounds or mixtures, that are unirradiated and in solid or liquid

form.

(iii) Radioactive material for which the A

value is unlimited. Fissile

material may be included only if excepted under para. 417.

(iv) Other radioactive material in which the activity is distributed

throughout and the estimated average specific activity does not exceed

30 times the values for the activity concentration specified in paras

402–407. Fissile material may be included only if excepted under

para. 417.

(b) LSA-II:

(i) Water with a tritium concentration of up to 0.8 TBq/L;

(ii) Other material in which the activity is distributed throughout and the

estimated average specific activity does not exceed 10

–4

/g for solids

and gases, and 10

–5

/g for liquids.

Solids (e.g. consolidated wastes, activated materials), excluding powders,

that meet the requirements of para. 601, in which:

(i) The radioactive material is distributed throughout a solid or a

collection of solid objects, or is essentially uniformly distributed in a

solid compact binding agent (such as concrete, bitumen and ceramic).

(ii) The radioactive material is relatively insoluble, or is intrinsically

contained in a relatively insoluble matrix, so that, even under loss of

packaging, the loss of radioactive material per package by leaching

when placed in water for 7 days would not exceed 0.1A

(iii) The estimated average specific activity of the solid, excluding any

shielding material, does not exceed 2 × 10

–3

/g.

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

410. A single package of non-combustible solid LSA-II or LSA-III material, if

carried by air, shall not contain an activity greater than 3000A

411. The radioactive contents in a single package of LSA material shall be so

restricted that the radiation level specified in para. 517 shall not be exceeded, and

the activity in a single package shall also be so restricted that the activity limits

for a conveyance specified in para. 522 shall not be exceeded.

Surface contaminated object

412. Radioactive material may be classified as SCO if the conditions in

paras 241, 413, 414 and 517– 522 are met.

413. SCO shall be in one of two groups:

(a) SCO-I: A solid object on which:

(i) The non-fixed contamination on the accessible surface averaged over

300 cm

(or the area of the surface if less than 300 cm

) does not

exceed 4 Bq/cm

for beta and gamma emitters and low toxicity alpha

emitters, or 0.4 Bq/cm

for all other alpha emitters.

(ii) The fixed contamination on the accessible surface averaged over

300 cm

(or the area of the surface if less than 300 cm

) does not

exceed 4 × 10

Bq/cm

for beta and gamma emitters and low toxicity

alpha emitters, or 4000 Bq/cm

for all other alpha emitters.

(iii) The non-fixed contamination plus the fixed contamination on the

inaccessible surface averaged over 300 cm

(or the area of the surface

if less than 300 cm

) does not exceed 4 × 10

Bq/cm

for beta and

gamma emitters and low toxicity alpha emitters, or 4000 Bq/cm

for

all other alpha emitters.

(b) SCO-II: A solid object on which either the fixed or non-fixed contamination

on the surface exceeds the applicable limits specified for SCO-I in (a) above

and on which:

(i) The non-fixed contamination on the accessible surface averaged over

300 cm

(or the area of the surface if less than 300 cm

) does not

exceed 400 Bq/cm

for beta and gamma emitters and low toxicity

alpha emitters, or 40 Bq/cm

for all other alpha emitters.

(ii) The fixed contamination on the accessible surface averaged over

300 cm

(or the area of the surface if less than 300 cm

) does not

exceed 8 × 10

Bq/cm

for beta and gamma emitters and low toxicity

alpha emitters, or 8 × 10

Bq/cm

for all other alpha emitters.

This publication has been superseded by SSR-6 (Rev. 1).

ACTIVITY LIMITS AND CLASSIFICATION

(iii) The non-fixed contamination plus the fixed contamination on the

inaccessible surface averaged over 300 cm

(or the area of the surface

if less than 300 cm

) does not exceed 8 × 10

Bq/cm

for beta and

gamma emitters and low toxicity alpha emitters, or 8 × 10

Bq/cm

for

all other alpha emitters.

414. The radioactive contents in a single package of SCO shall be so restricted

that the radiation level specified in para. 517 shall not be exceeded, and the

activity in a single package shall also be so restricted that the activity limits for a

conveyance specified in para. 522 shall not be exceeded.

Special form radioactive material

415. Radioactive material may be classified as special form radioactive material

only if it meets the requirements of paras 602–604 and 802.

Low dispersible radioactive material

416. Radioactive material may be classified as low dispersible radioactive

material only if it meets the requirements of para. 605, taking into account the

requirements of paras 665 and 802.

Fissile material

417. Fissile material and packages containing fissile material shall be classified

under the relevant entry as “FISSILE”,