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This publication has been superseded by SSR-6 (Rev. 1).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”, in accordance with Table 1 unless

excepted by one of the provisions of subparagraphs (a)–(f) of this paragraph and

transported subject to the requirements of para. 570. All provisions apply only to

material in packages that meets the requirements of para. 636, unless unpackaged

material is specifically allowed in the provision:

(a) Uranium enriched in uranium-235 to a maximum of 1% by mass, and with

a total plutonium and uranium-233 content not exceeding 1% of the mass of

uranium-235, provided that the fissile nuclides are distributed essentially

homogeneously throughout the material. In addition, if uranium-235 is

present in metallic, oxide or carbide forms, it shall not form a lattice

arrangement.

(b) Liquid solutions of uranyl nitrate enriched in uranium-235 to a maximum of

2% by mass, with a total plutonium and uranium-233 content not exceeding

0.002% of the mass of uranium, and with a minimum nitrogen to uranium

atomic ratio (N/U) of 2.

This publication has been superseded by SSR-6 (Rev. 1).

SECTION IV

235 provided:

(i) There is no more than 3.5 g of uranium-235 per package.

(ii) The total plutonium and uranium-233 content does not exceed 1% of

the mass of uranium-235 per package.

(iii) Transport of the package is subject to the consignment limit provided

in para. 570(c).

(d) Fissile nuclides with a total mass not greater than 2.0 g per package,

provided the package is transported subject to the consignment limit

provided in para. 570(d).

(e) Fissile nuclides with a total mass not greater than 45 g, either packaged or

unpackaged, subject to the limits provided in para. 570(e).

(f) A fissile material that meets the requirements of paras 570(b), 606 and 802.

418. The contents of packages containing fissile material shall be as specified

for the package design, either directly in these Regulations or in the certificate of

approval.

Uranium hexafluoride

419. Uranium hexafluoride shall be assigned to one of the following UN

numbers only:

(a) UN 2977, RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE,

FISSILE;

(b) UN 2978, RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE,

non-fissile or fissile-excepted;

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

fissile-excepted.

420. The contents of a package containing uranium hexafluoride shall comply

with the following requirements:

(a) The mass of uranium hexafluoride shall not be different from that allowed

for the package design.

(b) The mass of uranium hexafluoride shall not be greater than a value that

would lead to an ullage of less than 5% at the maximum temperature of the

package, as specified for the plant systems where the package might be

used.

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

ACTIVITY LIMITS AND CLASSIFICATION

shall not be above atmospheric pressure when presented for transport.

CLASSIFICATION OF PACKAGES

421. The quantity of radioactive material in a package shall not exceed the

relevant limits for the package type as specified below.

Classification as excepted package

422. A package may be classified as an excepted package if it meets one of the

following conditions:

(a) It is an empty package having contained radioactive material;

(b) It contains instruments or articles not exceeding the activity limits specified

in Table 4;

natural thorium;

(d) It contains radioactive material not exceeding the activity limits specified

in Table 4;

(e) It contains less than 0.1 kg of uranium hexafluoride not exceeding the

activity limits specified in column 4 of Table 4.

TABLE 4. ACTIVITY LIMITS FOR EXCEPTED PACKAGES

Physical state

of contents

Instrument or article Materials

Item limits

Package limits

Solids:

Special form 10

–2

–3

Other forms 10

–2

–3

Liquids 10

–3

–1

–4

Gases:

Tritium 2 × 10

–2

2 × 10

–1

2 × 10

–2

Special form 10

–3

–2

–3

Other forms 10

–3

–2

–3

For mixtures of radionuclides, see paras 405–407.

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

SECTION IV

423. Radioactive material that is enclosed in or is included as a component part

of an instrument or other manufactured article, may be classified under UN 2911,

RADIOACTIVE MATERIAL, EXCEPTED PACKAGE — INSTRUMENTS or

ARTICLES, provided that:

(a) The radiation level at 10 cm from any point on the external surface of any

unpackaged instrument or article is not greater than 0.1 mSv/h.

(b) Each instrument or article bears the marking “RADIOACTIVE” on its

external surface except for the following:

(i) Radioluminescent timepieces or devices do not require markings.

(ii) Consumer products that have either received regulatory approval in

accordance with para. 107(e) or do not individually exceed the

activity limit for an exempt consignment in Table 2 (column 5) do not

require markings, provided that such products are transported in a

package that bears the marking “RADIOACTIVE” on its internal

surface in such a manner that a warning of the presence of radioactive

material is visible on opening the package.

(iii) Other instruments or articles too small to bear the marking

“RADIOACTIVE” do not require markings, provided that they are

transported in a package that bears the marking “RADIOACTIVE”

on its internal surface in such a manner that a warning of the presence

of radioactive material is visible on opening the package.

(a device performing the sole function of containing radioactive material

shall not be considered to be an instrument or manufactured article).

(d) The limits specified in columns 2 and 3 of Table 4 are met for each

individual item and each package, respectively.

(e) For transport by post, the total activity in each excepted package shall not

exceed one tenth of the relevant limits specified in column 3 of Table 4.

424. Radioactive material in forms other than as specified in para. 423 and with

an activity not exceeding the limits specified in column 4 of Table 4 may be

classified under UN 2910, RADIOACTIVE MATERIAL, EXCEPTED

PACKAGE — LIMITED QUANTITY OF MATERIAL, provided that:

(a) The package retains its radioactive contents under routine conditions of

transport.

(b) The package bears the marking “RADIOACTIVE” on either:

(i) An internal surface in such a manner that a warning of the presence of

radioactive material is visible on opening the package; or

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

ACTIVITY LIMITS AND CLASSIFICATION

(ii) The outside of the package, where it is impractical to mark an internal

surface.

exceed one tenth of the relevant limits specified in column 4 of Table 4.

425. Uranium hexafluoride not exceeding the limits specified in column 4 of

Table 4 may be classified under UN 3507 URANIUM HEXAFLUORIDE,

RADIOACTIVE MATERIAL, EXCEPTED PACKAGE, less than 0.1 kg per

package, non-fissile or fissile-excepted, provided that:

(a) The mass of uranium hexafluoride in the package is less than 0.1 kg.

(b) The conditions of paras 420, 424(a) and 424(b) are met.

426. Articles manufactured of natural uranium, depleted uranium or natural

thorium and articles in which the sole radioactive material is unirradiated natural

uranium, unirradiated depleted uranium or unirradiated natural thorium may be

classified under UN 2909, RADIOACTIVE MATERIAL, EXCEPTED

PACKAGE — ARTICLES MANUFACTURED FROM NATURAL URANIUM

or DEPLETED URANIUM or NATURAL THORIUM, provided that the outer

surface of the uranium or thorium is enclosed in an inactive sheath made of metal

or some other substantial material.

Additional requirements and controls for transport of empty packagings

427. An empty packaging that had previously contained radioactive material

may be classified under UN 2908, RADIOACTIVE MATERIAL, EXCEPTED

PACKAGE — EMPTY PACKAGING, provided that:

(a) It is in a well-maintained condition and securely closed.

(b) The outer surface of any uranium or thorium in its structure is covered with

an inactive sheath made of metal or some other substantial material.

levels specified in para. 508.

(d) Any labels that may have been displayed on it in conformity with para. 538

are no longer visible.

Classification as Type A package

428. Packages containing radioactive material may be classified as Type A

packages provided that the conditions of paras 429 and 430 are met.

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

SECTION IV

429. Type A packages shall not contain activities greater than either of the

following:

(a) For special form radioactive material — A

;

(b) For all other radioactive material — A

430. For mixtures of radionuclides whose identities and respective activities are

known, the following condition shall apply to the radioactive contents of a Type

A package:

where

B(i) is the activity of radionuclide i as special form radioactive material;

(i) is the A

value for radionuclide i;

C(j) is the activity of radionuclide j as other than special form radioactive

material;

(j) is the A

value for radionuclide j.

Classification as Type B(U), Type B(M) or Type C package

431. Type B(U), Type B(M) and Type C packages shall be classified in

accordance with the competent authority certificate of approval for the package

issued by the country of origin of design.

432. The contents of a Type B(U), Type B(M) or Type C package shall be as

specified in the certificate of approval.

433. Type B(U) and Type B(M) packages, if transported by air, shall meet the

requirements of para. 432 and shall not contain activities greater than the

following:

(a) For low dispersible radioactive material — as authorized for the package

design as specified in the certificate of approval;

(b) For special form radioactive material — 3000A

or 10

, whichever is the

lower;

(i)

(j)

∑∑

+≤1

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

ACTIVITY LIMITS AND CLASSIFICATION

SPECIAL ARRANGEMENT

434. Radioactive material shall be classified as transported under special

arrangement when it is intended to be carried in accordance with para. 310.

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

Section V

REQUIREMENTS AND CONTROLS FOR TRANSPORT

REQUIREMENTS BEFORE THE FIRST SHIPMENT

501. Before a packaging is first used to transport radioactive material, it shall be

confirmed that it has been manufactured in conformity with the design

specifications to ensure compliance with the relevant provisions of these

Regulations and any applicable certificate of approval. The following

requirements shall also be fulfilled, if applicable:

(a) If the design pressure of the containment system exceeds 35 kPa (gauge), it

shall be ensured that the containment system of each packaging conforms to

the approved design requirements relating to the capability of that system to

maintain its integrity under that pressure.

(b) For each packaging intended for use as a Type B(U), Type B(M) or Type C

package and for each packaging intended to contain fissile material, it shall

be ensured that the effectiveness of its shielding and containment and,

where necessary, the heat transfer characteristics and the effectiveness of

the confinement system, are within the limits applicable to or specified for

the approved design.

that the effectiveness of the criticality safety features is within the limits

applicable to or specified for the design, and in particular where, in order to

comply with the requirements of para. 673, neutron poisons are specifically

included, checks shall be performed to confirm the presence and

distribution of those neutron poisons.

REQUIREMENTS BEFORE EACH SHIPMENT

502. Before each shipment of any package, it shall be ensured that the package

contains neither:

(a) Radionuclides different from those specified for the package design; nor

(b) Contents in a form, or physical or chemical state, different from those

specified for the package design.

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

SECTION V

503. Before each shipment of any package, it shall be ensured that all the

requirements specified in the relevant provisions of these Regulations and in the

applicable certificates of approval have been fulfilled. The following

requirements shall also be fulfilled, if applicable:

(a) It shall be ensured that lifting attachments that do not meet the requirements

of para. 608 have been removed or otherwise rendered incapable of being

used for lifting the package, in accordance with para. 609.

(b) Each Type B(U), Type B(M) and Type C package shall be held until

equilibrium conditions have been approached closely enough to

demonstrate compliance with the requirements for temperature and

pressure, unless an exemption from these requirements has received

unilateral approval.

inspection and/or appropriate tests that all closures, valve and other

openings of the containment system through which the radioactive contents

might escape are properly closed and, where appropriate, sealed in the

manner for which the demonstrations of compliance with the requirements

of paras 659 and 671 were made.

(d) For packages containing fissile material, the measurement specified in

para. 677(b) and the tests to demonstrate closure of each package as

specified in para. 680 shall be performed.

TRANSPORT OF OTHER GOODS

504. A package shall not contain any items other than those that are necessary

for the use of the radioactive material. The interaction between these items and

the package, under the conditions of transport applicable to the design, shall not

reduce the safety of the package.

505. Freight containers, IBCs, tanks, as well as other packagings and overpacks,

used for the transport of radioactive material shall not be used for the storage or

transport of other goods unless decontaminated below the level of 0.4 Bq/cm

for

beta and gamma emitters and low toxicity alpha emitters and 0.04 Bq/cm

for all

other alpha emitters.

506. Consignments shall be segregated from other dangerous goods during

transport in compliance with the relevant transport regulations for dangerous

goods of each of the countries through or into which the materials will be

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

transported, and, where applicable, with the regulations of the cognizant transport

organizations, as well as these Regulations.

Category

TI Maximum radiation level at

any point on external surface

Not more than 0.005 mSv/h I-WHITE

More than 0 but not more than 1

More than 0.005 mSv/h but

not more than 0.5 mSv/h

II-Yellow

More than 1 but not more than 10

More than 0.5 mSv/h but

not more than 2 mSv/h

III-YELLOW

More than 10

More than 2 mSv/h but

not more than 10 mSv/h

III-YELLOW

If the measured TI is not greater than 0.05, the value quoted may be zero in accordance with

para. 523(c).

Shall also be transported under exclusive use except for freight containers (see Table 10).

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

SECTION V

marking shall be in accordance with the certificate of the country of origin of

design.

Marking

531. Each package shall be legibly and durably marked on the outside of the

packaging with an identification of either the consignor or consignee, or both.

Each overpack shall be legibly and durably marked on the outside of the overpack

with an identification of either the consignor or consignee, or both, unless these

markings of all the packages within the overpack are clearly visible.

532. Each package shall be legibly and durably marked on the outside with the

UN marking as specified in Table 9. Additionally, each overpack shall be legibly

and durably marked with the word “OVERPACK” and the UN marking as

specified in Table 9 unless all the markings of the packages within the overpack

are clearly visible.

533. Each package of gross mass exceeding 50 kg shall have its permissible

gross mass legibly and durably marked on the outside of the packaging.

TABLE 9. UN MARKING FOR PACKAGES AND OVERPACKS

Item UN marking

Package

(other than an excepted package)

UN number, preceded by the letters “UN”,

and the proper shipping name

Excepted package

(other than those in consignments accepted

for international movement by post)

UN number, preceded by the letters “UN”

Overpack

(other than an overpack containing only

excepted packages)

UN number, preceded by the letters “UN”

for each applicable UN number in the

overpack, followed by the proper shipping

name in the case of a non-excepted

package

Overpack containing only excepted packages

(other than consignments accepted for

international movement by post)

UN number, preceded by the letters “UN”

for each applicable UN number in the

overpack

Consignment accepted for international

movement by post

The requirement of para. 581

See Table 1 for listing of UN numbers and proper shipping names.

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

534. Each package that conforms to:

(a) An IP-1, IP-2 or IP-3 design shall be legibly and durably marked on the

outside of the packaging with “TYPE IP-1”, “TYPE IP-2” or “TYPE IP-3”,

as appropriate.

(b) A Type A package design shall be legibly and durably marked on the

outside of the packaging with “TYPE A”.

marked on the outside of the packaging with the international vehicle

registration code (VRI code) of the country of origin of design and either

the name of the manufacturer or other identification of the packaging

specified by the competent authority of the country of origin of design.

535. Each package that conforms to a design approved under one or more of

paras 807–816 and 820 shall be legibly and durably marked on the outside of the

packaging with the following information:

(a) The identification mark allocated to that design by the competent authority;

(b) A serial number to identify uniquely each packaging that conforms to that

design;

Type B(M) or Type C package design.

536. Each package that conforms to a Type B(U), Type B(M) or Type C package

design shall have the outside of the outermost receptacle, that is resistant to the

effects of fire and water, plainly marked by embossing, stamping or other

means resistant to the effects of fire and water with the trefoil symbol shown in

Fig. 1.

537. Where LSA-I or SCO-I material is contained in receptacles or wrapping

materials and is transported under exclusive use, as permitted by para. 520, the

outer surface of these receptacles or wrapping materials may bear the marking

“RADIOACTIVE LSA-I” or “RADIOACTIVE SCO-I”, as appropriate.

Labelling

538. Each package, overpack and freight container shall bear the labels

conforming to the applicable models in Figs 2–4, except as allowed under the

alternative provisions of para. 543 for large freight containers and tanks,

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

SECTION V

according to the appropriate category. In addition, each package, overpack and

freight container containing fissile material, other than fissile material excepted

under the provisions of para. 417, shall bear labels conforming to the model in

Fig. 5. Any labels that do not relate to the contents shall be removed or covered.

For radioactive material having other dangerous properties, see para. 507.

539. The labels conforming to the applicable models in Figs 2–4 shall be affixed

to two opposite sides of the outside of a package or overpack or on the outside of

all four sides of a freight container or tank. The labels conforming to the model in

Fig. 5, where applicable, shall be affixed adjacent to the labels conforming to the

applicable models in Figs 2–4. The labels shall not cover the markings specified

in paras 531–536.

Labelling for radioactive contents

540. Each label conforming to the applicable models in Figs 2–4 shall be

completed with the following information:

X/2

5 X

60°

FIG. 1. Basic trefoil symbol with proportions based on a central circle of radius X. The

minimum allowable size of X shall be 4 mm.

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

(a) Contents:

(i) Except for LSA-I material, the name(s) of the radionuclide(s) as taken

from Table 2, using the symbols prescribed therein. For mixtures of

radionuclides, the most restrictive nuclides must be listed to the extent

the space on the line permits. The group of LSA or SCO shall be

shown following the name(s) of the radionuclide(s). The terms

“LSA-II”, “LSA-III”, “SCO-I” and “SCO-II” shall be used for this

purpose.

FIG. 2. Category I-WHITE label. The background colour of the label shall be white, the colour

of the trefoil and the printing shall be black, and the colour of the category bar shall be red.

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

SECTION V

(ii) For LSA-I material, the term “LSA-I” is all that is necessary; the name

of the radionuclide is not necessary.

(b) Activity: The maximum activity of the radioactive contents during

transport expressed in units of becquerels (Bq) with the appropriate

SI prefix symbol (see Annex II). For fissile material, the total mass of fissile

nuclides in units of grams (g), or multiples thereof, may be used in place of

activity.

5 mm

MINIMUM DIMENSION

100 mm

CONTENTS

RADIOACTIVE

ACTIVITY

MINIMUM DIMENSION

100 mm

4 mm

TRANSPORT

INDEX

FIG. 3. Category II-YELLOW label. The background colour of the upper half of the label shall

be yellow and the lower half white, the colour of the trefoil and the printing shall be black, and

the colour of the category bars shall be red.

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

on the label shall bear the information required in para. 540(a) and 540(b),

respectively, totalled together for the entire contents of the overpack or

freight container except that on labels for overpacks or freight containers

containing mixed loads of packages containing different radionuclides,

such entries may read “See Transport Documents”.

(d) TI: The number determined in accordance with paras 523 and 524 (no TI

entry is required for Category I-WHITE).

FIG. 4. Category III-YELLOW label. The background colour of the upper half of the label

shall be yellow and the lower half white, the colour of the trefoil and the printing shall be black,

and the colour of the category bars shall be red.

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

SECTION V

Labelling for criticality safety

541. Each label conforming to the model in Fig. 5 shall be completed with the

CSI as stated in the certificate of approval applicable in the countries through or

into which the consignment is transported and issued by the competent authority

or as specified in para. 674 or para. 675.

5 mm

MINIMUM DIMENSION

100 mm

FISSILE

MINIMUM DIMENSION

100 mm

CRITICALITY

SAFETY INDEX

FIG. 5. CSI label. The background colour of the label shall be white, the colour of the printing

shall be black.

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

542. For overpacks and freight containers, the label conforming to the model in

Fig. 5 shall bear the sum of the CSIs of all the packages contained therein.

Placarding

543. Large freight containers carrying packages other than excepted packages,

and tanks shall bear four placards that conform to the model given in Fig. 6. The

placards shall be affixed in a vertical orientation to each side wall and to each end

wall of the large freight container or tank. Any placards that do not relate to the

contents shall be removed. Instead of using both labels and placards, it is

permitted, as an alternative, to use enlarged labels only, where appropriate, as

shown in Figs 2–4, except having the minimum size shown in Fig. 6.

544. Where the consignment in the freight container or tank is unpackaged LSA-I

or SCO-I or where a consignment in a freight container is required to be shipped

under exclusive use and is packaged radioactive material with a single UN

number, the appropriate UN number for the consignment (see Table 1) shall also

be displayed, in black digits not less than 65 mm high, either:

(a) In the lower half of the placard shown in Fig. 6 and against the white

background; or

(b) On the placard shown in Fig. 7.

When the alternative given in (b) is used, the subsidiary placard shall be affixed

immediately adjacent to the main placard, on all four sides of the freight

container or tank.

CONSIGNOR’S RESPONSIBILITIES

545. Except as otherwise provided in these Regulations, no person may offer

radioactive material for transport unless it is properly marked, labelled,

placarded, described and certified on a transport document, and otherwise in a

condition for transport as required by these Regulations.

Particulars of consignment

546. The consignor shall include in the transport documents with each

consignment the identification of the consignor and consignee, including their

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

SECTION V

names and addresses, and the following information, as applicable, in the order

given:

(a) The UN number assigned to the material as specified in accordance with the

provisions of paras 401 and 530, preceded by the letters “UN”.

FIG. 6. Placard. Except as permitted by para. 571, minimum dimensions shall be as shown;

when different dimensions are used, the relative proportions shall be maintained. The

number ‘7’ shall not be less than 25 mm high. The background colour of the upper half of the

placard shall be yellow and the lower half white, the colour of the trefoil and the printing shall

be black. The use of the word “RADIOACTIVE” in the bottom half is optional, to allow the

alternative use of this placard to display the appropriate UN number for the consignment.

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

(b) The proper shipping name, as specified in accordance with the provisions of

paras 401 and 530.

(d) The subsidiary hazard class or division number(s) corresponding to the

subsidiary risk label(s) required to be applied, when assigned, shall be

entered following the primary hazard class or division and shall be enclosed

in parentheses.

(e) The name or symbol of each radionuclide or, for mixtures of radionuclides,

an appropriate general description or a list of the most restrictive nuclides.

(f) A description of the physical and chemical form of the material, or a

notation that the material is special form radioactive material or low

dispersible radioactive material. A generic chemical description is

acceptable for chemical form.

(g) The maximum activity of the radioactive contents during transport

expressed in units of becquerels (Bq) with the appropriate SI prefix symbol

(see Annex II). For fissile material, the mass of fissile material (or mass of

each fissile nuclide for mixtures, when appropriate) in units of grams (g), or

appropriate multiples thereof, may be used in place of activity.

(h) The category of the package, i.e. I-WHITE, II-YELLOW, III-YELLOW.

(i) The TI (categories II-YELLOW and III-YELLOW only).

FIG. 7. Placard for separate display of UN number. The background colour of the placard

shall be orange and the border and UN number shall be black. The symbol “****” denotes the

space in which the appropriate UN number for radioactive material, as specified in Table 1,

shall be displayed.

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

SECTION V

(j) For fissile material:

(i) Shipped under one exception of subparagraphs 417(a)–(f), reference

to that para.;

(ii) Shipped under para. 417(c)–(e), the total mass of fissile nuclides;

(iii) Contained in a package for which one of para. 674(a)–(c) or 675 is

applied, reference to that para.;

(iv) The CSI, where applicable.

(k) The identification mark for each competent authority certificate of approval

(special form radioactive material, low dispersible radioactive material,

fissile material excepted under para. 417(f), special arrangement, package

design or shipment) applicable to the consignment.

(l) For consignments of more than one package, the information contained in

para. 546(a)–(k) shall be given for each package. For packages in an

overpack, freight container or conveyance, a detailed statement of the

contents of each package within the overpack, freight container or

conveyance and, where appropriate, of each overpack, freight container or

conveyance shall be included. If packages are to be removed from the

overpack, freight container or conveyance at a point of intermediate

unloading, appropriate transport documents shall be made available.

(m) Where a consignment is required to be shipped under exclusive use, the

statement “EXCLUSIVE USE SHIPMENT”.

(n) For LSA-II, LSA-III, SCO-I and SCO-II, the total activity of the

consignment as a multiple of A

. For radioactive material for which the A

value is unlimited, the multiple of A

shall be zero.

Consignor’s certification or declaration

547. The consignor shall include in the transport documents a certification or

declaration in the following terms:

“I hereby declare that the contents of this consignment are fully and

accurately described above by the proper shipping name and are classified,

packaged, marked and labelled/placarded, and are in all respects in proper

condition for transport in accordance with the applicable international and

national governmental regulations.”

548. If the intent of the declaration is already a condition of transport within a

particular international convention, the consignor need not provide such a

declaration for that part of the transport covered by the convention.

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

549. The declaration shall be signed and dated by the consignor. Facsimile

signatures are acceptable where applicable laws and regulations recognize the

legal validity of facsimile signatures.

550. If the dangerous goods documentation is presented to the carrier by means

of electronic data processing (EDP) or electronic data interchange (EDI)

transmission techniques, the signature(s) may be replaced by the name(s)

(in capitals) of the person authorized to sign.

551. When radioactive material, other than when carried in tanks, is packed or

loaded into any freight container or vehicle that will be transported by sea, those

responsible for packing the container or vehicle shall provide a container/vehicle

packing certificate specifying the container/vehicle identification number(s) and

certifying that the operation has been carried out in accordance with the

applicable conditions of the IMDG Code [8].

552. The information required in the transport documents and the

container/vehicle packing certificate may be incorporated into a single document,

if not, the documents shall be attached one to the other. If the information is

incorporated into a single document, the document shall include a signed

declaration such as:

“It is declared that the packing of the goods into the container/vehicle has

been carried out in accordance with the applicable provisions”.

This declaration shall be dated and the person signing it shall be identified on the

document. Facsimile signatures are acceptable where applicable laws and

regulations recognize the legal validity of facsimile signatures.

553. The declaration shall be made on the same transport document that contains

the particulars of consignment listed in para. 546.

Information for carriers

554. The consignor shall provide in the transport documents a statement

regarding actions, if any, that are required to be taken by the carrier. The

statement shall be in the languages deemed necessary by the carrier or the

authorities concerned and shall include at least the following points:

(a) Supplementary requirements for loading, stowage, carriage, handling and

unloading of the package, overpack or freight container, including any

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

SECTION V

special stowage provisions for the safe dissipation of heat (see para. 565), or

a statement that no such requirements are necessary;

(b) Restrictions on the mode of transport or conveyance and any necessary

routeing instructions;

555. The consignor shall retain a copy of each of the transport documents

containing the information specified in paras 546, 547, 551, 552 and 554, as

applicable, for a minimum period of three months.

When the documents are kept electronically, the consignor shall be able to

reproduce them in a printed form.

556. The applicable competent authority certificates need not necessarily

accompany the consignment. The consignor shall make them available to the

carrier(s) before loading and unloading.

Notification of competent authorities

557. Before the first shipment of any package requiring competent authority

approval, the consignor shall ensure that copies of each applicable competent

authority certificate applying to that package design have been submitted to the

competent authority of the country of origin of the shipment and to the competent

authority of each country through or into which the consignment is to be

transported. The consignor is not required to await an acknowledgement from the

competent authority, nor is the competent authority required to make such

acknowledgement of receipt of the certificate.

558. For each shipment listed in (a), (b), (c) or (d) below, the consignor shall

notify the competent authority of the country of origin of the shipment and the

competent authority of each country through or into which the consignment is to

be transported. This notification shall be in the hands of each competent authority

prior to the commencement of the shipment, and preferably at least 7 days in

advance.

(a) Type C packages containing radioactive material with an activity greater

than 3000A

or 3000A

, as appropriate, or 1000 TBq, whichever is the

lower;

(b) Type B(U) packages containing radioactive material with an activity

greater than 3000A

or 3000A

, as appropriate, or 1000 TBq, whichever is

the lower;

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

(d) Shipments under special arrangement.

559. The consignment notification shall include:

(a) Sufficient information to enable the identification of the package or

packages, including all applicable certificate numbers and identification

marks.

(b) Information on the date of shipment, the expected date of arrival and the

proposed routeing.

(d) Descriptions of the physical and chemical forms of the radioactive

material, or whether it is special form radioactive material or low

dispersible radioactive material.

(e) The maximum activity of the radioactive contents during transport

expressed in units of becquerels (Bq) with the appropriate SI prefix symbol

(see Annex II). For fissile material, the mass of fissile material (or the mass

of each fissile nuclide for a mixture, when appropriate) in units of

grams (g), or multiples thereof, may be used in place of activity.

560. The consignor is not required to send a separate notification if the required

information has been included in the application for approval of shipment (see

para. 827).

Possession of certificates and instructions

561. The consignor shall have in his/her possession a copy of each certificate

required under Section VIII of these Regulations and a copy of the instructions

with regard to the proper closing of the package and other preparations for

shipment before making any shipment under the terms of the certificates.

TRANSPORT AND STORAGE IN TRANSIT

Segregation during transport and storage in transit

562. Packages, overpacks and freight containers containing radioactive material

and unpackaged radioactive material shall be segregated during transport and

during storage in transit:

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

SECTION V

(a) From workers in regularly occupied working areas by distances calculated

using a dose criterion of 5 mSv in a year and conservative model

parameters;

(b) From members of the public in areas where the public has regular access by

distances calculated using a dose criterion of 1 mSv in a year and

conservative model parameters;

radiation exposure criterion for undeveloped photographic film due to the

transport of radioactive material of 0.1 mSv per consignment of such film;

(d) From other dangerous goods in accordance with para. 506.

563. Category II-YELLOW or III-YELLOW packages or overpacks shall not be

carried in compartments occupied by passengers, except those exclusively

reserved for couriers specially authorized to accompany such packages or

overpacks.

Stowage during transport and storage in transit

564. Consignments shall be securely stowed.

565. Provided that its average surface heat flux does not exceed 15 W/m

and

that the immediate surrounding cargo is not in sacks or bags, a package or

overpack may be carried or stored among packaged general cargo without any

special stowage provisions except as may be specifically required by the

competent authority in an applicable certificate of approval.

566. Loading of freight containers and accumulation of packages, overpacks and

freight containers shall be controlled as follows:

(a) Except under the condition of exclusive use, and for consignments of LSA-I

material, the total number of packages, overpacks and freight containers

aboard a single conveyance shall be so limited that the sum of the TIs

aboard the conveyance does not exceed the values shown in Table 10.

(b) The radiation level under routine conditions of transport shall not exceed

2 mSv/h at any point on, and 0.1 mSv/h at 2 m from, the external surface of

the conveyance, except for consignments transported under exclusive use by

road or rail, for which the radiation limits around the vehicle are set forth in

para. 573(b) and 573(c).

not exceed the values shown in Table 11.

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

567. Any package or overpack having a TI greater than 10, or any consignment

having a CSI greater than 50, shall be transported only under exclusive use.

Additional requirements relating to transport and storage in transit of



fissile material

568. Any group of packages, overpacks and freight containers containing fissile

material stored in transit in any one storage area shall be so limited that the sum

of the CSIs in the group does not exceed 50. Each group shall be stored so as to

maintain a spacing of at least 6 m from other such groups.

569. Where the sum of the CSIs on board a conveyance or in a freight container

exceeds 50, as permitted in Table 11, storage shall be such as to maintain a spacing

TABLE 10. TRANSPORT INDEX LIMITS FOR FREIGHT CONTAINERS

AND CONVEYANCES NOT UNDER EXCLUSIVE USE

Type of freight container or conveyance

Limit on sum of TIs in a freight

container or aboard a conveyance

Freight container:

Small freight container 50

Large freight container 50

Vehicle 50

Aircraft:

Passenger 50

Cargo 200

Inland waterway craft 50

Seagoing vessel

(i) Hold, compartment or defined deck area:

Packages, overpacks, small freight containers



Large freight containers

200

(ii) Total vessel:

Packages, overpacks, small freight containers



Large freight containers

200

No limit

Packages or overpacks carried in or on a vehicle that are in accordance with the provisions

of para. 573 may be transported by vessels provided that they are not removed from the

vehicle at any time while on board the vessel.

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

SECTION V

of at least 6 m from other groups of packages, overpacks or freight containers

containing fissile material or other conveyances carrying radioactive material.

TABLE 11. CSI LIMITS FOR FREIGHT CONTAINERS AND CONVEYANCES

CONTAINING FISSILE MATERIAL

Type of freight container or conveyance

Limit on sum of CSIs in a freight container or

aboard a conveyance

Not under exclusive use Under exclusive use

Freight container:

Small freight container 50 Not applicable

Large freight container 50 100

Vehicle 50 100

Aircraft:

Passenger 50 Not applicable

Cargo 50 100

Inland waterway craft 50 100

Seagoing vessel

(i) Hold, compartment or

defined deck area:

Packages, overpacks,



small freight containers



Large freight containers

100

(ii) Total vessel:

Packages, overpacks,



small freight containers



Large freight containers

200

No limit

200

No limit

Packages or overpacks carried in or on a vehicle that are in accordance with the provisions

of para. 573 may be transported by vessels provided that they are not removed from the

vehicle at any time while on board the vessel. In this case, the entries under the heading

“under exclusive use” apply.

The consignment shall be so handled and stowed that the sum of CSIs in any group does not

exceed 50 and that each group is handled and stowed so as to maintain a spacing of at least

6 m from other groups.

The consignment shall be so handled and stowed that the sum of CSIs in any group does not

exceed 100 and that each group is handled and stowed so as to maintain a spacing of at least

6 m from other groups. The intervening space between groups may be occupied by other

cargo in accordance with para. 506.

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

570. Fissile material meeting one of the provisions (a)–(f) of para. 417 shall

meet the following requirements:

(a) Only one of the provisions (a)–(f) of para. 417 is allowed per consignment.

(b) Only one approved fissile material in packages classified in accordance

with para. 417(f) is allowed per consignment unless multiple materials are

authorized in the certificate of approval.

be transported in a consignment with no more than 45 g of fissile nuclides.

(d) Fissile material in packages classified in accordance with para. 417(d) shall

be transported in a consignment with no more than 15 g of fissile nuclides.

(e) Unpackaged or packaged fissile material classified in accordance with

para. 417(e) shall be transported under exclusive use on a conveyance with

no more than 45 g of fissile nuclides.

Additional requirements relating to transport by rail and by road

571. Rail and road vehicles carrying packages, overpacks or freight containers

labelled with any of the labels shown in Figs 2–5, or carrying consignments under

exclusive use, shall display the placard shown in Fig. 6 on each of:

(a) The two external lateral walls in the case of a rail vehicle;

(b) The two external lateral walls and the external rear wall in the case of a road

vehicle.

In the case of a vehicle without sides, the placards may be affixed directly on the

cargo carrying unit provided that they are readily visible. In the case of large

tanks or freight containers, the placards on the tanks or freight containers shall

suffice. In the case of vehicles that have insufficient area to allow the fixing of

larger placards, the dimensions of the placard described in Fig. 6 may be reduced

to 100 mm. Any placards that do not relate to the contents shall be removed.

572. Where the consignment in or on the vehicle is unpackaged LSA-I material or

SCO-I or where a consignment is required to be shipped under exclusive use and

is packaged radioactive material with a single UN number, the appropriate

UN number (see Table 1) shall also be displayed, in black digits not less than

65 mm high, either:

(a) In the lower half of the placard shown in Fig. 6, against the white

background; or

(b) On the placard shown in Fig. 7.

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

SECTION V

When the alternative given in (b) is used, the subsidiary placard shall be affixed

immediately adjacent to the main placard, either on the two external lateral walls

in the case of a rail vehicle or on the two external lateral walls and the external

rear wall in the case of a road vehicle.

573. For consignments under exclusive use, the radiation level shall not exceed:

(a) 10 mSv/h at any point on the external surface of any package or overpack,

and may only exceed 2 mSv/h provided that:

(i) The vehicle is equipped with an enclosure that, during routine

conditions of transport, prevents the access of unauthorized persons to

the interior of the enclosure.

(ii) Provisions are made to secure the package or overpack so that its

position within the vehicle enclosure remains fixed during routine

conditions of transport.

(iii) There is no loading or unloading during the shipment.

(b) 2 mSv/h at any point on the outer surfaces of the vehicle, including the

upper and lower surfaces, or, in the case of an open vehicle, at any point on

the vertical planes projected from the outer edges of the vehicle, on the

upper surface of the load, and on the lower external surface of the vehicle.

lateral surfaces of the vehicle, or, if the load is transported in an open

vehicle, at any point 2 m from the vertical planes projected from the outer

edges of the vehicle.

574. In the case of road vehicles, no persons other than the driver and assistants

shall be permitted in vehicles carrying packages, overpacks or freight containers

bearing category II-YELLOW or III-YELLOW labels.

Additional requirements relating to transport by vessels

575. Packages or overpacks having a surface radiation level greater than

2 mSv/h, unless being carried in or on a vehicle under exclusive use in accordance

with Table 10, footnote (a), shall not be transported by vessel except under

special arrangement.

576. The transport of consignments by means of a special use vessel that, by

virtue of its design, or by reason of its being chartered, is dedicated to the purpose

of carrying radioactive material, shall be excepted from the requirements

specified in para. 566 provided that the following conditions are met:

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

(a) A radiation protection programme for the shipment shall be approved by

the competent authority of the flag state of the vessel and, when requested,

by the competent authority at each port of call.

(b) Stowage arrangements shall be predetermined for the whole voyage,

including any consignments to be loaded at ports of call en route.

supervised by persons qualified in the transport of radioactive material.

Additional requirements relating to transport by air

577. Type B(M) packages and consignments under exclusive use shall not be

transported on passenger aircraft.

578. Vented Type B(M) packages, packages that require external cooling by an

ancillary cooling system, packages subject to operational controls during

transport and packages containing liquid pyrophoric materials shall not be

transported by air.

579. Packages or overpacks having a surface radiation level greater than

2 mSv/h shall not be transported by air except by special arrangement.

Additional requirements relating to transport by post

580. A consignment that conforms to the requirements of para. 515, in which the

activity of the radioactive contents does not exceed one tenth of the limits

prescribed in Table 4, and that does not contain uranium hexafluoride, may be

accepted for domestic movement by national postal authorities, subject to such

additional requirements as those authorities may prescribe.

581. A consignment that conforms to the requirements of para. 515, in which the

activity of the radioactive contents does not exceed one tenth of the limits

prescribed in Table 4, and that does not contain uranium hexafluoride, may be

accepted for international movement by post, subject in particular to the

following additional requirements as prescribed by the Acts of the Universal

Postal Union:

(a) It shall be deposited with the postal service only by consignors authorized

by the national authority.

(b) It shall be dispatched by the quickest route, normally by air.

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

SECTION V

“RADIOACTIVE MATERIAL — QUANTITIES PERMITTED FOR

MOVEMENT BY POST”. These words shall be crossed out if the

packaging is returned empty.

(d) It shall carry on the outside the name and address of the consignor with the

request that the consignment be returned in the case of non-delivery.

(e) The name and address of the consignor and the contents of the consignment

shall be indicated on the internal packaging.

CUSTOMS OPERATIONS

582. Customs operations involving the inspection of the radioactive contents of

a package shall be carried out only in a place where adequate means of

controlling radiation exposure are provided and in the presence of qualified

persons. Any package opened on customs instructions shall, before being

forwarded to the consignee, be restored to its original condition.

UNDELIVERABLE CONSIGNMENTS

583. Where a consignment is undeliverable, it shall be placed in a safe location

and the appropriate competent authority shall be informed as soon as possible and

a request made for instructions on further action.

RETENTION AND AVAILABILITY OF TRANSPORT DOCUMENTS BY

CARRIERS

584. A carrier shall not accept a consignment for transport unless:

(a) A copy of the transport document and other documents or information as

required by these Regulations are provided; or

(b) The information applicable to the consignment is provided in electronic

form.

585. The information applicable to the consignment shall accompany the

consignment to final destination. This information may be on the transport

document or may be on another document. This information shall be given to the

consignee when the consignment is delivered.

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

REQUIREMENTS AND CONTROLS FOR TRANSPORT

586. When the information applicable to the consignment is given to the carrier

in electronic form, the information shall be available to the carrier at all times

during transport to final destination. The information shall be able to be produced

without delay as a paper document.

587. The carrier shall retain a copy of the transport document and additional

information and documentation, as specified in these Regulations, for a minimum

period of three months.

588. When the documents are kept electronically or in a computer system, the

carrier shall be capable of reproducing them in a printed form.

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

Section VI

REQUIREMENTS FOR RADIOACTIVE MATERIAL

AND FOR PACKAGINGS AND PACKAGES

REQUIREMENTS FOR RADIOACTIVE MATERIAL

Requirements for LSA-III material

601. LSA-III material shall be a solid of such a nature that if the entire contents

of a package were subjected to the test specified in para. 703, the activity in the

water would not exceed 0.1A

Requirements for special form radioactive material

602. Special form radioactive material shall have at least one dimension of not

less than 5 mm.

603. Special form radioactive material shall be of such a nature or shall be so

designed that if it is subjected to the tests specified in paras 704–711, it shall meet

the following requirements:

(a) It would not break or shatter under the impact, percussion and bending tests

in paras 705–707 and 709(a), as applicable.

(b) It would not melt or disperse in the heat test in para. 708 or para. 709(b), as

applicable.

711 would not exceed 2 kBq; or alternatively, for sealed sources, the

leakage rate for the volumetric leakage assessment test specified in the

International Organization for Standardization document ISO 9978:

Radiation Protection — Sealed Radioactive Sources — Leakage Test

Methods [9], would not exceed the applicable acceptance threshold

acceptable to the competent authority.

604. When a sealed capsule constitutes part of the special form radioactive

material, the capsule shall be so manufactured that it can be opened only by

destroying it.

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

SECTION VI

Requirements for low dispersible radioactive material

605. Low dispersible radioactive material shall be such that the total amount of

this radioactive material in a package shall meet the following requirements:

(a) The radiation level at 3 m from the unshielded radioactive material does

not exceed 10 mSv/h.

(b) If subjected to the tests specified in paras 736 and 737, the airborne release

in gaseous and particulate forms of up to 100 μm aerodynamic equivalent

diameter would not exceed 100A

. A separate specimen may be used for

each test.

not exceed 100A

. In the application of this test, the damaging effects of the

tests specified in (b) shall be taken into account.

REQUIREMENTS FOR MATERIAL EXCEPTED FROM FISSILE

CLASSIFICATION

606. A fissile material excepted from classification as “FISSILE” under

para. 417(f) shall be subcritical without the need for accumulation control under

the following conditions:

(a) The conditions of para. 673(a);

(b) The conditions consistent with the assessment provisions stated in

paras 684(b) and 685(b) for packages;

GENERAL REQUIREMENTS FOR ALL PACKAGINGS AND PACKAGES

607. The package shall be so designed in relation to its mass, volume and shape

that it can be easily and safely transported. In addition, the package shall be so

designed that it can be properly secured in or on the conveyance during transport.

608. The design shall be such that any lifting attachments on the package will

not fail when used in the intended manner and that if failure of the attachments

should occur, the ability of the package to meet other requirements of these

Regulations would not be impaired. The design shall take account of appropriate

safety factors to cover snatch lifting.

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

REQUIREMENTS FOR PACKAGES

609. Attachments and any other features on the outer surface of the package that

could be used to lift it shall be designed either to support its mass in accordance

with the requirements of para. 608 or shall be removable or otherwise rendered

incapable of being used during transport.

610. As far as practicable, the packaging shall be so designed and finished that

the external surfaces are free from protruding features and can be easily

decontaminated.

611. As far as practicable, the outer layer of the package shall be so designed as

to prevent the collection and the retention of water.

612. Any features added to the package at the time of transport that are not part

of the package shall not reduce its safety.

613. The package shall be capable of withstanding the effects of any

acceleration, vibration or vibration resonance that may arise under routine

conditions of transport without any deterioration in the effectiveness of the

closing devices on the various receptacles or in the integrity of the package as a

whole. In particular, nuts, bolts and other securing devices shall be so designed as

to prevent them from becoming loose or being released unintentionally, even

after repeated use.

614. The materials of the packaging and any components or structures shall be

physically and chemically compatible with each other and with the radioactive

contents. Account shall be taken of their behaviour under irradiation.

615. All valves through which the radioactive contents could escape shall be

protected against unauthorized operation.

616. The design of the package shall take into account ambient temperatures and

pressures that are likely to be encountered in routine conditions of transport.

617. A package shall be so designed that it provides sufficient shielding to

ensure that, under routine conditions of transport and with the maximum

radioactive contents that the package is designed to contain, the radiation level at

any point on the external surface of the package would not exceed the values

specified in paras 516, 527 and 528, as applicable, with account taken of

paras 566(b) and 573.

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

SECTION VI

618. For radioactive material having other dangerous properties, the package

design shall take into account those properties (see paras 110 and 507).

ADDITIONAL REQUIREMENTS FOR PACKAGES TRANSPORTED

BY AIR

619. For packages to be transported by air, the temperature of the accessible

surfaces shall not exceed 50°C at an ambient temperature of 38°C with no

account taken for insolation.

620. Packages to be transported by air shall be so designed that if they were

exposed to ambient temperatures ranging from –40°C to +55°C, the integrity of

containment would not be impaired.

621. Packages containing radioactive material to be transported by air shall be

capable of withstanding, without loss or dispersal of radioactive contents from

the containment system, an internal pressure that produces a pressure differential

of not less than maximum normal operating pressure plus 95 kPa.

REQUIREMENTS FOR EXCEPTED PACKAGES

622. An excepted package shall be designed to meet the requirements specified

in paras 607–618 and, in addition, the requirements of paras 619–621 if carried

by air.

REQUIREMENTS FOR INDUSTRIAL PACKAGES

Requirements for Type IP-1

623. A Type IP-1 package shall be designed to meet the requirements specified

in paras 607–618 and 636 and, in addition, the requirements of paras 619–621 if

carried by air.

Requirements for Type IP-2

624. A package to be qualified as Type IP-2 shall be designed to meet the

requirements for Type IP-1 as specified in para. 623 and, in addition, if it were

subjected to the tests specified in paras 722 and 723, it would prevent:

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

REQUIREMENTS FOR PACKAGES

(a) Loss or dispersal of the radioactive contents;

(b) More than a 20% increase in the maximum radiation level at any external

surface of the package.

Requirements for Type IP-3

625. A package to be qualified as Type IP-3 shall be designed to meet the

requirements for Type IP-1 as specified in para. 623 and, in addition, the

requirements specified in paras 636–649.

Alternative requirements for Type IP-2 and Type IP-3

626. Packages may be used as Type IP-2, provided that:

(a) They satisfy the requirements for Type IP-1 specified in para. 623.

(b) They are designed to satisfy the requirements prescribed for UN Packing

Group I or II in Chapter 6.1 of the United Nations Recommendations on the

Transport of Dangerous Goods, Model Regulations [10].

would prevent:

(i) Loss or dispersal of the radioactive contents;

(ii) More than a 20% increase in the maximum radiation level at any

external surface of the package.

627. Portable tanks may also be used as Type IP-2 or Type IP-3, provided that:

(a) They satisfy the requirements for Type IP-1 specified in para. 623.

(b) They are designed to satisfy the requirements prescribed in Chapter 6.7 of

the United Nations Recommendations on the Transport of Dangerous

Goods, Model Regulations [10], or other requirements, at least equivalent,

and are capable of withstanding a test pressure of 265 kPa.

capable of withstanding the static and dynamic stresses resulting from

handling and routine conditions of transport and of preventing more than a

20% increase in the maximum radiation level at any external surface of the

portable tanks.

628. Ta nks, other than portable tanks, may also be used as Type IP-2 or Type IP-3

for transporting LSA-I and LSA-II liquids and gases as prescribed in Table 5,

provided that:

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

SECTION VI

(a) They satisfy the requirements for Type IP-1 specified in para. 623.

(b) They are designed to satisfy the requirements prescribed in regional or

national regulations for the transport of dangerous goods and are capable of

withstanding a test pressure of 265 kPa.

capable of withstanding the static and dynamic stresses resulting from

handling and routine conditions of transport and of preventing more than a

20% increase in the maximum radiation level at any external surface of the

tanks.

629. Freight containers with the characteristics of a permanent enclosure may

also be used as Type IP-2 or Type IP-3, provided that:

(a) The radioactive contents are restricted to solid materials.

(b) They satisfy the requirements for Type IP-1 specified in para. 623.

Standardization document ISO 1496/1: Series 1 Freight Containers —

Specifications and Testing — Part 1: General Cargo Containers for General

Purposes [11] excluding dimensions and ratings. They shall be designed

such that if subjected to the tests prescribed in that document and to the

accelerations occurring during routine conditions of transport they would

prevent:

(i) Loss or dispersal of the radioactive contents;

(ii) More than a 20% increase in the maximum radiation level at any

external surface of the freight containers.

630. Metal IBCs may also be used as Type IP-2 or Type IP-3, provided that:

(a) They satisfy the requirements for Type IP-1 specified in para. 623.

(b) They are designed to satisfy the requirements prescribed for UN Packing

Group I or II in Chapter 6.5 of the United Nations Recommendations on the

Transport of Dangerous Goods, Model Regulations [10], and if they were

subjected to the tests prescribed in that document, but with the drop test

conducted in the most damaging orientation, they would prevent:

(i) Loss or dispersal of the radioactive contents;

(ii) More than a 20% increase in the maximum radiation level at any

external surface of the IBC.

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

REQUIREMENTS FOR PACKAGES

REQUIREMENTS FOR PACKAGES CONTAINING URANIUM

HEXAFLUORIDE

631. Packages designed to contain uranium hexafluoride shall meet the

requirements that pertain to the radioactive and fissile properties of the material

prescribed elsewhere in these Regulations. Except as allowed in para. 634,

uranium hexafluoride in quantities of 0.1 kg or more shall also be packaged and

transported in accordance with the provisions of the International Organization

for Standardization document ISO 7195: Packaging of Uranium Hexafluoride

(UF

) for Transport [12], and the requirements of paras 632 and 633.

632. Each package designed to contain 0.1 kg or more of uranium hexafluoride

shall be designed so that it will meet the following requirements:

(a) Withstand, without leakage and without unacceptable stress, as specified in

ISO 7195 [12], the structural test as specified in para. 718, except as

allowed in para. 634;

(b) Withstand, without loss or dispersal of the uranium hexafluoride, the free

drop test specified in para. 722;

specified in para. 728, except as allowed in para. 634.

633. Packages designed to contain 0.1 kg or more of uranium hexafluoride shall

not be provided with pressure relief devices.

634. Subject to multilateral approval, packages designed to contain 0.1 kg or

more of uranium hexafluoride may be transported if the packages are designed:

(a) To international or national standards other than ISO 7195 [12], provided an

equivalent level of safety is maintained; and/or

(b) To withstand, without leakage and without unacceptable stress, a test

pressure of less than 2.76 MPa as specified in para. 718; and/or

not meet the requirement of para. 632(c).

In all other respects, the requirements specified in paras 631–633 shall be

satisfied.

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

SECTION VI

REQUIREMENTS FOR TYPE A PACKAGES

635. Type A packages shall be designed to meet the requirements specified in

paras 607–618 and, in addition, the requirements of paras 619–621 if carried by

air, and of paras 636–651.

636. The smallest overall external dimension of the package shall not be less

than 10 cm.

637. The outside of the package shall incorporate a feature such as a seal that is

not readily breakable and which, while intact, will be evidence that the package

has not been opened.

638. Any tie-down attachments on the package shall be so designed that, under

normal and accident conditions of transport, the forces in those attachments shall

not impair the ability of the package to meet the requirements of these

Regulations.

639. The design of the package shall take into account temperatures ranging

from –40°C to +70°C for the components of the packaging. Attention shall be

given to freezing temperatures for liquids and to the potential degradation of

packaging materials within the given temperature range.

640. The design and manufacturing techniques shall be in accordance with

national or international standards, or other requirements, acceptable to the

competent authority.

641. The design shall include a containment system securely closed by a positive

fastening device that cannot be opened unintentionally or by a pressure that may

arise within the package.

642. Special form radioactive material may be considered as a component of the

containment system.

643. If the containment system forms a separate unit of the package, it shall be

capable of being securely closed by a positive fastening device that is

independent of any other part of the packaging.

644. The design of any component of the containment system shall take into

account, where applicable, the radiolytic decomposition of liquids and other

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

REQUIREMENTS FOR PACKAGES

vulnerable materials and the generation of gas by chemical reaction and

radiolysis.

645. The containment system shall retain its radioactive contents under a

reduction of ambient pressure to 60 kPa.

646. All valves, other than pressure relief valves, shall be provided with an

enclosure to retain any leakage from the valve.

647. A radiation shield that encloses a component of the package specified as a

part of the containment system shall be so designed as to prevent the unintentional

release of that component from the shield. Where the radiation shield and such

component within it form a separate unit, the radiation shield shall be capable of

being securely closed by a positive fastening device that is independent of any

other packaging structure.

648. A package shall be so designed that if it were subjected to the tests specified

in paras 719–724, it would prevent:

(a) Loss or dispersal of the radioactive contents;

(b) More than a 20% increase in the maximum radiation level at any external

surface of the package;

649. The design of a package intended for liquid radioactive material shall make

provision for ullage to accommodate variations in the temperature of the

contents, dynamic effects and filling dynamics.

650. A Type A package designed to contain liquid radioactive material shall, in

addition:

(a) Be adequate to meet the conditions specified in para. 648(a) if the package

is subjected to the tests specified in para. 725; and

(b) Either:

(i) Be provided with sufficient absorbent material to absorb twice the

volume of the liquid contents. Such absorbent material must be suitably

positioned so as to contact the liquid in the event of leakage; or

(ii) Be provided with a containment system composed of primary inner

and secondary outer containment components designed to enclose the

liquid contents completely and to ensure their retention within the

secondary outer containment components, even if the primary inner

components leak.

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

SECTION VI

651. A package designed for gases shall prevent loss or dispersal of the

radioactive contents if the package were subjected to the tests specified in

para. 725. A Type A package designed for tritium gas or for noble gases shall be

excepted from this requirement.

REQUIREMENTS FOR TYPE B(U) PACKAGES

652. Type B(U) packages shall be designed to meet the requirements specified in

paras 607–618, the requirements specified in paras 619–621 if carried by air, and

in paras 636–649, except as specified in para. 648(a), and, in addition, the

requirements specified in paras 653–666.

653. A package shall be so designed that, under the ambient conditions specified

in paras 656 and 657, heat generated within the package by the radioactive

contents shall not, under normal conditions of transport, as demonstrated by the

tests in paras 719–724, adversely affect the package in such a way that it would

fail to meet the applicable requirements for containment and shielding if left

unattended for a period of one week. Particular attention shall be paid to the

effects of heat that may cause one or more of the following:

(a) Alteration of the arrangement, the geometrical form or the physical state of

the radioactive contents or, if the radioactive material is enclosed in a can

or receptacle (for example, clad fuel elements), cause the can, receptacle or

radioactive material to deform or melt;

(b) Lessening the efficiency of the packaging through differential thermal

expansion, or cracking or melting of the radiation shielding material;

654. A package shall be so designed that, under the ambient condition specified

in para. 656 and in the absence of insolation, the temperature of the accessible

surfaces of a package shall not exceed 50°C, unless the package is transported

under exclusive use.

655. Except as required in para. 619 for a package transported by air, the

maximum temperature of any surface readily accessible during transport of a

package under exclusive use shall not exceed 85°C in the absence of insolation

under the ambient condition specified in para. 656. Account may be taken of

barriers or screens intended to give protection to persons without the need for the

barriers or screens being subject to any test.

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

REQUIREMENTS FOR PACKAGES

656. The ambient temperature shall be assumed to be 38°C.

657. The solar insolation conditions shall be assumed to be as specified in Table 12.

658. A package that includes thermal protection for the purpose of satisfying the

requirements of the thermal test specified in para. 728 shall be so designed that

such protection will remain effective if the package is subjected to the tests

specified in paras 719–724 and 727(a) and 727(b) or 727(b) and 727(c), as

appropriate. Any such protection on the exterior of the package shall not be

rendered ineffective by ripping, cutting, skidding, abrading or rough handling.

659. A package shall be so designed that if it were subjected to:

(a) The tests specified in paras 719–724, it would restrict the loss of

radioactive contents to not more than 10

–6

per hour.

(b) The tests specified in paras 726, 727(b), 728 and 729 and either the test in:

— Para. 727(c), when the package has a mass not greater than 500 kg, an

overall density not greater than 1000 kg/m

based on the external

dimensions, and radioactive contents greater than 1000A

not as special

form radioactive material; or

— Para. 727(a), for all other packages.

(i) It would retain sufficient shielding to ensure that the radiation level

1 m from the surface of the package would not exceed 10 mSv/h

with the maximum radioactive contents that the package is

designed to contain.

(ii) It would restrict the accumulated loss of radioactive contents in a

period of one week to not more than 10A

for krypton-85 and not

more than A

for all other radionuclides.

TABLE 12. INSOLATION DATA

Case Form and location of surface

Insolation

for 12 h per day (W/m

)

1 Flat surfaces transported horizontally — downward facing 0

2 Flat surfaces transported horizontally — upward facing 800

3 Surfaces transported vertically 200

4 Other downward facing (not horizontal) surfaces 200

5 All other surfaces 400

Alternatively, a sine function may be used, with an absorption coefficient adopted and the

effects of possible reflection from neighbouring objects neglected.

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

SECTION VI

100

Where mixtures of different radionuclides are present, the provisions of

paras 405–407 shall apply, except that for krypton-85 an effective A

(i) value

equal to 10A

may be used. For case (a), the assessment shall take into account the

external contamination limits of para. 508.

660. A package for radioactive contents with activity greater than 10

shall be

so designed that if it were subjected to the enhanced water immersion test

specified in para. 730, there would be no rupture of the containment system.

661. Compliance with the permitted activity release limits shall depend neither

upon filters nor upon a mechanical cooling system.

662. A package shall not include a pressure relief system from the containment

system that would allow the release of radioactive material to the environment

under the conditions of the tests specified in paras 719–724 and 726–729.

663. A package shall be so designed that if it were at the maximum normal

operating pressure and it were subjected to the tests specified in paras 719–724

and 726–729, the levels of strains in the containment system would not attain

values that would adversely affect the package in such a way that it would fail to

meet the applicable requirements.

664. A package shall not have a maximum normal operating pressure in excess

of a gauge pressure of 700 kPa.

665. A package containing low dispersible radioactive material shall be so

designed that any features added to the low dispersible radioactive material that

are not part of it, or any internal components of the packaging, shall not adversely

affect the performance of the low dispersible radioactive material.

666. A package shall be designed for an ambient temperature range of –40°C to

+38°C.

REQUIREMENTS FOR TYPE B(M) PACKAGES

667. Type B(M) packages shall meet the requirements for Type B(U) packages

specified in para. 652, except that for packages to be transported solely within a

specified country or solely between specified countries, conditions other than

those given in paras 639, 655–657 and 660–666 may be assumed with the

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

REQUIREMENTS FOR PACKAGES

101

approval of the competent authorities of these countries. Notwithstanding, the

requirements for Type B(U) packages specified in paras 655 and 660–666 shall be

met as far as practicable.

668. Intermittent venting of Type B(M) packages may be permitted during

transport, provided that the operational controls for venting are acceptable to the

relevant competent authorities.

REQUIREMENTS FOR TYPE C PACKAGES

669. Type C packages shall be designed to meet the requirements specified in

paras 607–621 and 636–649, except as specified in para. 648(a), and the

requirements specified in paras 653–657, 661–666 and 670–672.

670. A package shall be capable of meeting the assessment criteria prescribed

for tests in paras 659(b) and 663 after burial in an environment defined by a

thermal conductivity of 0.33 W/(m·K) and a temperature of 38°C in the steady

state. Initial conditions for the assessment shall assume that any thermal

insulation of the package remains intact, the package is at the maximum normal

operating pressure and the ambient temperature is 38°C.

671. A package shall be so designed that if it were at the maximum normal

operating pressure and subjected to:

(a) The tests specified in paras 719–724, it would restrict the loss of

radioactive contents to not more than 10

–6

per hour.

(b) The test sequences in para. 734:

(i) It would retain sufficient shielding to ensure that the radiation level

1 m from the surface of the package would not exceed 10 mSv/h with

the maximum radioactive contents that the package is designed to

contain.

(ii) It would restrict the accumulated loss of radioactive contents in a

period of one week to not more than 10A

for krypton-85 and not

more than A

for all other radionuclides.

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

SECTION VI

102

Where mixtures of different radionuclides are present, the provisions of

paras 405–407 shall apply, except that for krypton-85 an effective A

(i) value

equal to 10A

may be used. For case (a), the assessment shall take into account the

external contamination limits of para. 508.

672. A package shall be so designed that there will be no rupture of the

containment system following performance of the enhanced water immersion test

specified in para. 730.

REQUIREMENTS FOR PACKAGES CONTAINING FISSILE MATERIAL

673. Fissile material shall be transported so as to:

(a) Maintain subcriticality during routine, normal and accident conditions of

transport; in particular, the following contingencies shall be considered:

(i) Leakage of water into or out of packages;

(ii) Loss of efficiency of built-in neutron absorbers or moderators;

(iii) Rearrangement of the contents either within the package or as a result

of loss from the package;

(iv) Reduction of spaces within or between packages;

(v) Packages becoming immersed in water or buried in snow;

(vi) Temperature changes.

(b) Meet the requirements:

(i) Of para. 636 except for unpackaged material when specifically

allowed by para. 417(e);

(ii) Prescribed elsewhere in these Regulations that pertain to the

radioactive properties of the material;

(iii) Of para. 637 unless the material is excepted by para. 417;

(iv) Of paras 676–686, unless the material is excepted by para. 417, 674 or

675.

674. Packages containing fissile material that meets the requirements of

para. 674(d) and one of the provisions of para. 674(a)–(c) are excepted from the

requirements of paras 676–686.

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

REQUIREMENTS FOR PACKAGES

103

(a) Packages containing fissile material in any form provided that:

(i) The smallest external dimension of the package is not less than 10 cm.

(ii) The CSI of the package is calculated using the following formula:

CSI = 50 × 5 × {[mass of uranium-235 in package (g)]/Z

+ [mass of other fissile nuclides

in package (g)]/280}

where the values of Z are taken from Table 13.

(iii) The CSI of any package does not exceed 10.

(b) Packages containing fissile material in any form provided that:

(i) The smallest external dimension of the package is not less than 30 cm.

(ii) The package, after being subjected to the tests specified in

paras 719–724:

― Retains its fissile material contents;

― Preserves the minimum overall outside dimensions of the package

to at least 30 cm;

― Prevents the entry of a 10 cm cube.

(iii) The CSI of the package is calculated using the following formula:

CSI = 50 × 2 × {[mass of uranium-235 in package (g)]/Z

+ [mass of other fissile nuclides

in package (g)] / 280}

where the values of Z are taken from Table 13.

(iv) The CSI of any package does not exceed 10.

Plutonium may be of any isotopic composition provided that the amount of

plutonium-241 is less than that of plutonium-240 in the package.

TABLE 13. VALUES OF Z FOR CALCULATION OF CSI IN ACCORDANCE

WITH PARA. 674

Enrichment

Uranium enriched up to 1.5% 2200

Uranium enriched up to 5% 850

Uranium enriched up to 10% 660

Uranium enriched up to 20% 580

Uranium enriched up to 100% 450

If a package contains uranium with varying enrichments of uranium-235, then the value

corresponding to the highest enrichment shall be used for Z.

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

SECTION VI

104

(i) The smallest external dimension of the package is not less than 10 cm.

(ii) The package, after being subjected to the tests specified in

paras 719–724:

― Retains its fissile material contents;

― Preserves the minimum overall outside dimensions of the package

to at least 10 cm;

― Prevents the entry of a 10 cm cube.

(iii) The CSI of the package is calculated using the following formula:

CSI = 50 × 2 × {[mass of uranium-235 in package (g)]/450

+ [mass of other fissile nuclides

in package (g)]/280}

(iv) The maximum mass of fissile nuclides in any package does not

exceed 15 g.

(d) The total mass of beryllium, hydrogenous material enriched in deuterium,

graphite and other allotropic forms of carbon in an individual package shall

not be greater than the mass of fissile nuclides in the package except where

their total concentration does not exceed 1 g in any 1000 g of material.

Beryllium incorporated in copper alloys up to 4% by weight of the alloy

does not need to be considered.

675. Packages containing not more than 1000 g of plutonium are excepted from

the application of paras 676–686 provided that:

(a) Not more than 20% of the plutonium by mass is fissile nuclides.

(b) The CSI of the package is calculated using the following formula:

CSI = 50 × 2 × [mass of plutonium (g)/1000]

more than 1% of the mass of the plutonium.

Contents specification for assessments of package designs containing fissile

material

676. Where the chemical or physical form, isotopic composition, mass or

concentration, moderation ratio or density, or geometric configuration is not

known, the assessments of paras 680–685 shall be performed assuming that each

parameter that is not known has the value that gives the maximum neutron

multiplication consistent with the known conditions and parameters in these

assessments.

677. For irradiated nuclear fuel, the assessments of paras 680–685 shall be based

on an isotopic composition demonstrated to provide either:

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

REQUIREMENTS FOR PACKAGES

105

(a) The maximum neutron multiplication during the irradiation history; or

(b) A conservative estimate of the neutron multiplication for the package

assessments. After irradiation but prior to shipment, a measurement shall be

performed to confirm the conservatism of the isotopic composition.

Geometry and temperature requirements

678. The package, after being subjected to the tests specified in paras 719–724,

shall:

(a) Preserve the minimum overall outside dimensions of the package to at least

10 cm;

(b) Prevent the entry of a 10 cm cube.

679. The package shall be designed for an ambient temperature range of –40°C

to +38°C unless the competent authority specifies otherwise in the certificate of

approval for the package design.

Assessment of an individual package in isolation

680. For a package in isolation, it shall be assumed that water can leak into or out

of all void spaces of the package, including those within the containment system.

However, if the design incorporates special features to prevent such leakage of

water into or out of certain void spaces, even as a result of error, absence of

leakage may be assumed in respect of those void spaces. Special features shall

include either of the following:

(a) Multiple high standard water barriers, not less than two of which would

remain watertight if the package were subject to the tests prescribed in

para. 685(b), a high degree of quality control in the manufacture,

maintenance and repair of packagings, and tests to demonstrate the closure

of each package before each shipment; or

(b) For packages containing uranium hexafluoride only, with a maximum

uranium enrichment of 5 mass per cent uranium-235:

(i) Packages where, following the tests prescribed in para. 685(b), there

is no physical contact between the valve and any other component of

the packaging other than at its original point of attachment and where,

in addition, following the test prescribed in para. 728, the valves

remain leaktight;

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

SECTION VI

106

(ii) A high degree of quality control in the manufacture, maintenance and

repair of packagings, coupled with tests to demonstrate closure of

each package before each shipment.

681. It shall be assumed that the confinement system is closely reflected by at

least 20 cm of water or such greater reflection as may additionally be provided by

the surrounding material of the packaging. However, when it can be

demonstrated that the confinement system remains within the packaging

following the tests prescribed in para. 685(b), close reflection of the package by

at least 20 cm of water may be assumed in para. 682(c).

682. The package shall be subcritical under the conditions of paras 680 and 681

and with the package conditions that result in the maximum neutron

multiplication consistent with:

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

(b) The tests specified in para. 684(b);

683. For packages to be transported by air:

(a) The package shall be subcritical under conditions consistent with the

Type C package tests specified in para. 734, assuming reflection by at least

20 cm of water but no water in-leakage.

(b) In the assessment of para. 682, allowance shall not be made for special

features of para. 680 unless, following the Type C package tests specified in

para. 734 and, subsequently, the water in-leakage test of para. 733, leakage

of water into or out of the void spaces is prevented.

Assessment of package arrays under normal conditions of transport

684. A number N shall be derived, such that five times N packages shall be

subcritical for the arrangement and package conditions that provide the

maximum neutron multiplication consistent with the following:

(a) There shall not be anything between the packages, and the package

arrangement shall be reflected on all sides by at least 20 cm of water.

(b) The state of the packages shall be their assessed or demonstrated condition

if they had been subjected to the tests specified in paras 719–724.

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

REQUIREMENTS FOR PACKAGES

107

Assessment of package arrays under accident conditions of transport

685. A number N shall be derived, such that two times N packages shall be

subcritical for the arrangement and package conditions that provide the

maximum neutron multiplication consistent with the following:

(a) Hydrogenous moderation between the packages and the package

arrangement reflected on all sides by at least 20 cm of water.

(b) The tests specified in paras 719–724 followed by whichever of the

following is the more limiting:

(i) The tests specified in para. 727(b) and either para. 727(c) for

packages having a mass not greater than 500 kg and an overall density

not greater than 1000 kg/m

based on the external dimensions or

para. 727(a) for all other packages, followed by the test specified in

para. 728 and completed by the tests specified in paras 731–733; or

(ii) The test specified in para. 729.

following the tests specified in para. 685(b), it shall be assumed that fissile

material escapes from each package in the array and that all of the fissile

material shall be arranged in the configuration and moderation that results

in the maximum neutron multiplication with close reflection by at least

20 cm of water.

Determination of criticality safety index for packages

686. The CSI for packages containing fissile material shall be obtained by

dividing the number 50 by the smaller of the two values of N derived in paras 684

and 685 (i.e. CSI = 50/N). The value of the CSI may be zero, provided that an

unlimited number of packages are subcritical (i.e. N is effectively equal to

infinity in both cases).

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109

Section VII

TEST PROCEDURES

DEMONSTRATION OF COMPLIANCE

701. Demonstration of compliance with the performance standards required in

Section VI shall be accomplished by any of the following methods listed below or

by a combination thereof:

(a) Performance of tests with specimens representing LSA-III material, or

special form radioactive material, or low dispersible radioactive material,

or with prototypes or samples of the packaging, where the contents of the

specimen or the packaging for the tests shall simulate as closely as

practicable the expected range of radioactive contents and the specimen or

packaging to be tested shall be prepared as presented for transport.

(b) Reference to previous satisfactory demonstrations of a sufficiently similar

nature.

features that are significant with respect to the item under investigation

when engineering experience has shown the results of such tests to be

suitable for design purposes. When a scale model is used, the need for

adjusting certain test parameters, such as penetrator diameter or

compressive load, shall be taken into account.

(d) Calculation, or reasoned argument, when the calculation procedures and

parameters are generally agreed to be reliable or conservative.

702. After the specimen, prototype or sample has been subjected to the tests,

appropriate methods of assessment shall be used to ensure that the requirements

of this section have been fulfilled in compliance with the performance and

acceptance standards prescribed in Section VI.

LEACHING TEST FOR LSA-III MATERIAL AND LOW DISPERSIBLE

RADIOACTIVE MATERIAL

703. A solid material sample representing the entire contents of the package

shall be immersed for 7 days in water at ambient temperature. The volume of

water to be used in the test shall be sufficient to ensure that at the end of the 7 day

test period, the free volume of the unabsorbed and unreacted water remaining

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110

shall be at least 10% of the volume of the solid test sample itself. The water shall

have an initial pH of 6–8 and a maximum conductivity of 1 mS/m at 20°C. The

total activity of the free volume of water shall be measured following the 7 day

immersion of the test sample.

TESTS FOR SPECIAL FORM RADIOACTIVE MATERIAL

General

704. Specimens that comprise or simulate special form radioactive material

shall be subjected to the impact test, the percussion test, the bending test and the

heat test specified in paras 705–708. A different specimen may be used for each

of the tests. Following each test, a leaching assessment or volumetric leakage test

shall be performed on the specimen by a method no less sensitive than the

methods given in para. 710 for indispersible solid material or in para. 711 for

encapsulated material.

Test met hod s

705. Impact test: The specimen shall drop onto the target from a height of 9 m.

The target shall be as defined in para. 717.

706. Percussion test: The specimen shall be placed on a sheet of lead that is

supported by a smooth solid surface and struck by the flat face of a mild steel bar

so as to cause an impact equivalent to that resulting from a free drop of 1.4 kg

through 1 m. The lower part of the bar shall be 25 mm in diameter with the edges

rounded off to a radius of 3.0 ± 0.3 mm. The lead, of hardness number 3.5–4.5 on

the Vickers scale and not more than 25 mm thick, shall cover an area greater than

that covered by the specimen. A fresh surface of lead shall be used for each

impact. The bar shall strike the specimen so as to cause maximum damage.

707. Bending test: The test shall apply only to long, slender sources with both a

minimum length of 10 cm and a length to minimum width ratio of not less than

10. The specimen shall be rigidly clamped in a horizontal position so that one half

of its length protrudes from the face of the clamp. The orientation of the specimen

shall be such that the specimen will suffer maximum damage when its free end is

struck by the flat face of a steel bar. The bar shall strike the specimen so as to

cause an impact equivalent to that resulting from a free vertical drop of 1.4 kg

through 1 m. The lower part of the bar shall be 25 mm in diameter with the edges

rounded off to a radius of 3.0 ± 0.3 mm.

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708. Heat test: The specimen shall be heated in air to a temperature of 800°C and

held at that temperature for a period of 10 min and shall then be allowed to cool.

709. Specimens that comprise or simulate radioactive material enclosed in a

sealed capsule may be excepted from:

(a) The tests prescribed in paras 705 and 706, provided that the specimens are

alternatively subjected to the impact test prescribed in the International

Organization for Standardization document ISO 2919: Sealed Radioactive

Sources — Classification [13]:

(i) The Class 4 impact test if the mass of the special form radioactive

material is less than 200 g;

(ii) The Class 5 impact test if the mass of the special form radioactive

material is more than 200 g but less than 500 g.

(b) The test prescribed in para. 708, provided the specimens are alternatively

subjected to the Class 6 temperature test specified in ISO 2919 [13].

Leaching and volumetric leakage assessment methods

710. For specimens that comprise or simulate indispersible solid material, a

leaching assessment shall be performed as follows:

(a) The specimen shall be immersed for 7 days in water at ambient

temperature. The volume of water to be used in the test shall be sufficient to

ensure that at the end of the 7 day test period the free volume of the

unabsorbed and unreacted water remaining shall be at least 10% of the

volume of the solid test sample itself. The water shall have an initial pH of

6–8 and a maximum conductivity of 1 mS/m at 20°C.

(b) The water with the specimen shall then be heated to a temperature of

50 ± 5°C and maintained at this temperature for 4 h.

(d) The specimen shall then be kept for at least 7 days in still air at not less than

30°C and with a relative humidity of not less than 90%.

(e) The specimen shall then be immersed in water of the same specification as

that in (a) and the water with the specimen heated to 50 ± 5°C and

maintained at this temperature for 4 h.

(f) The activity of the water shall then be determined.

711. For specimens that comprise or simulate radioactive material enclosed in a

sealed capsule, either a leaching assessment or a volumetric leakage assessment

shall be performed as follows:

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112

(a) The leaching assessment shall consist of the following steps:

(i) The specimen shall be immersed in water at ambient temperature. The

water shall have an initial pH of 6–8 with a maximum conductivity of

1 mS/m at 20°C.

(ii) The water and the specimen shall be heated to a temperature of

50 ± 5°C and maintained at this temperature for 4 h.

(iii) The activity of the water shall then be determined.

(iv) The specimen shall then be kept for at least 7 days in still air at not

less than 30°C and with a relative humidity of not less than 90%.

(v) The process in (i), (ii) and (iii) shall be repeated.

(b) The alternative volumetric leakage assessment shall comprise any of the

tests prescribed in the International Organization for Standardization

document ISO 9978: Radiation Protection — Sealed Radioactive Sources

— Leakage Test Methods [9] provided that they are acceptable to the

competent authority.

TESTS FOR LOW DISPERSIBLE RADIOACTIVE MATERIAL

712. A specimen that comprises or simulates low dispersible radioactive

material shall be subjected to the enhanced thermal test specified in para. 736 and

the impact test specified in para. 737. A different specimen may be used for each

of the tests. Following each test, the specimen shall be subjected to the leach test

specified in para. 703. After each test it shall be determined if the applicable

requirements of para. 605 have been met.

TESTS FOR PACKAGES

Preparation of a specimen for testing

713. All specimens shall be inspected before testing in order to identify and

record faults or damage, including the following:

(a) Divergence from the design;

(b) Defects in manufacture;

(d) Distortion of features.

714. The containment system of the package shall be clearly specified.

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715. The external features of the specimen shall be clearly identified so that

reference may be made simply and clearly to any part of such a specimen.

Testing the integrity of the containment system and shielding and assessing

criticality safety

716. After each of the applicable tests specified in paras 718–737:

(a) Faults and damage shall be identified and recorded.

(b) It shall be determined whether the integrity of the containment system and

shielding has been retained to the extent required in Section VI for the

package under test.

assumptions and conditions used in the assessments required by

paras 673–686 for one or more packages are valid.

Target for drop tests

717. The target for the drop test specified in paras 705, 722, 725(a), 727 and 735

shall be a flat, horizontal surface of such a character that any increase in its

resistance to displacement or deformation upon impact by the specimen would

not significantly increase damage to the specimen.

Test for packagings designed to contain uranium hexafluoride

718. Specimens that comprise or simulate packagings designed to contain 0.1 kg

or more of uranium hexafluoride shall be tested hydraulically at an internal

pressure of at least 1.38 MPa, but when the test pressure is less than 2.76 MPa, the

design shall require multilateral approval. For retesting packagings, any other

equivalent non-destructive testing may be applied, subject to multilateral

approval.

Tests for demonstrating ability to withstand normal conditions of transport

719. The tests are the water spray test, the free drop test, the stacking test and the

penetration test. Specimens of the package shall be subjected to the free drop test,

the stacking test and the penetration test, preceded in each case by the water spray

test. One specimen may be used for all the tests, provided that the requirements of

para. 720 are fulfilled.

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720. The time interval between the conclusion of the water spray test and the

succeeding test shall be such that the water has soaked in to the maximum extent,

without appreciable drying of the exterior of the specimen. In the absence of any

evidence to the contrary, this interval shall be taken to be 2 h if the water spray is

applied from four directions simultaneously. No time interval shall elapse,

however, if the water spray is applied from each of the four directions

consecutively.

721. Water spray test: The specimen shall be subjected to a water spray test that

simulates exposure to rainfall of approximately 5 cm per hour for at least 1 h.

722. Free drop test: The specimen shall drop onto the target so as to suffer

maximum damage in respect of the safety features to be tested:

(a) The height of drop measured from the lowest point of the specimen to the

upper surface of the target shall be not less than the distance specified in

Table 14 for the applicable mass. The target shall be as defined in para. 717.

(b) For rectangular fibreboard or wood packages not exceeding a mass of

50 kg, a separate specimen shall be subjected to a free drop onto each

corner from a height of 0.3 m.

separate specimen shall be subjected to a free drop onto each of the quarters

of each rim from a height of 0.3 m.

723. Stacking test: Unless the shape of the packaging effectively prevents

stacking, the specimen shall be subjected, for a period of 24 h, to a compressive

load equal to the greater of the following:

(a) The equivalent of 5 times the maximum weight of the package;

(b) The equivalent of 13 kPa multiplied by the vertically projected area of the

package.

TABLE 14. FREE DROP DISTANCE FOR TESTING PACKAGES TO

NORMAL CONDITIONS OF TRANSPORT

Package mass (kg) Free drop distance (m)

package mass < 5 000 1.2

5 000 ≤ package mass < 10 000 0.9

10 000 ≤ package mass < 15 000 0.6

15 000 ≤ package mass 0.3

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The load shall be applied uniformly to two opposite sides of the specimen, one of

which shall be the base on which the package would typically rest.

724. Penetration test: The specimen shall be placed on a rigid, flat, horizontal

surface that will not move significantly while the test is being carried out:

(a) A bar 3.2 cm in diameter with a hemispherical end and a mass of 6 kg shall

be dropped and directed to fall, with its longitudinal axis vertical, onto the

centre of the weakest part of the specimen, so that, if it penetrates

sufficiently far, it will hit the containment system. The bar shall not be

significantly deformed by the test performance.

(b) The height of drop of the bar measured from its lower end to the intended

point of impact on the upper surface of the specimen shall be 1 m.

Additional tests for Type A packages designed for liquids and gases

725. A specimen, or separate specimens, shall be subjected to each of the

following tests unless it can be demonstrated that one test is more severe for the

specimen in question than the other, in which case one specimen shall be

subjected to the more severe test:

(a) Free drop test: The specimen shall drop onto the target so as to suffer the

maximum damage in respect of containment. The height of the drop

measured from the lowest part of the specimen to the upper surface of the

target shall be 9 m. The target shall be as defined in para. 717.

(b) Penetration test: The specimen shall be subjected to the test specified in

para. 724, except that the height of the drop shall be increased to 1.7 m from

the 1 m specified in para. 724(b).

Tests for demonstrating ability to withstand accident conditions of transport

726. The specimen shall be subjected to the cumulative effects of the tests

specified in paras 727 and 728, in that order. Following these tests, either this

specimen or a separate specimen shall be subjected to the effect(s) of the water

immersion test(s), as specified in para. 729 and, if applicable, para. 730.

727. Mechanical test: The mechanical test consists of three different drop tests.

Each specimen shall be subjected to the applicable drops, as specified in

para. 659 or para. 685. The order in which the specimen is subjected to the drops

shall be such that, on completion of the mechanical test, the specimen shall have

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116

suffered such damage as will lead to maximum damage in the thermal test that

follows:

(a) For drop I, the specimen shall drop onto the target so as to suffer maximum

damage, and the height of the drop measured from the lowest point of the

specimen to the upper surface of the target shall be 9 m. The target shall be

as defined in para. 717.

(b) For drop II, the specimen shall drop onto a bar rigidly mounted

perpendicularly on the target so as to suffer maximum damage. The height

of the drop measured from the intended point of impact of the specimen to

the upper surface of the bar shall be 1 m. The bar shall be of solid mild steel

of circular section, 15.0 ± 0.5 cm in diameter and 20 cm long, unless a

longer bar would cause greater damage, in which case a bar of sufficient

length to cause maximum damage shall be used. The upper end of the bar

shall be flat and horizontal with its edge rounded off to a radius of not more

than 6 mm. The target on which the bar is mounted shall be as described in

para. 717.

positioning the specimen on the target so as to suffer maximum damage by

the drop of a 500 kg mass from 9 m onto the specimen. The mass shall

consist of a solid mild steel plate 1 m × 1 m and shall fall in a horizontal

attitude. The lower face of the steel plate shall have its edges and corners

rounded off to a radius of not more than 6 mm. The height of the drop shall

be measured from the underside of the plate to the highest point of the

specimen. The target on which the specimen rests shall be as defined in

para. 717.

728. Thermal test: The specimen shall be in thermal equilibrium under

conditions of an ambient temperature of 38°C, subject to the solar insolation

conditions specified in Table 12 and subject to the design maximum rate of

internal heat generation within the package from the radioactive contents.

Alternatively, any of these parameters are allowed to have different values prior

to, and during, the test, provided due account is taken of them in the subsequent

assessment of package response. The thermal test shall then consist of (a)

followed by (b).

(a) Exposure of a specimen for a period of 30 min to a thermal environment

that provides a heat flux at least equivalent to that of a hydrocarbon fuel–air

fire in sufficiently quiescent ambient conditions to give a minimum average

flame emissivity coefficient of 0.9 and an average temperature of at least

800°C, fully engulfing the specimen, with a surface absorptivity coefficient

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of 0.8 or that value that the package may be demonstrated to possess if

exposed to the fire specified.

(b) Exposure of the specimen to an ambient temperature of 38°C, subject to the

solar insolation conditions specified in Table 12 and subject to the design

maximum rate of internal heat generation within the package by the

radioactive contents for a sufficient period to ensure that temperatures in

the specimen are everywhere decreasing and/or are approaching initial

steady state conditions. Alternatively, any of these parameters are allowed

to have different values following cessation of heating, provided due

account is taken of them in the subsequent assessment of package response.

During and following the test, the specimen shall not be artificially cooled

and any combustion of materials of the specimen shall be permitted to

proceed naturally.

729. Water immersion test: The specimen shall be immersed under a head of

water of at least 15 m for a period of not less than 8 h in the attitude that will lead

to maximum damage. For demonstration purposes, an external gauge pressure of

at least 150 kPa shall be considered to meet these conditions.

Enhanced water immersion test for Type B(U) and Type B(M) packages

containing more than 10

and Type C packages

730. Enhanced water immersion test: The specimen shall be immersed under a

head of water of at least 200 m for a period of not less than 1 h. For demonstration

purposes, an external gauge pressure of at least 2 MPa shall be considered to meet

these conditions.

Water leakage test for packages containing fissile material

731. Packages for which water in-leakage or out-leakage to the extent that

results in greatest reactivity has been assumed for purposes of assessment under

paras 680–685 shall be excepted from the test.

732. Before the specimen is subjected to the water leakage test specified below,

it shall be subjected to the tests in para. 727(b) and either para. 727(a) or 727(c),

as required by para. 685 and the test specified in para. 728.

733. The specimen shall be immersed under a head of water of at least 0.9 m for

a period of not less than 8 h and in the attitude for which maximum leakage is

expected.

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Tests for Type C packages

734. Specimens shall be subjected to the effects of the following test sequences:

(a) The tests specified in paras 727(a), 727(c), 735 and 736, in this order;

(b) The test specified in para. 737.

Separate specimens are allowed to be used for the sequence in (a) and for (b).

735. Puncture–tearing test: The specimen shall be subjected to the damaging

effects of a vertical solid probe made of mild steel. The orientation of the package

specimen and the impact point on the package surface shall be such as to cause

maximum damage at the conclusion of the test sequence specified in para. 734(a):

(a) The specimen, representing a package having a mass of less than 250 kg,

shall be placed on a target and subjected to a probe having a mass of 250 kg

falling from a height of 3 m above the intended impact point. For this test

the probe shall be a 20 cm diameter cylindrical bar with the striking end

forming the frustum of a right circular cone with the following dimensions:

30 cm height and 2.5 cm diameter at the top with its edge rounded off to a

radius of not more than 6 mm. The target on which the specimen is placed

shall be as specified in para. 717.

(b) For packages having a mass of 250 kg or more, the base of the probe shall

be placed on a target and the specimen dropped onto the probe. The height

of the drop, measured from the point of impact with the specimen to the

upper surface of the probe, shall be 3 m. The probe for this test shall have

the same properties and dimensions as specified in (a), except that the

length and mass of the probe shall be such as to cause maximum damage to

the specimen. The target on which the base of the probe is placed shall be as

specified in para. 717.

736. Enhanced thermal test: The conditions for this test shall be as specified in

para. 728, except that the exposure to the thermal environment shall be for a

period of 60 min.

737. Impact test: The specimen shall be subject to an impact on a target at a

velocity of not less than 90 m/s, at such an orientation as to suffer maximum

damage. The target shall be as defined in para. 717, except that the target surface

may be at any orientation as long as the surface is normal to the specimen path.

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119

Section VIII

APPROVAL AND ADMINISTRATIVE REQUIREMENTS

GENERAL

801. For package designs where it is not required that a competent authority

issue a certificate of approval, the consignor shall, on request, make available for

inspection by the relevant competent authority, documentary evidence of the

compliance of the package design with all the applicable requirements.

802. Competent authority approval shall be required for the following:

(a) Designs for:

(i) Special form radioactive material (see paras 803, 804 and 823);

(ii) Low dispersible radioactive material (see paras 803 and 804);

(iii) Fissile material excepted under para. 417(f) (see paras 805 and 806);

(iv) Packages containing 0.1 kg or more of uranium hexafluoride

(see para. 807);

(v) Packages containing fissile material, unless excepted by para. 417,

674 or 675 (see paras 814–816 and 820);

(vi) Type B(U) packages and Type B(M) packages (see paras 808–813 and

820);

(vii) Type C packages (see paras 808–810).

(b) Special arrangements (see paras 829–831).

(d) Radiation protection programme for special use vessels (see para. 576(a)).

(e) Calculation of radionuclide values that are not listed in Table 2 (see

para. 403(a)).

(f) Calculation of alternative activity limits for an exempt consignment of

instruments or articles (see para. 403(b)).

The certificates of approval for the package design and the shipment may be

combined into a single certificate.

Although this publication is identified as a new edition, there are no changes that affect

the administrative and approval requirements in respect of radioactive material and packages

approved under the previous editions, amendments or revisions since the 1996 Edition.

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120

APPROVAL OF SPECIAL FORM RADIOACTIVE MATERIAL AND

LOW DISPERSIBLE RADIOACTIVE MATERIAL

803. The design for special form radioactive material shall require unilateral

approval. The design for low dispersible radioactive material shall require

multilateral approval. In both cases, an application for approval shall include:

(a) A detailed description of the radioactive material or, if a capsule, the

contents; particular reference shall be made to both physical and chemical

states.

(b) A detailed statement of the design of any capsule to be used.

evidence based on calculative methods, to show that the radioactive

material is capable of meeting the performance standards, or other evidence

that the special form radioactive material or low dispersible radioactive

material meets the applicable requirements of these Regulations.

(d) A specification of the applicable management system, as required in

para. 306.

(e) Any proposed pre-shipment actions for use in the consignment of special

form radioactive material or low dispersible radioactive material.

804. The competent authority shall establish a certificate of approval stating that

the approved design meets the requirements for special form radioactive material

or low dispersible radioactive material and shall attribute to that design an

identification mark.

APPROVAL OF MATERIAL EXCEPTED FROM FISSILE CLASSIFICATION

805. The design for a fissile material excepted from “FISSILE” classification in

accordance with Table 1, under para. 417(f) shall require multilateral approval.

An application for approval shall include:

(a) A detailed description of the material; particular reference shall be made to

both physical and chemical states.

(b) A statement of the tests that have been carried out and their results, or

evidence based on calculative methods, to show that the material is capable

of meeting the requirements specified in para. 606.

para. 306.

(d) A statement of specific actions to be taken prior to shipment.

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806. The competent authority shall establish a certificate of approval stating that

the approved material meets the requirements for fissile material excepted by the

competent authority in accordance with para. 606 and shall attribute to that

design an identification mark.

APPROVAL OF PACKAGE DESIGNS

Approval of package designs to contain uranium hexafluoride

807. The approval of designs for packages containing 0.1 kg or more of uranium

hexafluoride requires that:

(a) Each design that meets the requirements of para. 634 shall require

multilateral approval.

(b) Each design that meets the requirements of paras 631–633 shall require

unilateral approval by the competent authority of the country of origin of

the design, unless multilateral approval is otherwise required by these

Regulations.

satisfy the competent authority that the design meets the requirements of

para. 631 and a specification of the applicable management system, as

required in para. 306.

(d) The competent authority shall establish a certificate of approval stating that

the approved design meets the requirements of para. 631 and shall attribute

to that design an identification mark.

Approval of Type B(U) and Type C package designs

808. Each Type B(U) and Type C package design shall require unilateral

approval, except that:

(a) A package design for fissile material, which is also subject to

paras 814–816, shall require multilateral approval.

(b) A Type B(U) package design for low dispersible radioactive material shall

require multilateral approval.

809. An application for approval shall include:

(a) A detailed description of the proposed radioactive contents with reference

to their physical and chemical states and the nature of the radiation emitted;

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122

(b) A detailed statement of the design, including complete engineering

drawings and schedules of materials and methods of manufacture;

evidence based on calculative methods or other evidence that the design is

adequate to meet the applicable requirements;

(d) The proposed operating and maintenance instructions for the use of the

packaging;

(e) If the package is designed to have a maximum normal operating pressure in

excess of 100 kPa gauge, a specification of the materials of manufacture of

the containment system, the samples to be taken and the tests to be made;

(f) Where the proposed radioactive contents are irradiated nuclear fuel, the

applicant shall state and justify any assumption in the safety analysis

relating to the characteristics of the fuel and describe any pre-shipment

measurement required by para. 677(b);

(g) Any special stowage provisions necessary to ensure the safe dissipation of

heat from the package considering the various modes of transport to be used

and the type of conveyance or freight container;

(h) A reproducible illustration, not larger than 21 cm × 30 cm, showing the

make-up of the package;

(i) A specification of the applicable management system as required in

para. 306.

810. The competent authority shall establish a certificate of approval stating that

the approved design meets the requirements for Type B(U) or Type C packages

and shall attribute to that design an identification mark.

Approval of Type B(M) package designs

811. Each Type B(M) package design, including those for fissile material which

are also subject to paras 814–816 and those for low dispersible radioactive

material, shall require multilateral approval.

812. An application for approval of a Type B(M) package design shall include, in

addition to the information required in para. 809 for Type B(U) packages:

(a) A list of the requirements specified in paras 639, 655–657 and 660–666

with which the package does not conform;

(b) Any proposed supplementary operational controls to be applied during

transport not regularly provided for in these Regulations, but which are

necessary to ensure the safety of the package or to compensate for the

deficiencies listed in (a);

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special loading, carriage, unloading or handling procedures;

(d) A statement of the range of ambient conditions (temperature, solar

insolation) that are expected to be encountered during transport and which

have been taken into account in the design.

813. The competent authority shall establish a certificate of approval stating that

the approved design meets the applicable requirements for Type B(M) packages

and shall attribute to that design an identification mark.

Approval of package designs to contain fissile material

814. Each package design for fissile material that is not excepted by any of the

paras 417(a)–(f), 674 and 675 shall require multilateral approval.

815. An application for approval shall include all information necessary to

satisfy the competent authority that the design meets the requirements of

para. 673 and a specification of the applicable management system, as required in

para. 306.

816. The competent authority shall establish a certificate of approval stating that

the approved design meets the requirements of para. 673 and shall attribute to that

design an identification mark.

APPROVAL OF ALTERNATIVE ACTIVITY LIMITS FOR

AN EXEMPT CONSIGNMENT OF INSTRUMENTS OR ARTICLES

817. Alternative activity limits for an exempt consignment of instruments or

articles in accordance with para. 403(b) shall require multilateral approval. An

application for approval shall include:

(a) An identification and detailed description of the instrument or article, its

intended uses and the radionuclide(s) incorporated;

(b) The maximum activity of the radionuclide(s) in the instrument or article;

(d) The chemical and physical forms of the radionuclide(s) contained in the

instrument or article;

(e) Details of the construction and design of the instrument or article,

particularly as related to the containment and shielding of the radionuclide

in routine, normal and accident conditions of transport;

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124

(f) The applicable management system, including the quality testing and

verification procedures to be applied to radioactive sources, components

and finished products to ensure that the maximum specified activity of

radioactive material or the maximum radiation levels specified for the

instrument or article are not exceeded, and that the instruments or articles

are constructed according to the design specifications;

(g) The maximum number of instruments or articles expected to be shipped per

consignment and annually;

(h) Dose assessments in accordance with the principles and methodologies set

out in the BSS [2], including individual doses to transport workers and

members of the public and, if appropriate, collective doses arising from

routine, normal and accident conditions of transport, based on

representative transport scenarios that the consignments are subject to.

818. The competent authority shall establish a certificate of approval stating that

the approved alternative activity limit for an exempt consignment of instruments

or articles meets the requirements of para. 403(b) and shall attribute to that

certificate an identification mark.

TRANSITIONAL ARRANGEMENTS

Packages not requiring competent authority approval of design under



the 1985 and 1985 (As Amended 1990) Editions of these Regulations

819. Packages not requiring competent authority approval of design (excepted

packages, Type IP-1, Type IP-2, Type IP-3 and Type A packages) shall meet this

Edition of these Regulations in full, except that packages that meet the

requirements of the 1985 or 1985 (As Amended 1990) Editions of these

Regulations:

(a) May continue in transport provided that they were prepared for transport

prior to 31 December 2003 and are subject to the requirements of para. 822,

if applicable;

(b) May continue to be used, provided that:

(i) They were not designed to contain uranium hexafluoride.

(ii) The applicable requirements of para. 306 of this Edition of these

Regulations are applied.

(iii) The activity limits and classification in Section IV of this Edition of

these Regulations are applied.

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

APPROVAL AND ADMINISTRATIVE REQUIREMENTS

125

(iv) The requirements and controls for transport in Section V of this

Edition of these Regulations are applied.

(v) The packaging was not manufactured or modified after

31 December 2003.

Packages approved under the 1973, 1973 (As Amended), 1985 and 1985



(As Amended 1990) Editions of these Regulations

820. Packages requiring competent authority approval of the design shall meet

this Edition of these Regulations in full unless the following conditions are met:

(a) The packagings were manufactured to a package design approved by the

competent authority under the provisions of the 1973 or 1973

(As Amended) or the 1985 or 1985 (As Amended 1990) Editions of these

Regulations.

(b) The package design is subject to multilateral approval.

Regulations are applied.

(d) The activity limits and classification in Section IV of this Edition of these

Regulations are applied.

(e) The requirements and controls for transport in Section V of this Edition of

these Regulations are applied.

(f) For a package containing fissile material and transported by air, the

requirement of para. 683 is met.

(g) For packages that meet the requirements of the 1973 or 1973 (As Amended)

Editions of these Regulations:

(i) The packages retain sufficient shielding to ensure that the radiation

level at 1 m from the surface of the package would not exceed

10 mSv/h in the accident conditions of transport defined in the 1973

Revised or 1973 Revised (As Amended) Editions of these

Regulations with the maximum radioactive contents which the

package is authorized to contain.

(ii) The packages do not utilize continuous venting.

(iii) A serial number in accordance with the provision of para. 535 is

assigned to and marked on the outside of each packaging.

821. No new manufacture of packagings to a package design meeting the

provisions of the 1973, 1973 (As Amended), 1985 and 1985 (As Amended 1990)

Editions of these Regulations shall be permitted to commence.

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

SECTION VIII

126

Packages excepted from the requirements for fissile material under

the 2009 Edition of these Regulations

822. Packages containing fissile material that is excepted from classification as

“FISSILE” according to para. 417(a)(i) or (iii) of the 2009 Edition of these

Regulations prepared for transport before 31 December 2014 may continue in

transport and may continue to be classified as non-fissile or fissile-excepted

except that the consignment limits in Table 4 of the 2009 Edition of these

Regulations shall apply to the conveyance. The consignment shall be transported

under exclusive use.

Special form radioactive material approved under the 1973, 1973



(As Amended), 1985 and 1985 (As Amended 1990) 

Editions of these Regulations

823. Special form radioactive material manufactured to a design that had

received unilateral approval by the competent authority under the 1973, 1973

(As Amended), 1985 or 1985 (As Amended 1990) Editions of these Regulations

may continue to be used when in compliance with the mandatory management

system in accordance with the applicable requirements of para. 306. No new

manufacture of such special form radioactive material shall be permitted to

commence.

NOTIFICATION AND REGISTRATION OF SERIAL NUMBERS

824. The competent authority shall be informed of the serial number of each

packaging manufactured to a design approved under paras 808, 811, 814 and 820.

APPROVAL OF SHIPMENTS

825. Multilateral approval shall be required for:

(a) The shipment of Type B(M) packages not conforming with the requirements

of para. 639 or designed to allow controlled intermittent venting.

(b) The shipment of Type B(M) packages containing radioactive material with

an activity greater than 3000A

or 3000A

, as appropriate, or 1000 TBq,

whichever is the lower.

of the packages in a single freight container or in a single conveyance

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

APPROVAL AND ADMINISTRATIVE REQUIREMENTS

127

exceeds 50. Excluded from this requirement shall be shipments by seagoing

vessels, if the sum of the CSIs does not exceed 50 for any hold,

compartment or defined deck area and the distance of 6 m between groups

of packages or overpacks, as required in Table 11, is met.

(d) Radiation protection programmes for shipments by special use vessels in

accordance with para. 576(a).

826. A competent authority may authorize transport through or into its country

without shipment approval, by a specific provision in its design approval.

827. An application for approval of shipment shall include:

(a) The period of time, related to the shipment, for which the approval is

sought;

(b) The actual radioactive contents, the expected modes of transport, the type

of conveyance and the probable or proposed route;

controls, referred to in the certificates of approval for the package design, if

applicable, issued under paras 810, 813 and 816, are to be put into effect.

828. Upon approval of the shipment, the competent authority shall issue a

certificate of approval.

APPROVAL OF SHIPMENTS UNDER SPECIAL ARRANGEMENT

829. Each consignment transported under special arrangement shall require

multilateral approval.

830. An application for approval of shipments under special arrangement shall

include all the information necessary to satisfy the competent authority that the

overall level of safety in transport is at least equivalent to that which would be

provided if all the applicable requirements of these Regulations had been met.

The application shall also include:

(a) A statement of the respects in which, and of the reasons why, the shipment

cannot be made in full accordance with the applicable requirements;

(b) A statement of any special precautions or special administrative or

operational controls that are to be employed during transport to compensate

for the failure to meet the applicable requirements.

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

SECTION VIII

128

831. Upon approval of shipments under special arrangement, the competent

authority shall issue a certificate of approval.

COMPETENT AUTHORITY CERTIFICATES OF APPROVAL

Competent authority identification marks

832. Each certificate of approval issued by a competent authority shall be assigned

an identification mark. The mark shall be of the following generalized type:

VRI/Number/Type Code

(a) Except as provided in para. 833(b), VRI represents the international vehicle

registration identification code of the country issuing the certificate.

(b) The number shall be assigned by the competent authority and shall be

unique and specific with regard to the particular design, shipment or

alternative activity limit for exempt consignment. The identification mark

of the approval of shipment shall be clearly related to the identification

mark of the approval of design.

types of certificate of approval issued:

AF Type A package design for fissile material

B(U) Type B(U) package design (B(U)F if for fissile material)

B(M) Type B(M) package design (B(M)F if for fissile material)

C Type C package design (CF if for fissile material)

IF Industrial package design for fissile material

S Special form radioactive material

LD Low dispersible radioactive material

FE Fissile material complying with the requirements of para. 606

T Shipment

X Special arrangement

AL Alternative activity limits for an exempt consignment of

instruments or articles

In the case of package designs for non-fissile or fissile-excepted uranium

hexafluoride, where none of the above codes apply, the following type codes shall

be used:

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

APPROVAL AND ADMINISTRATIVE REQUIREMENTS

129

H(U) Unilateral approval

H(M) Multilateral approval.

(d) For certificates of approval of package design and special form radioactive

material, other than those issued under the provisions of paras 820–823,

and for certificates of approval of low dispersible radioactive material, the

symbol “-96” shall be added to the type code.

833. These identification marks shall be applied as follows:

(a) Each certificate and each package shall bear the appropriate identification

mark, comprising the symbols prescribed in para. 832(a)–(d), except that,

for packages, only the applicable design type codes including, if applicable,

the symbol “-96” shall appear following the second stroke, that is, the “T”

or “X” shall not appear in the identification marking on the package. Where

the approval of design and the approval of shipment are combined, the

applicable type codes do not need to be repeated. For example:

A/132/B(M)F-96: A Type B(M) package design approved for fissile

material, requiring multilateral approval, for which

the competent authority of Austria has assigned the

design number 132 (to be marked both on the

package and on the certificate of approval for the

package design)

A/132/B(M)F-96T: The approval of shipment issued for a package

bearing the identification mark elaborated above

(to be marked on the certificate only)

A/137/X: An approval of special arrangement issued by the

competent authority of Austria, to which the number

137 has been assigned (to be marked on the

certificate only)

A/139/IF-96: An industrial package design for fissile material

approved by the competent authority of Austria, to

which package design number 139 has been assigned

(to be marked both on the package and on the

certificate of approval for the package design)

A/145/H(U)-96: A package design for fissile-excepted uranium

hexafluoride approved by the competent authority of

Austria, to which package design number 145 has

been assigned (to be marked both on the package and

on the certificate of approval for the package design)

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

SECTION VIII

130

(b) Where multilateral approval is effected by validation in accordance with

para. 840, only the identification mark issued by the country of origin of the

design or shipment shall be used. Where multilateral approval is effected

by issue of certificates by successive countries, each certificate shall bear

the appropriate identification mark and the package whose design was so

approved shall bear all appropriate identification marks.

For example:

A/132/B(M)F-96

CH/28/B(M)F-96

would be the identification mark of a package that was originally approved

by Austria and was subsequently approved, by separate certificate, by

Switzerland. Additional identification marks would be tabulated in a similar

manner on the package.

following the identification mark on the certificate. For example,

A/132/B(M)F-96(Rev.2) would indicate revision 2 of the Austrian

certificate of approval for the package design; or A/132/B(M)F-96(Rev.0)

would indicate the original issuance of the Austrian certificate of approval

for the package design. For original issuances, the parenthetical entry is

optional and other words such as “original issuance” may also be used in

place of “Rev.0”. Certificate revision numbers may only be issued by the

country issuing the original certificate of approval.

(d) Additional symbols (as may be necessitated by national requirements) may

be added in brackets to the end of the identification mark, for example,

A/132/B(M)F-96(SP503).

(e) It is not necessary to alter the identification mark on the packaging each

time that a revision to the design certificate is made. Such re-marking shall

be required only in those cases where the revision to the package design

certificate involves a change in the letter type codes for the package design

following the second stroke.

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

APPROVAL AND ADMINISTRATIVE REQUIREMENTS

131

CONTENTS OF CERTIFICATES OF APPROVAL

Certificates of approval for special form radioactive material and low

dispersible radioactive material

834. Each certificate of approval issued by a competent authority for special

form radioactive material or low dispersible radioactive material shall include

the following information:

(a) Type of certificate;

(b) The competent authority identification mark;

(d) List of applicable national and international regulations, including the

edition of the IAEA Regulations for the Safe Transport of Radioactive

Material under which the special form radioactive material or low

dispersible radioactive material is approved;

(e) The identification of the special form radioactive material or low

dispersible radioactive material;

(f) A description of the special form radioactive material or low dispersible

radioactive material;

(g) Design specifications for the special form radioactive material or low

dispersible radioactive material, which may include references to

drawings;

(h) A specification of the radioactive contents that includes the activities

involved and which may include the physical and chemical forms;

(i) A specification of the applicable management system, as required in

para. 306;

(j) Reference to information provided by the applicant relating to specific

actions to be taken prior to shipment;

(k) If deemed appropriate by the competent authority, reference to the identity

of the applicant;

(l) Signature and identification of the certifying official.

Certificates of approval for material excepted from fissile classification

835. Each certificate of approval issued by a competent authority for material

excepted from classification as “FISSILE” shall include the following

information:

(a) Type of certificate;

(b) The competent authority identification mark;

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

SECTION VIII

132

(d) List of applicable national and international regulations, including the

edition of the IAEA Regulations for the Safe Transport of Radioactive

Material under which the exception is approved;

(e) A description of the excepted material;

(f) Limiting specifications for the excepted material;

(g) A specification of the applicable management system, as required in

para. 306;

(h) Reference to information provided by the applicant relating to specific

actions to be taken prior to shipment;

(i) If deemed appropriate by the competent authority, reference to the identity

of the applicant;

(j) Signature and identification of the certifying official;

(k) Reference to documentation that demonstrates compliance with para. 606.

Certificates of approval for special arrangement

836. Each certificate of approval issued by a competent authority for a special

arrangement shall include the following information:

(a) Type of certificate.

(b) The competent authority identification mark.

(d) Mode(s) of transport.

(e) Any restrictions on the modes of transport, type of conveyance, freight

container and any necessary routeing instructions.

(f) List of applicable national and international regulations, including the

edition of the IAEA Regulations for the Safe Transport of Radioactive

Material under which the special arrangement is approved.

(g) The following statement: “This certificate does not relieve the consignor

from compliance with any requirement of the government of any country

through or into which the package will be transported”.

(h) References to certificates for alternative radioactive contents, other

competent authority validation, or additional technical data or information,

as deemed appropriate by the competent authority.

(i) Description of the packaging by reference to the drawings or a specification

of the design. If deemed appropriate by the competent authority, a

reproducible illustration not larger than 21 cm × 30 cm, showing the

make-up of the package, should also be provided, accompanied by a brief

description of the packaging, including materials of manufacture, gross

mass, general external dimensions and appearance.

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

APPROVAL AND ADMINISTRATIVE REQUIREMENTS

133

(j) A specification of the authorized radioactive contents, including any

restrictions on the radioactive contents that might not be obvious from the

nature of the packaging. This shall include the physical and chemical

forms, the activities involved (including those of the various isotopes, if

appropriate), mass in grams (for fissile material or for each fissile nuclide,

when appropriate) and whether special form radioactive material, low

dispersible radioactive material or fissile material excepted under

para. 417(f), if applicable.

(k) Additionally, for packages containing fissile material:

(i) A detailed description of the authorized radioactive contents;

(ii) The value of the CSI;

(iii) Reference to the documentation that demonstrates the criticality

safety of the contents;

(iv) Any special features on the basis of which the absence of water from

certain void spaces has been assumed in the criticality assessment;

(v) Any allowance (based on para. 677(b)) for a change in neutron

multiplication assumed in the criticality assessment as a result of

actual irradiation experience;

(vi) The ambient temperature range for which the special arrangement

has been approved.

(l) A detailed listing of any supplementary operational controls required for

preparation, loading, carriage, unloading and handling of the consignment,

including any special stowage provisions for the safe dissipation of heat.

(m) If deemed appropriate by the competent authority, reasons for the special

arrangement.

(n) Description of the compensatory measures to be applied as a result of the

shipment being under special arrangement.

(o) Reference to information provided by the applicant relating to the use of the

packaging or specific actions to be taken prior to the shipment.

(p) A statement regarding the ambient conditions assumed for purposes of

design if these are not in accordance with those specified in paras 656, 657

and 666, as applicable.

(q) Any emergency arrangements deemed necessary by the competent

authority.

(r) A specification of the applicable management system, as required in

para. 306.

(s) If deemed appropriate by the competent authority, reference to the identity

of the applicant and to the identity of the carrier.

(t) Signature and identification of the certifying official.

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

SECTION VIII

134

Certificates of approval for shipments

837. Each certificate of approval for a shipment issued by a competent authority

shall include the following information:

(a) Type of certificate.

(b) The competent authority identification mark(s).

(d) List of applicable national and international regulations, including the

edition of the IAEA Regulations for the Safe Transport of Radioactive

Material under which the shipment is approved.

(e) Any restrictions on the modes of transport, type of conveyance, freight

container and any necessary routeing instructions.

(f) The following statement: “This certificate does not relieve the consignor

from compliance with any requirement of the government of any country

through or into which the package will be transported”.

(g) A detailed listing of any supplementary operational controls required for

preparation, loading, carriage, unloading and handling of the consignment,

including any special stowage provisions for the safe dissipation of heat or

maintenance of criticality safety.

(h) Reference to information provided by the applicant relating to specific

actions to be taken prior to shipment.

(i) Reference to the applicable certificate(s) of approval of design.

(j) A specification of the actual radioactive contents, including any restrictions

on the radioactive contents that might not be obvious from the nature of the

packaging. This shall include the physical and chemical forms, the total

activities involved (including those of the various isotopes, if appropriate),

mass in grams (for fissile material or for each fissile nuclide, when

appropriate) and whether special form radioactive material, low dispersible

radioactive material or fissile material excepted under para. 417(f), if

applicable.

(k) Any emergency arrangements deemed necessary by the competent

authority.

(l) A specification of the applicable management system, as required in

para. 306.

(m) If deemed appropriate by the competent authority, reference to the identity

of the applicant.

(n) Signature and identification of the certifying official.

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

APPROVAL AND ADMINISTRATIVE REQUIREMENTS

135

Certificates of approval for package design

838. Each certificate of approval of the design of a package issued by a

competent authority shall include the following information:

(a) Type of certificate.

(b) The competent authority identification mark.

(d) Any restriction on the modes of transport, if appropriate.

(e) List of applicable national and international regulations, including the

edition of the IAEA Regulations for the Safe Transport of Radioactive

Material under which the design is approved.

(f) The following statement: “This certificate does not relieve the consignor

from compliance with any requirement of the government of any country

through or into which the package will be transported”.

(g) References to certificates for alternative radioactive contents, other

competent authority validation, or additional technical data or information,

as deemed appropriate by the competent authority.

(h) A statement authorizing shipment, where approval of shipment is required

under para. 825, if deemed appropriate.

(i) Identification of the packaging.

(j) Description of the packaging by reference to the drawings or specification

of the design. If deemed appropriate by the competent authority, a

reproducible illustration not larger than 21 cm × 30 cm, showing the

make-up of the package, should also be provided, accompanied by a brief

description of the packaging, including materials of manufacture, gross

mass, general external dimensions and appearance.

(k) Specification of the design by reference to the drawings.

(l) A specification of the authorized radioactive contents, including any

restrictions on the radioactive contents that might not be obvious from the

nature of the packaging. This shall include the physical and chemical

forms, the activities involved (including those of the various isotopes, if

appropriate), the mass in grams (for fissile material, the total mass of fissile

nuclides or the mass for each fissile nuclide, when appropriate) and whether

special form radioactive material, low dispersible radioactive material or

fissile material excepted under para. 417(f), if applicable.

(m) A description of the containment system.

(n) For package designs containing fissile material that require multilateral

approval of the package design in accordance with para. 814:

(i) A detailed description of the authorized radioactive contents;

(ii) A description of the confinement system;

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

SECTION VIII

136

(iii) The value of the CSI;

(iv) Reference to the documentation that demonstrates the criticality

safety of the contents;

(v) Any special features on the basis of which the absence of water from

certain void spaces has been assumed in the criticality assessment;

(vi) Any allowance (based on para. 677(b)) for a change in neutron

multiplication assumed in the criticality assessment as a result of

actual irradiation experience;

(vii) The ambient temperature range for which the package design has

been approved.

(o) For Type B(M) packages, a statement specifying those prescriptions of

paras 639, 655–657 and 660–666 with which the package does not conform

and any amplifying information that may be useful to other competent

authorities.

(p) For packages containing more than 0.1 kg of uranium hexafluoride, a

statement specifying those prescriptions of para. 634 that apply, if any, and

any amplifying information that may be useful to other competent

authorities.

(q) A detailed listing of any supplementary operational controls required for

preparation, loading, carriage, unloading and handling of the consignment,

including any special stowage provisions for the safe dissipation of heat.

(r) Reference to information provided by the applicant relating to the use of the

packaging or to specific actions to be taken prior to shipment.

(s) A statement regarding the ambient conditions assumed for purposes of

design, if these are not in accordance with those specified in paras 656, 657

and 666, as applicable.

(t) A specification of the applicable management system, as required in

para. 306.

(u) Any emergency arrangements deemed necessary by the competent

authority.

(v) If deemed appropriate by the competent authority, reference to the identity

of the applicant.

(w) Signature and identification of the certifying official.

Certificates of approval for alternative activity limits for



an exempt consignment of instruments or articles

839. Each certificate issued by a competent authority for alternative activity

limits for an exempt consignment of instruments or articles according to para. 818

shall include the following information:

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

APPROVAL AND ADMINISTRATIVE REQUIREMENTS

137

(a) Type of certificate;

(b) The competent authority identification mark;

(d) List of applicable national and international regulations, including the

edition of the IAEA Regulations for the Safe Transport of Radioactive

Material under which the exemption is approved;

(e) The identification of the instrument or article;

(f) A description of the instrument or article;

(g) Design specifications for the instrument or article;

(h) A specification of the radionuclide(s) and the approved alternative activity

limit(s) for the exempt consignment(s) of the instrument(s) or article(s);

(i) Reference to documentation that demonstrates compliance with

para. 403(b);

(j) If deemed appropriate by the competent authority, reference to the identity

of the applicant;

(k) Signature and identification of the certifying official.

VALIDATION OF CERTIFICATES

840. Multilateral approval may be by validation of the original certificate issued

by the competent authority of the country of origin of the design or shipment.

Such validation may take the form of an endorsement on the original certificate or

the issuance of a separate endorsement, annex, supplement, etc., by the competent

authority of the country through or into which the shipment is made.

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

139

REFERENCES

References are to editions that are current as of the time of publication of these

Regulations. Editions that supersede these may be adopted under national

legislation.

[1] EUROPEAN ATOMIC ENERGY COMMUNITY, FOOD AND AGRICULTURE

ORGANIZATION OF THE UNITED NATIONS, INTERNATIONAL ATOMIC

ENERGY AGENCY, INTERNATIONAL LABOUR ORGANIZATION,

INTERNATIONAL MARITIME ORGANIZATION, OECD NUCLEAR ENERGY

AGENCY, PAN AMERICAN HEALTH ORGANIZATION, UNITED NATIONS

ENVIRONMENT PROGRAMME, WORLD HEALTH ORGANIZATION,

Fundamental Safety Principles, IAEA Safety Standards Series No. SF-1, IAEA, Vienna

(2006).

[2] FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED NATIONS,

INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL LABOUR

ORGANISATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICAN

HEALTH ORGANIZATION, WORLD HEALTH ORGANIZATION, International

Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of

Radiation Sources, Safety Series No. 115, IAEA, Vienna (1996).

[3] INTERNATIONAL ATOMIC ENERGY AGENCY, Advisory Material for the IAEA

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

Series No. TS-G-1.1 (Rev. 1), IAEA, Vienna (2008).

[4] INTERNATIONAL ATOMIC ENERGY AGENCY, Planning and Preparing for

Emergency Response to Transport Accidents Involving Radioactive Material, IAEA

Safety Standards Series No. TS-G-1.2 (ST-3), IAEA, Vienna (2002).

[5] INTERNATIONAL ATOMIC ENERGY AGENCY, Compliance Assurance for the Safe

Transport of Radioactive Material, IAEA Safety Standards Series No. TS-G-1.5, IAEA,

Vienna (2009).

[6] INTERNATIONAL ATOMIC ENERGY AGENCY, The Management System for the

Safe Transport of Radioactive Material, IAEA Safety Standards Series No. TS-G-1.4,

IAEA, Vienna (2008).

[7] INTERNATIONAL ATOMIC ENERGY AGENCY, Radiation Protection Programmes

for the Transport of Radioactive Material, IAEA Safety Standards Series No. TS-G-1.3,

IAEA, Vienna (2007).

[8] INTERNATIONAL MARITIME ORGANIZATION, International Maritime Dangerous

Goods (IMDG) Code, IMO, London (2010).

[9] INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Radiation

Protection — Sealed Radioactive Sources — Leakage Test Methods, ISO 9978:1992(E),

ISO, Geneva (1992).

[10] UNITED NATIONS, Recommendations on the Transport of Dangerous Goods, Model

Regulations, ST/SG/AC.10/1/Rev.17, UN, New York and Geneva (2011).

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

140

[11] INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Series 1 Freight

Containers — Specifications and Testing – Part 1: General Cargo Containers for General

Purposes, ISO 1496:1990(E), ISO, Geneva (1990); and subsequent Amendments

1:1993, 2:1998, 3:2005, 4:2006 and 5:2006.

[12] INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Nuclear Energy

— Packaging of Uranium Hexafluoride (UF

) for Transport, ISO 7195:2005(E), ISO,

Geneva (2005).

[13] INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Radiation

Protection — Sealed Radioactive Sources — General Requirements and Classification,

ISO 2919:2012(E), ISO, Geneva (2012).

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

141

Annex I

SUMMARY OF APPROVAL AND

PRIOR NOTIFICATION REQUIREMENTS

This summary reflects the contents of the Regulations for the Safe

Transport of Radioactive Material (2012 Edition). The user’s attention is called to

the fact that there may be deviations (exceptions, additions, etc.) relative to:

(a) National regulations relating to safety;

(b) Carrier restrictions;

insurance, pre-notification and/or routeing and import/export/transit

licensing.

In particular, additional measures are taken to provide appropriate physical protection

in the transport of nuclear material and to prevent acts without lawful authority that constitute

the receipt, possession, use, transfer, alteration, disposal or dispersal of nuclear material and

which cause or are likely to cause, death or serious injury to any person or substantial damage

to property (see Refs I–1 to I–6).

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

ANNEX I

142

ANNEX I: SUMMARY OF APPROVAL AND PRIOR NOTIFICATION

REQUIREMENTS (Part 1)

Key

paragraphs

in the

Regulations

Class of package

or material

Competent authority

approval required

Consignor required

to notify country of

origin and countries

en route

each shipment

Country of

origin

Countries en

route

Excepted package

b,c

No No No

LSA material

c,d,e

and SCO

c,e

— Type IP-1,

— Type IP-2 or

— Type IP-3

No No No

Type A

c,d,e

No No No

Countries through or into which (but not over which) the consignment is transported (see

para. 204 of the Regulations).

For international transport by post, the consignment shall be deposited with the postal service

only by consignors authorized by the national authority.

If the radioactive contents are fissile material excepted under para. 417(f) of the Regulations,

multilateral approval shall be required (see para. 805 of the Regulations).

If the radioactive contents are uranium hexafluoride in quantities of 0.1 kg or more, the

approval requirements for packages containing it shall additionally apply (see paras 802 and

807 of the Regulations).

If the radioactive contents are fissile material that is not excepted from the requirements for

packages containing fissile material, then the approval requirements in paras 814 and 825

of the Regulations shall additionally apply.

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

SUMMARY OF APPROVAL AND PRIOR NOTIFICATION REQUIREMENTS

143

ANNEX I: SUMMARY OF APPROVAL AND PRIOR NOTIFICATION

REQUIREMENTS (Part 2)

Key

paragraphs

in the

Regulations

Class of package

or material

Competent authority

approval required

Consignor required

to notify country of

origin and countries

en route

each shipment

Country of

origin

Countries en

route



808

557, 558, 825

Type B(U)

b,c,d

— Package design

— Shipment

Yes

No (see Notes 1 and 2)



811

557, 558, 825

Type B(M)

b,c,e

— Package design

— Shipment

Yes

(see Note 3)

Yes

(see Note 3)

Yes

(see Note 1)



808

557, 558, 825

Type C

b,c,d

— Package design

— Shipment

Yes

No (see Notes 1 and 2)

Countries through or into which (but not over which) the consignment is transported (see

para. 204 of the Regulations).

If the radioactive contents are fissile material that is not excepted from the requirements for

packages containing fissile material, then the approval requirements in paras 814 and 825 of

the Regulations shall additionally apply.

If the radioactive contents are uranium hexafluoride in quantities of 0.1 kg or more, the

approval requirements for packages containing it shall additionally apply (see paras 802 and

807 of the Regulations).

If the radioactive contents are fissile material excepted under para. 417(f) of the Regulations,

multilateral approval shall be required (see para. 805 of the Regulations).

If the radioactive contents are low dispersible radioactive material and the package is to be

shipped by air, multilateral approval of the package design is required (see para. 808(b) of

the Regulations).

Note 1: Before the first shipment of any package requiring competent authority approval of the

design, the consignor shall ensure that a copy of the certificate of approval for that design

has been submitted to the competent authority of each country (see para. 557 of the

Regulations).

Note 2: Notification is required if the radioactive contents exceed 3000A

, or 3000A

, or 1000

TBq, whichever is the lower (see para. 558 of the Regulations).

Note 3: Multilateral approval of shipment required if the radioactive contents exceed 3000A

or 3000A

, or 1000 TBq, whichever is the lower, or if controlled intermittent venting is

allowed (see para. 825 of the Regulations).

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

ANNEX I

144

ANNEX I: SUMMARY OF APPROVAL AND PRIOR NOTIFICATION

REQUIREMENTS (Part 3)

Key

paragraph

in the

Regulations

Class of package

or material

Competent authority

approval required

Consignor required

to notify country of

origin and countries

en route

each shipment

Country of

origin

Countries en

route



814

825

Packages for

fissile material

— Package design

— Shipment

ΣCSI ≤ 50

ΣCSI > 50

Yes

(see Notes 1 and 2)



807



825

Packages containing

0.1 kg or more of

uranium hexafluoride

— Package design

— Shipment

Yes

Yes for H(M)/no

for H(U)

(see Notes 1 and 2)

Countries through or into which (but not over which) the consignment is transported (see

para. 204 of the Regulations).

Designs of packages containing fissile material may also require approval in respect of one

of the other items in Annex I.

Shipments may, however, require approval in respect of one of the other items in Annex I.

If the radioactive contents are fissile material excepted under para. 417(f) of the Regulations,

multilateral approval shall be required (see para. 805 of the Regulations).

Note 1: The multilateral approval requirement for fissile packages and some uranium

hexafluoride packages automatically satisfies the requirement of para. 557 of the

Regulations.

Note 2: Notification is required if the radioactive contents exceed 3000A

, or 3000A

, or

1000 TBq, whichever is the lower (see para. 558 of the Regulations).

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

SUMMARY OF APPROVAL AND PRIOR NOTIFICATION REQUIREMENTS

145

ANNEX I: SUMMARY OF APPROVAL AND PRIOR NOTIFICATION

REQUIREMENTS (Part 4)

Key

paragraphs

in the

Regulations

Class of package

or material

Competent authority

approval required

Consignor required

to notify country of

origin and countries

en route

each shipment

Country of

origin

Countries en

route



803

825

Special form



radioactive material

— Design

— Shipment

Yes

(see Note 1)



803

825

Low dispersible



radioactive material

— Design

— Shipment

Yes

(see Note 1)

Yes

(see Note 1)



558, 802, 829



820

805



817

Special arrangement

— Shipment

Type B (U) packages



for which design is

approved under

— 1973 Regulations

— 1985 Regulations

Fissile material excepted

from “FISSILE” 

classification, in accordance

with para. 606

Exempt consignment of 

instruments or articles

Yes

(see Note 2)

Countries through or into which (but not over which) the consignment is transported (see

para. 204 of the Regulations).

Note 1: See approval and prior notification requirements for applicable package.

Note 2: Before the first shipment of any package requiring competent authority approval of the

design, the consignor shall ensure that a copy of the certificate of approval for that design

has been submitted to the competent authority of each country (see para. 557 of the

Regulations).

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

ANNEX I

146

REFERENCES TO ANNEX I

[I–1] INTERNATIONAL ATOMIC ENERGY AGENCY, The Convention on the Physical

Protection of Nuclear Material, INFCIRC/274/Rev.1, IAEA, Vienna (1980).

[I–2] INTERNATIONAL ATOMIC ENERGY AGENCY, Nuclear Security

Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities

(INFCIRC/225/Revision 5), IAEA Nuclear Security Series No. 13, IAEA, Vienna

(2011).

[I–3] INTERNATIONAL ATOMIC ENERGY AGENCY, Guidance and Considerations for

the Implementation of INFCIRC/225/Rev.4, The Physical Protection of Nuclear

Material and Nuclear Facilities, IAEA-TECDOC-967(Rev.1), IAEA, Vienna (2000).

[I–4] INTERNATIONAL ATOMIC ENERGY AGENCY, Security in the Transport of

Radioactive Material, IAEA Nuclear Security Series No. 9, IAEA, Vienna (2008).

[I–5] INTERNATIONAL ATOMIC ENERGY AGENCY, Code of Conduct on the Safety and

Security of Radioactive Sources, IAEA, Vienna (2004).

[I–6] INTERNATIONAL ATOMIC ENERGY AGENCY, Guidance on the Import and Export

of Radioactive Sources, IAEA, Vienna (2005).

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

147

Annex II

CONVERSION FACTORS AND PREFIXES

This edition of the Regulations for the Safe Transport of Radioactive

Material uses the International System of Units (SI). The conversion factors for

non-SI units are:

RADIATION UNITS

Activity in becquerel (Bq) or curie (Ci)

1 Ci = 3.7 × 10

1 Bq = 2.7 × 10

–11

Dose equivalent in sievert (Sv) or rem

1 rem = 1.0 × 10

–2

1 Sv = 100 rem

PRESSURE

Pressure in pascal (Pa) or (kgf/cm

)

1 kgf/cm

= 9.806 808 × 10

1 Pa = 1.020 × 10

–5

kgf/cm

CONDUCTIVITY

Conductivity in siemens per metre (S/m) or (mho/cm)

10 µmho/cm = 1 mS/m

1 mho/cm = 100 S/m

1 S/m = 10

–2

mho/cm

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

ANNEX II

148

SI PREFIXES AND SYMBOLS

The decimal multiples and submultiples of a unit may be formed by

prefixes or symbols, having the following meanings, placed before the name or

symbol of the unit:

Multiplying factor Prefix Symbol

1 000 000 000 000 000 000 = 10

exa E

1 000 000 000 000 000 = 10

peta P

1 000 000 000 000 = 10

tera T

1 000 000 000 = 10

giga G

1 000 000 = 10

mega M

1 000 = 10

kilo k

100 = 10

hecto h

10 = 10

deca da

0.1 = 10

–1

deci d

0.01 = 10

–2

centi c

0.001 = 10

–3

milli m

0.000 001 = 10

–6

micro µ

0.000 000 001 = 10

–9

nano n

0.000 000 000 001 = 10

–12

pico p

0.000 000 000 000 001 = 10

–15

femto f

0.000 000 000 000 000 001 = 10

–18

atto a

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

149

Annex III

SUMMARY OF CONSIGNMENTS REQUIRING EXCLUSIVE USE

The following consignments are required to be shipped under exclusive use:

(a) Unpackaged LSA-I material and SCO-I (see para. 520);

(b) Liquid LSA-I material in a Type IP-1 package (see para. 521 and Table 5);

and Table 5);

(d) LSA-III material in a Type IP-2 package (see para. 521 and Table 5);

(e) Packages or overpacks having an individual TI greater than 10 or a

consignment CSI greater than 50 (see paras 526 and 567);

(f) Packages or overpacks having the maximum radiation level at any point on

the external surfaces that exceed 2 mSv/h (see para. 527);

(g) Loaded conveyance or large freight containers with a total sum of

TI exceeding the values given in Table 10 (see para. 566(a));

(h) Loaded conveyances or large freight containers with a total sum of CSI

exceeding the values given in Table 11 for “not under exclusive use”

(see para. 569);

(i) Type B(U), Type B(M) or Type C package whose temperature of accessible

surfaces exceeds 50°C when subject to an ambient temperature of 38°C in

the absence of insolation (see para. 654);

(j) Up to 45 g of fissile nuclides on a conveyance, either packaged or

unpackaged, in accordance with the provisions of paras 417(e) and 520(d);

(k) Packages containing fissile material classified as non-fissile or

fissile-excepted under para. 417(a)(i) or (iii) of the 2009 Edition of these

Regulations (see para. 822).

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

151

CONTRIBUTORS TO DRAFTING AND REVIEW (2012)

Aceña Moreno, V. Consejo de Seguridad Nuclear, Spain

Alter, U. Federal Ministry for the Environment, Germany

Anikin, A. Federal Environmental, Industrial and Nuclear

Supervision Service of Russia, Russian Federation

Ardouin, C. National Radiation Laboratory, New Zealand

Ashour Al-Jeidi, J. Libya

Askitoglu, E. Swiss Federal Nuclear Safety Inspectorate, Switzerland

Barlow, I. Department for Transport, United Kingdom

Barto, A. Nuclear Regulatory Commission,

United States of America

Barton, N. Department for Transport, United Kingdom

Belamaric, N. State Office of Radiation Protection, Croatia

Binet, J. European Commission

Blahova, V. State Office for Nuclear Safety, Czech Republic

Börst, F. Bundesamt für Strahlenschutz, Germany

Bove, R. ENEA/FPN, Italy

Boyle, R. US Department of Transportation,

United States of America

Brach, E. Nuclear Regulatory Commission,

United States of America

Brennan, D. International Air Transport Association

Buchelnikov, A. State Atomic Energy Corporation, Russian Federation

Busitta, M.A. Atomic Energy Establishment, Libya

Buxo da Trindade, R. UPSR/ITN, Portugal

Cabianca, T. Health Protection Agency, United Kingdom

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

CONTRIBUTORS TO DRAFTING AND REVIEW (2012)

152

Capadona, N. Autoridad Regulatoria Nuclear, Argentina

Carenini, L. IRSN, France

Charette, M. CAMECO, Canada

Cho, D. Korea Institute of Nuclear Safety, Republic of Korea

Conroy, M. US Department of Transportation,

United States of America

Cook, J. Nuclear Regulatory Commission,

United States of America

Cottens, E. Federal Agency for Nuclear Control, Belgium

Crook, P. Department for Transport, United Kingdom

Darby, S. World Nuclear Transport Institute

Dekker, B. World Nuclear Transport Institute

Desnoyers, B. World Nuclear Transport Institute

Droste, B. Bundesanstalt für Materialforschung und -prüfung,

Germany

Duchacek, V. State Office for Nuclear Safety, Czech Republic

Duffy, J. Radiological Protection Institute of Ireland, Ireland

Dziubiak, T. National Atomic Energy Agency, Poland

Edgecombe, R. Nordion Inc., Canada

Elkikly, A.E. Libya

El-Shinawy, R. Atomic Energy Authority, Egypt

Enriquez Marchal, C. Empresa Nacional de Residuos Radiactivos S.A., Spain

Ershov, V. State Corporation on Atomic Energy, Russian

Federation

Ertürk, K. Turkish Atomic Energy Authority, Turkey

Eshragi, A. Atomic Energy Organization of Iran,

Islamic Republic of Iran

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

CONTRIBUTORS TO DRAFTING AND REVIEW (2012)

153

Faille, S. Canadian Nuclear Safety Commission, Canada

Faludi, R. European Lamp Companies Federation

Fasten, C. Bundesamt für Strahlenschutz, Germany

Fierbintu, T. National Commission for Nuclear Activities Control,

Romania

Fulford, G. Nordion Inc., Canada

Fuller, J. Department for Transport, United Kingdom

Garg, R. Canadian Nuclear Safety Commission, Canada

Gessl, M. International Federation of Air Pilots’ Associations

Getrey, C. IRSN, France

Girkens, P. Federal Ministry of Transport, Building and Urban

Affairs, Germany

Glenn, K. Canadian Nuclear Safety Commission, Canada

Gorlin, S. World Nuclear Association

Gozalo, L. ASN/DIT, France

Gullö, J. Swedish Civil Contingencies Agency, Sweden

Hajizadeh, B. Atomic Energy Organization of Iran,

Islamic Republic of Iran

Hanaki, I. Nuclear and Industrial Safety Agency, Japan

Hellsten, S. Radiation and Nuclear Safety Authority, Finland

Herrati, A. Centre de recherche nucléaire d’Alger, Algeria

Hesius, M. Federal Agency for Nuclear Control, Belgium

Hinrichsen, P. National Nuclear Regulator, South Africa

Hirose, M. World Nuclear Transport Institute

Hishida, M. Japan Nuclear Energy Safety Organization, Japan

Hornkjøl, S. Norwegian Radiation Protection Authority, Norway

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

CONTRIBUTORS TO DRAFTING AND REVIEW (2012)

154

Hughes, S. Health Protection Agency, United Kingdom

Hursthouse, J. Department for Transport, United Kingdom

Ikoma, Y. Secretariat of the Nuclear Safety Commission, Japan

Ilijas, B. State Office for Radiological and Nuclear Safety,

Croatia

Ito, D. World Nuclear Transport Institute

Itoh, C. Central Research Institute of Electric Power Industry,

Japan

Iwasa, T. Ministry of Education, Culture, Sports,

Science & Technology, Japan

Jacob, E. DSND/ASND, France

Jutier, L. IRSN/DSU, France

Kapoor, A. US Department of Energy, United States of America

Katona, T. Hungarian Academy of Sciences, Hungary

Kavanagh, J. Nordion Inc., Canada

Kekli, A. Renewable Energies and Water Desalination Research

Center, Libya

Kent, N. World Nuclear Transport Institute

Kervella, O. United Nations Economic Commission for Europe

Kirchnawy, F. Federal Ministry for Transport, Innovation and

Technology, Austria

Koch, F. Swiss Federal Nuclear Safety Inspectorate, Switzerland

Kojima, S. Nuclear and Industrial Safety Agency, Japan

Komann, S. Bundesanstalt für Materialforschung und -prüfung,

Germany

Konnai, A. National Maritime Research Institute, Japan

Korbmacher, T. World Nuclear Transport Institute

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

CONTRIBUTORS TO DRAFTING AND REVIEW (2012)

155

Krzaniak, M. Nordion Inc., Canada

Kueny, L. Autorité de sûreté nucléaire, France

Lahkola, A. Radiation and Nuclear Safety Authority, Finland

Lamarche, D. Transport Canada, Canada

Landier, D. Autorité de sûreté nucléaire, France

Leblanc, V. Federal Agency for Nuclear Control, Belgium

Li, X. CNNC Everclean Co. Ltd., China

Lizot, M. ASN/DIT, France

Lopez Vietri, J. Autoridad Regulatoria Nuclear, Argentina

Lourtie, G. Federal Agency for Nuclear Control, Belgium

Malesys, P. International Organization for Standardization

Marzo, G. ENEA, Italy

McGhee, S. Nordion Inc., Canada

Mennerdahl, D. E. Mennerdahl Systems, Sweden

Miller, J. International Source Suppliers and Producers

Association

Mirfakhraei, P. Canadian Nuclear Safety Commission, Canada

Mochizuki, H. National Maritime Research Institute, Japan

Mohajane, E. South Africa

Mohd Sobari, M. Atomic Energy Licensing Board, Malaysia

Mosoeunyane, S. National Nuclear Regulator, South Africa

Muneer, M. Pakistan Nuclear Regulatory Authority, Pakistan

Nada, A. Egyptian Atomic Energy Authority, Egypt

Neau, H. World Nuclear Transport Institute

Neuman, I. EU.select GmbH, Belgium

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

CONTRIBUTORS TO DRAFTING AND REVIEW (2012)

156

Nitsche, F. Bundesamt für Strahlenschutz, Germany

O Connor, G. Department for Transport, United Kingdom

O’Connor, S. US Department of Energy, United States of America

Odano, N. National Maritime Research Institute, Japan

Olma, R. EU.select GmbH, Belgium

Ordaz, V. Nuclear Regulatory Commission,

United States of America

Orsini, A. ENEA, Italy

Ortiz de Echevarria Diez, I. IRSN/DSU, France

Oue, K. Nuclear and Industrial Safety Agency, Japan

Owen, G. International Nuclear Services, United Kingdom

Oyinloye, J. Department for Transport, United Kingdom

Parks, C. Oak Ridge National Laboratory,

United States of America

Patasius, Z. State Nuclear Power Safety Inspectorate, Lithuania

Patko, A. NAC International, United States of America

Pecnik, M. State Office of Radiation Protection, Croatia

Rahim, I. International Maritime Organization

Rashid, M. Pakistan Nuclear Regulatory Authority, Pakistan

Reculeau, J. ASND/DSND, France

Reiche, I. Bundesamt für Strahlenschutz, Germany

Richartz, M. Bundesministerium für Umwelt, Naturschutz und

Reaktorsicherheit, Germany

Roelofsen, E. Covidien, Netherlands

Rooney, K. International Civil Aviation Organization

Rossi, L. European Commission

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

CONTRIBUTORS TO DRAFTING AND REVIEW (2012)

157

Rubio de Juan, E. Consejo de Seguridad Nuclear, Spain

Safar, J. Hungarian Atomic Energy Authority, Hungary

Sallit, G. Department for Transport, United Kingdom

Sampson, M. Nuclear Regulatory Commission,

United States of America

Sannen, H. Belgium

Sarkar, S. Australian Radiation Protection and Nuclear Safety

Agency, Australia

Sauron, C. Autorité de sûreté nucléaire, France

Savic, N. BMVIT, Austria

Schwela, U. Tantalum–Niobium International Study Center

Sekse, T. Norwegian Radiation Protection Authority, Norway

Sen, A. Department for Transport, United Kingdom

Sert, G. IRSN/DSU, France

Shukri, T. Resident Representative of KACST, Saudi Arabia

Singh, K. Atomic Energy Regulatory Board, India

Smith, J. Nuclear Regulatory Commission,

United States of America

Statkus, V. Radiation Protection Center, Lithuania

Stroem, K. Swedish Civil Contingencies Agency, Sweden

Svahn, B. Swedish Radiation Safety Authority, Sweden

Svein-Erik, C. Norwegian Radiation Protection Authority, Norway

Takani, M. World Nuclear Transport Institute

Taniuchi, H. Transnuclear Ltd., Japan

Ter Morshuizen, M. Ministry of Housing, Spatial Planning and the

Environment, Netherlands

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

CONTRIBUTORS TO DRAFTING AND REVIEW (2012)

158

Tezuka, H. Japan Nuclear Energy Safety Organization, Japan

Tikkinen, J. Radiation and Nuclear Safety Authority, Finland

Trivelloni, S. Agency for Environmental Protection and Technical

Services, Italy

Turner, M. Department for Transport, United Kingdom

Twala, V. ESKOM, South Africa

van Aarle, J. Nordostschweizerische Kraftwerke AG, Switzerland

Van de Put, F. European Lamp Companies Federation

Vince, D. Department for Transport, United Kingdom

Vogiatzi, S. Greek Atomic Energy Commission, Greece

Welleman, E. Swedish Radiation Safety Authority, Sweden

Whittingham, S. Department for Transport, United Kingdom

Wille, F. Bundesanstalt für Materialforschung und -prüfung,

Germany

Wortmann, G. International Source Suppliers and Producers

Association

Xavier, A. National Nuclear Energy Commission, Brazil

Yamaguchi, M. Japan Nuclear Energy Safety Organization, Japan

Yamanaka, T. Japan Nuclear Energy Safety Organization, Japan

Yamasaki, A. Nippon Kaiji Kentei Kyokai, Japan

Yamauchi, T. Nuclear and Industrial Safety Agency, Japan

Young, C. Consultant, United Kingdom

Zamora Martín, F. Consejo de Seguridad Nuclear, Spain

Zika, H. Swedish Radiation Safety Authority, Sweden

Numerous other participants in Member States took part in the review and revision of this

publication. Their invaluable contributions to the process is recognized.

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

159

BODIES FOR THE ENDORSEMENT

OF IAEA SAFETY STANDARDS

An asterisk denotes a corresponding member. Corresponding members receive

drafts for comment and other documentation but they do not generally participate

in meetings. Two asterisks denote an alternate.

Commission on Safety Standards

Argentina: González, A.J.; Australia: Larsson, C.-M.; Belgium: Samain,

J.-P.; Brazil: Salati de Almeida, I.P.; Canada: Jammal, R.; China: Jun Yu;

Czech Republic: Drábová, D. (Chairperson); Finland: Reiman, L.; France:

Lacoste, A.-C.; Germany: Vorwerk, A.; India: Bajaj, S.S.; Israel: Markovits, M.;

Japan: Nakamura, K.; Korea, Republic of: Yun, C.-H.; Lithuania

Malaysia: Raja Adnan, R.; MoroccoPakistan: Habib, M.A.; Russian

Federation: Bezzubtsev, V.S.; South Africa: Phillips, C.O.; Spain: Gurguí

Ferrer, A.; Sweden: Lund, I.; United Arab Emirates: Travers, W.; United Kingdom:

Weightman, M.; United States of America: Weber, M.; IAEA: Delattre, D.

(Coordinator); Advisory Group on Nuclear Security: Raja Adnan, A.; European

Commission: Faross, P.; International Commission on Radiological Protection:

Cousins, C.; International Nuclear Safety Group: Meserve, R.; OECD Nuclear

Energy Agency: Yoshimura, U.; Safety Standards Committee Chairpersons:

Feron, F. (NUSSC); Massera, G. (RASSC); Brach, E.W. (TRANSSC);

Williams, G. (WASSC).

Nuclear Safety Standards Committee

*Algeria: Merrouche, D.; Argentina: Waldman, R.; Australia: Ward, J.;

Austria: Sholly, S.; Belgium: De Boeck, B.; Brazil: Gromann, A.; *Bulgaria:

Vlahov, N.; Canada: Rzentkowski, G.; China: Li, Jingxi; Croatia:

  *Cyprus: Demetriades, P.; Czech Republic: Vesely, J.; Egypt:

Ibrahim, M.; Finland: Järvinen, M.-L.; France: Feron, F. (Chairperson);

Germany: Weidenbrück, K.; *Greece: Nikolaou, G.; Hungary: Adorján, F.;

India: Vaze, K.; *Indonesia: Antariksawan, A.; Iran, Islamic Republic of: Mataji

Kojouri, N.; Israel: Harari, R.; Italy: Matteocci, L.; Japan: Maki, S.; Korea,

Republic of: Lee, S.; Libya: Abulagassem, O.; Lithuania  

Malaysia: Azlina Mohammed Jais; Mexico: Carrera, A.; Morocco:

  Pakistan: Mansoor, F.; Panama: Gibbs, E.; Poland: Kielbasa, W.;

Romania: Ciurea-Ercau, C.; Russian Federation: Stroganov, A.; Slovakia:

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

BODIES FOR THE ENDORSEMENT OF IAEA SAFETY STANDARDS

160

Uhrik, P.; Slovenia   Spain: Zarzuela, J.; Sweden: Hallman, A.;

Switzerland: Flury, P.; *Thailand: Siripirom, L.; *Turkey: Kilinc, B.; Ukraine:

Gromov, G.; United Arab Emirates: Grant, I.; United Kingdom: Hart, A;

United States of America: Case, M.; European Commission: Vigne, S.; ENISS:

Bassing, G.; IAEA: Svab, M. (Coordinator); International Electrotechnical

Commission: Bouard, J.-P.; International Organization for Standardization:

Sevestre, B.; OECD Nuclear Energy Agency: Reig, J.; World Nuclear Association:

Fröhmel, T.

Radiation Safety Standards Committee

*Algeria: Chelbani, S.; Argentina: Massera, G. (Chairperson), **Gregory, B.;

Australia: Topfer, H.; *Austria: Karg, V.; Belgium: van Bladel, L.; Brazil: Da

Hora Marechal, M.H.; *Bulgaria: Katzarska, L.; Canada: Thompson, P.; China:

Yang, H.; Croatia: Kralik, I.; *Cyprus: Demetriades, P.; Czech Republic:

Petrova, K.; Denmark: Øhlenschlæger, M.; Egypt: Hamed Osman, A.; Finland:

Markkanen, M.; France: Godet, J.-L.; Germany: Helming, M.; *Greece:

Kamenopoulou, V.; Hungary: Koblinger, L.; India: Sharma, D.N.; *Indonesia:

Rusdian, Y.; Iran, Islamic Republic of: Kardan, M.R.; Ireland: Pollard, D.; Israel:

Koch, J.; Italy: Bologna, L.; Japan: Nagata, M.; Korea, Republic of: Rho, S.;

Libya: El-Fawaris, B.; Lithuania: Mastauskas, A.; Malaysia: Mishar, M.; Mexico:

Delgado Guardado, J.; Netherlands: Vermeulen, T.; New Zealand: Cotterill, A.;

Norway: Saxebol, G.; Pakistan: Nasim, B.; Panama: Gibbs, E.; Peru: Ramirez

Quijada, R.; Poland: Merta, A.; Romania: Preoteasa, A.; Russian Federation:

Mikhenko, S.; Slovakia: Jurina, V.; Slovenia: Sutej, T.; South Africa:

Tselane, T.J.; Spain: Álvarez, C.; Sweden: Hägg, A.; Switzerland: Leupin, A.;

*Thailand: Suntarapai, P.; *Turkey: Celik, P.; Ukraine: Pavlenko, T.; United

Arab Emirates: Loy, J; United Kingdom: Temple, C.; United States of America:

McDermott, B.; European Commission: Janssens, A.; European Nuclear

Installation Safety Standards: Lorenz, B.; Food and Agriculture Organization of

the United Nations: Byron, D.; IAEA: Colgan, P.A. (Coordinator); International

Commission on Radiological Protection: Clement, C.; International Labour

: Niu, S.; International Radiation Protection Association: Kase, K.;

International Organization for Standardization: Rannou, A.; International Source

Suppliers and Producers Association: Fasten, W.; OECD Nuclear Energy Agency:

Lazo, T.E.; Pan American Health Organization: Jiménez, P.; United Nations

: Crick, M.; World Health

Organization: Peres, M.; World Nuclear Association: Saint-Pierre, S.

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

BODIES FOR THE ENDORSEMENT OF IAEA SAFETY STANDARDS

161

Transport Safety Standards Committee

Algeria: Herrati, A.; Argentina: López Vietri, J.; Australia: Sarkar, S.; Austria:

Kirchnawy, F.; Belgium: Lourtie, G.; Brazil: Xavier, A.M.; *Bulgaria:

Bakalova, A.; Canada: Faille, S.; China: Xiaoqing, Li; Croatia:

Ilijas, B.; *Cyprus: Demetriades, P.; Czech Republic:   Egypt:

Nada, A.; Finland: Lahkola, A.; France: Kueny, L., **Sert, G.; Germany:

Richartz, M., **Nitsche, F.; *Greece: Vogiatzi, S.; Hungary: Sáfár, J.; India:

Singh, K.; *Indonesia: Sinaga, D.; Iran, Islamic Republic of: Eshraghi, A.;

Ireland: Duffy, J.; Italy: Trivelloni, S.; Japan: Kojima, S.; Korea, Republic of:

Cho, D.; Lithuania: Statkus, V.; Malaysia: Mohd Sobari, M.P.; **Hussain, Z.A.;

Mexico: Bautista Arteaga, D.M.; **Delgado Guardado, J.L.; *Morocco: Allach,

A.; Netherlands: Ter Morshuizen, M.; *New Zealand: Ardouin, C.; Norway:

Hornkjøl, S.; Pakistan: Muneer, M.; Panama: Francis, D.; *Poland: Dziubiak, T.;

Russian Federation: Buchelnikov, A., **Ershov, V., **Anikin, A.; South Africa:

Mohajane, P., **Hinrichsen, P., **Mmutle, N.; Spain: Zamora, F.; Sweden:

Zika, H.; Switzerland: Koch, F.; *Thailand: Jerachanchai, S.; *Turkey:

Türkes

Yilmas, S.; Ukraine: Kutuzova, T.; United Kingdom: Sallit, G.; United States of

America: Boyle, R.W.; **Brach, E.W. (Chairperson); **Weaver, D.; European

Commission: Binet, J.; IAEA: Stewart, J.T. (Coordinator); International Air

Transport Association: Brennan, D.; International Civil Aviation Organization:

Rooney, K.; International Organization for Standardization: Malesys, P.;

International Source Supplies and Producers Association: Miller, J.J.; United

Nations Economic Commission for Europe: Kervella, O.; Universal Postal

Union: Bowers, D.G.; World Nuclear Association: Gorlin, S.; World Nuclear

Transport Institute: Neau, H.J.

Waste Safety Standards Committee

*Algeria: Ghezal, A.; Argentina: Lee Gonzales, H.A.; Australia: Williams, G.

(Chairperson); *Austria: Fischer, H.; Belgium: Blommaert, W.; Brazil: De Souza

Ferreira, R.; *Bulgaria: Alexiev, A.; Canada: Howard, D.; China: Zhimin

Qu; Croatia: Trifunovic, D.; Cyprus: Demetriades, P.; Czech Republic:

Lietava, P.; Denmark: Hannesson, H.; Egypt: Abdel-Geleel, M.; Finland:

Hutri, K.; France: Evrard, L.; Germany: Götz, C.; *Greece: Mitrakos, D.; Hungary:

Molnár, B.; India: Rana, D.; *Indonesia: Wisnubroto, D.; Iran, Islamic Republic

of: Sebteahmadi, S.; Iraq: Al-Janabi, M.; Israel: Torgeman, S.; Italy: Dionisi, M.;

Japan: Shiozaki, M.; Korea, Republic of: Park, W.-J.; Libya: Gremida, K.; Lithuania:

Paulikas, V.; Malaysia: Hassan, H.; Mexico: Aguirre Gómez, J.; *Morocco:

Bouanani, A.; Netherlands: van der Shaaf, M.; *New Zealand: Cotterill, A.;

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

BODIES FOR THE ENDORSEMENT OF IAEA SAFETY STANDARDS

162

Skrzeczkowska, M.; Romania: Rodna, A.; Russian Federation: Polyakov, Y.;

Slovakia: Homola, J.; Slovenia: Kroselj, V.; South Africa: Mosoeunyane, S.;

Spain: López de la Higuera, J.; Sweden: Hedberg, B.; Switzerland: Altorfer, F.;

*Thailand: Supaokit, P.; *Turkey: Ünver, Ö.; Ukraine: Kondratyev, S.; United

Kingdom: Chandler, S.; United States of America: Camper, L.; European Nuclear

Installation Safety Standards-FORATOM: Nocture, P.; European Commission:

Necheva, C.; IAEA: Siraky, G. (Coordinator); International Organization for

Standardization: James, M.; International Source Suppliers and Producers

Association: Fasten, W.; OECD Nuclear Energy Agency: Riotte, H.; World

Nuclear Association: Saint-Pierre, S.

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

163

INDEX

(by paragraph number)

Accident conditions: 106, 403, 404, 638, 673, 685, 726, 817, 820

Activity limit: 111, 201, 231, 402, 403, 405, 411, 414, 422, 423, 802, 817–820,

832, 839

: 201, 402, 404–407, 428, 429, 430, 433, 558, 825

: 201, 402–407, 409, 410, 428, 429, 430, 433, 546, 558, 601, 605, 659, 660,

671, 730, 825

Alternative activity limit: 403, 802, 817, 818, 832, 839

Air (transport by): 106, 217, 243, 410, 433, 527, 577–579, 581, 606, 619–623,

635, 652, 655, 683, 820

Ambient conditions: 616, 619, 620, 645, 653–656, 666, 670, 679, 703, 710, 711,

728, 812, 836, 838

Basic Safety Standards (BSS): 101, 308, 403, 817

Carrier: 203, 206, 309, 550, 554, 556, 584, 586–588, 836

Categories of package: 529, 530, 538, 540, 546, 563, 573

Certificate of approval: 104, 111, 204, 205, 238, 310, 403, 418, 431–433, 501,

503, 530, 535, 541, 546, 556, 557, 559–561, 565, 570, 634, 667, 679, 718,

801–808, 810, 811, 813, 814, 816, 818, 827, 828, 831–840

Competent authority: 104, 204, 205, 207–209, 238, 302, 306–310, 313, 315, 403,

431, 510, 530, 534, 535, 541, 546, 556–558, 565, 576, 583, 603, 640, 667,

668, 679, 711, 801, 802, 804, 806, 807, 810, 813, 815, 816, 818–820, 823,

824, 826, 828, 830–840

Compliance assurance: 102, 105, 208, 307

Confinement system: 209, 501, 681, 838

Consignee: 210, 221, 309, 531, 546, 582, 585

Consignment: 203, 204, 210–212, 222, 236–238, 243, 305, 310, 402, 403, 405,

417, 423, 506, 525, 526, 541, 544, 546, 547, 553, 554, 556–559, 562, 564,

566, 567, 570–573, 576, 577, 580, 581, 583–586, 802, 803, 817, 818, 822,

829, 832, 836–839

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

INDEX

164

Consignor: 211, 212, 221, 230, 306, 309, 531, 546–549, 554–558, 560, 561, 581,

801, 836–838

Containment: 104, 232, 501, 620, 650, 653, 725, 817

Containment system: 213, 229, 501, 503, 621, 632, 641–645, 647, 650, 660, 662,

663, 672, 680, 685, 714, 716, 724, 809, 838

Contamination: 107, 214–216, 309, 413, 427, 508–510, 512, 513, 520, 659, 671

Conveyance: 104, 217, 221, 411, 414, 509, 510, 512–514, 520, 522, 524, 525,

546, 554, 566, 569, 570, 607, 809, 822, 825, 827, 836, 837

Cooling system: 578, 661

Criticality: 101, 104, 209, 501, 606, 673, 716, 836–838

Criticality safety index (CSI): 218, 525, 526, 541, 542, 546, 566–569, 674, 675,

686, 825, 836, 838

Customs: 582

Dangerous goods: 110, 506, 507, 550, 562, 627, 628, 630

Deck area: 217, 219, 825

Decontamination: 511, 513

Dose limits: 301

Emergency: 102, 304, 305, 309, 313, 554, 836–838

Empty packaging: 422, 427, 581

Excepted package: 231, 419, 422–427, 515, 516, 543, 622, 819

Exclusive use: 221, 514, 520, 526–529, 537, 544, 546, 566, 567, 570–573, 575,

577, 654, 655, 822

Fissile material: 209, 218, 220, 222, 231, 409, 417–419, 501, 503, 515, 518–520,

538, 540, 546, 559, 568–570, 606, 631, 673–686, 716, 731–733, 802, 805,

806, 808, 811, 814–816, 820, 822, 825, 832, 833, 835–838

Freight container: 218, 221, 223, 244, 313, 505, 509, 514, 523–525, 529,

538–540, 542–544, 546, 551, 554, 562, 566, 568, 569, 571, 574, 629, 809,

825, 836, 837

Gas: 235, 242, 409, 628, 644, 651, 725

Heat: 104, 501, 554, 565, 603, 653, 704, 708, 728, 809, 836–838

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

INDEX

165

Identification mark: 534, 535, 546, 559, 804, 806, 807, 810, 813, 816, 818,

832–839

Industrial package (IP): 231, 517–524, 534, 623–630, 819, 832, 833

Insolation: 619, 654, 655, 657, 728

Inspection: 302, 306, 503, 582, 801

Intermediate bulk container (IBC): 224, 505, 509, 514, 630

Label: 313, 427, 507, 530, 538–543, 545–547, 571, 574

Leaching: 409, 603, 703, 704, 710–712

Leakage: 510, 603, 632, 634, 646, 650, 673, 680, 683, 704, 710, 711, 731–733

Low dispersible radioactive material: 220, 225, 416, 433, 546, 559, 605, 665,

701, 703, 712, 802–804, 808, 811, 832, 834, 836–838

Low specific activity (LSA): 226, 244, 408–411, 517–523, 537, 540, 544, 546,

566, 572, 601, 628, 701, 703

Maintenance: 104, 106, 680, 809, 837

Management system: 102, 105, 228, 306, 803, 805, 807, 809, 815, 817, 823,

834–838

Manufacture: 106, 306, 403, 422, 423, 426, 501, 604, 640, 680, 713, 809,

819–821, 823, 824, 836, 838

Marking: 313, 423, 424, 507, 530–537, 539, 545, 547, 820, 833

Mass:240, 247, 417, 420, 425, 533, 540, 546, 559, 607, 609, 659, 674–676, 680,

685, 709, 722–724, 727, 735, 836–838

Maximum normal operating pressure: 229, 621, 663, 664, 670, 671, 809

Multilateral approval: 204, 310, 403, 634, 718, 803, 805, 807, 808, 811, 814,

817, 820, 825, 829, 832, 833, 838, 840

N: 684–686

Normal conditions: 106, 511, 653, 673, 684, 719–725

Notification: 557–560, 824

Operational controls: 229, 578, 668, 812, 827, 830, 836–838

Other dangerous properties: 507, 538, 618

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

INDEX

166

Overpack: 218, 230, 244, 505, 509, 523–532, 538–540, 542, 546, 554, 562, 563,

565–569, 571, 573–575, 579, 825

Package design: 104, 418, 420, 433, 502, 534–536, 546, 557, 617, 618, 632, 650,

651, 676–679, 801, 802, 807–816, 820, 821, 827, 832, 833, 838, 840

Packaging: 104, 106, 111, 209, 213, 220, 224, 231, 232, 235, 313, 409, 427, 501,

505, 531, 533–535, 581, 610, 614, 631, 639, 643, 647, 653, 665, 680, 681,

701, 718, 723, 809, 819–821, 824, 833, 836–838

Placard: 313, 507, 543–545, 547, 571, 572

Post: 423, 424, 515, 580, 581

Pressure: 229, 420, 501, 503, 616, 621, 627, 628, 633, 634, 641, 645, 646,

662–664, 670, 671, 718, 729, 730, 809

Pressure relief: 633, 646, 662

Radiation exposure: 244, 302, 562, 582

Radiation level: 104, 233, 309, 404, 411, 414, 423, 510, 513, 516, 517, 523, 524,

527–529, 566, 573, 575, 579, 605, 617, 624, 626–630, 648, 659, 671, 817,

820

Radiation protection: 102, 234, 302, 311, 576, 603, 711, 802, 825

Rail (transport by): 106, 107, 217, 242, 248, 527, 566, 571, 572

Responsibility: 101, 103

Road (transport by): 106, 107, 217, 242, 248, 527, 566, 571–574

Routine conditions: 106, 215, 424, 508, 520, 566, 573, 613, 616, 617, 627–629,

673, 682, 817

Segregation: 313, 562, 563, 568

Serial number: 535, 820, 824

Shielding: 226, 409, 501, 520, 617, 627, 628, 653, 659, 671, 716, 817

Shipment: 204, 221, 237, 501–503, 530, 546, 557–561, 573, 576, 677, 680, 802,

803, 805, 809, 825–828, 830–838, 840

Shipping name: 530, 546, 547

Special arrangement: 238, 310, 434, 527, 529, 546, 558, 575, 579, 802, 829–833,

836

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

INDEX

167

Special form: 201, 220, 239, 415, 429, 430, 433, 546, 559, 602–604, 642, 659,

701, 704, 709, 802–804, 823, 832, 834, 836–838

Specific activity: 226, 240, 409

Storage: 106, 505, 507, 562, 568, 569

Stowage: 219, 230, 313, 554, 565, 576, 809, 836–838

Surface contaminated object (SCO): 241, 244, 412–414, 517–523, 537, 540, 544,

546, 572

Tank: 242, 505, 509, 514, 523, 538, 539, 543, 544, 551, 571, 627, 628

Tank container: 242

Tank vehicle: 242

Temperature: 229, 420, 503, 616, 619, 620, 639, 649, 654–656, 666, 670, 673,

679, 703, 708–711, 728, 812, 836, 838

Test(s): 111, 224, 503, 601, 603, 605, 624, 626–630, 632, 634, 648, 650, 651,

653, 655, 658–660, 662, 663, 670–672, 674, 678, 680–685, 701–713,

716–737, 803, 805, 809, 817

Tie-down: 638

Transport document(s): 313, 540, 545–547, 552–555, 584–588

Transport index (TI): 244, 523, 524, 526, 529, 540, 546, 566, 567

Type A package: 231, 428–430, 534, 635–651, 725, 819, 832

Type B(M) package: 231, 431–433, 501, 503, 535, 536, 558, 577, 578, 667, 668,

730, 802, 811–813, 825, 832, 833, 838

Type B(U) package: 231, 431–433, 501, 503, 535, 536, 558, 652–667, 730, 802,

808, 810, 812, 832

Type C package: 231, 431, 432, 501, 503, 535, 536, 558, 669–672, 683, 730,

734–737, 802, 808, 810, 832

Ullage: 420, 649

Unilateral approval: 205, 503, 803, 807, 808, 823, 832

UN number: 401, 419, 530, 544, 546, 572

Unpackaged: 222, 244, 417, 423, 514, 520, 522, 523, 544, 562, 570, 572, 673

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

INDEX

168

Uranium hexafluoride: 231, 419, 420, 422, 425, 523, 580, 581, 631–634, 680,

718, 802, 807, 832, 833, 838

Ve hi cl e: 217, 219, 223, 242, 248, 313, 534, 551, 552, 566, 571–575, 832

Venting: 229, 668, 820, 825

Vessel: 217, 219, 249, 527, 575, 576, 802, 825

Water: 106, 217, 409, 536, 601, 603, 605, 611, 660, 672, 673, 680, 681, 683–685,

703, 710, 711, 719–721, 726, 729–733, 836, 838

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

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

12-29971

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

INTERNATIONAL ATOMIC ENERGY AGENCY

VIENNA

ISBN 978–92–0–133310–0

ISSN 1020–525X

“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.”

Yukiya Amano

Director General

Safety through international standards

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