Dangerous Goods by Road
Applications and approvals for radioactive material carriage
(Reserved)
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 carriage, the type of vehicle, and the
probable or proposed route; and
(c) The details of how the precautions and administrative or operational controls, referred to in
the certificate of approval for the package design, if applicable, issued under 5.1.5.2.1 (a) (v),
(vi) or (vii), are to be put into effect.
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 carriage is at
least equivalent to that which would be provided if all the applicable requirements of ADR 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 of ADR; and
(b) A statement of any special precautions or special administrative or operational controls
which are to be employed during carriage to compensate for the failure to meet the applicable
requirements of ADR.
An application for approval of Type B(U) or Type C package design 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;
(b) A detailed statement of the design, including complete engineering drawings and schedules of
materials and methods of manufacture;
(c) A statement of the tests which have been done and their results, or 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, a statement and a
justification of any assumption in the safety analysis relating to the characteristics of the fuel
and a description of any pre-shipment measurement as required by 6.4.11.5 (b);
(g) Any special stowage provisions necessary to ensure the safe dissipation of heat from the
package considering the various modes of carriage to be used and type of vehicle or container;
(h) A reproducible illustration, not larger than 21 cm by 30 cm, showing the make-up of the
package; and
(i) A specification of the applicable management system as required in 1.7.3.
An application for approval of a Type B(M) package design shall include, in addition to the general
information required in 6.4.23.4 for Type B(U) packages:
(a) A list of the requirements specified in 6.4.7.5, 6.4.8.4 to 6.4.8.6 and 6.4.8.9 to 6.4.8.15
with which the package does not conform;
(b) Any proposed supplementary operational controls to be applied during carriage not regularly
provided for in this Annex, but which are necessary to ensure the safety of the package or to
compensate for the deficiencies listed in (a) above;
(c) A statement relative to any restrictions on the mode of carriage and to any special loading,
carriage, unloading or handling procedures; and
(d)
A statement of the range of ambient conditions (temperature, solar radiation) which are
expected to be encountered during carriage and which have been taken into account in the
design.
The application for approval of designs for packages containing 0.1 kg or more of uranium
hexafluoride shall include all information necessary to satisfy the competent authority that the design
meets the applicable requirements of 6.4.6.1, and a description of the applicable management system
as required in 1.7.3.
An application for a fissile package approval shall include all information necessary to satisfy the
competent authority that the design meets the applicable requirements of 6.4.11.1, and a specification
of the applicable management system as required by 1.7.3.
An application for approval of design for special form radioactive material and design
for low
dispersible radioactive material 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;
(c) A statement of the tests which have been done and their results, or 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 ADR;
(d) A specification of the applicable management system as required in 1.7.3; and
(e) Any proposed pre-shipment actions for use in the consignment of special form radioactive
material or low dispersible radioactive material.
An application for approval of design for fissile material excepted from "FISSILE" classification in
accordance with Table 2.2.7.2.1.1, under 2.2.7.2.3.5 (f) 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
calculation methods to show that the material is capable of meeting the requirements specified
in 2.2.7.2.3.6;
(c) A specification of the applicable management system as required in 1.7.3;
(d) A statement of specific actions to be taken prior to shipment.
An application for approval of alternative activity limits for an exempt consignment of instruments or
articles 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;
(c) Maximum external radiation levels arising from 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
carriage;
(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
International Basic Safety Standards for Protection against Ionizing Radiation and for the
Safety of Radiation Sources, Safety Series No.115, IAEA, Vienna (1996), including individual
doses to transport workers and members of the public and, if appropriate, collective doses
arising from routine, normal and accident conditions of carriage, based on representative
carriage scenarios the consignments are subject to.
Each certificate of approval issued by a competent authority shall be assigned an identification
mark.
The identification mark shall be of the following generalized type:
VRI/Number/Type Code
(a) Except as provided in 6.4.23.12 (b), VRI represents the distinguishing sign used on vehicles in
international road traffic1;
(b) The number shall be assigned by the competent authority, and shall be unique and specific with
regard to the particular design or 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;
(c) The following type codes shall be used in the order listed to indicate the 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 2.2.7.2.3.6 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, then the following type codes shall be used:
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 transitional provisions of 1.6.6.2 to 1.6.6.4, and for low dispersible
radioactive material, the symbols "-96" shall be added to the type code.
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 6.4.23.11 (a), (b), (c) and (d) above, except that, for
packages, only the applicable design type codes including, if applicable, the symbols "-96", shall
appear following the second stroke, that is, the "T" or "X" shall not appear in the identification
marks
1 Distinguishing sign of the State of registration used on motor vehicles and
trailers in international road traffic,
e.g. in accordance with the Geneva Convention on Road Traffic of 1949 or the Vienna Convention on
Road Traffic of 1968.
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 on both 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 on both
the package and on the certificate of approval for the package design); and
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 on both the package and on the certificate of approval for the package design);
(b) Where multilateral approval is effected by validation in accordance with 6.4.23.20, 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 which 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;
(c) The revision of a certificate shall be indicated by a parenthetical expression 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 regulations) 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.
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;
(c) The issue date and an expiry date;
(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 which includes the activities involved and which
may include the physical and chemical form;
(i) A specification of the applicable management system as required in 1.7.3;
(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.
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;
(c) The issue date and an expiry date;
(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 1.7.3;
(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 2.2.7.2.3.6.