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.

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;
(c) The issue date and an expiry date;
(d) Mode(s) of carriage;
(e) Any restrictions on the modes of carriage, type of vehicle, 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 carried.";
(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 a 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 by 30 cm, showing the make-up of the package shall also be provided, accompanied by a
brief description of the packaging, including materials of manufacture, gross mass, general
outside dimensions and appearance;
(j) A specification of the authorized radioactive contents, including any restrictions on the
radioactive contents which 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 2.2.7.2.3.5 (f) if applicable;
(k) Additionally, for packages containing fissile material:
(i) a detailed description of the authorized radioactive contents;
(ii) the value of the criticality safety index;
(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 6.4.11.5 (b)) for a change in neutron multiplication assumed in
the criticality assessment as a result of actual irradiation experience; and
(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 6.4.8.5, 6.4.8.6, and 6.4.8.15, as applicable;
(q) Any emergency arrangements deemed necessary by the competent authority;
(r) A specification of the applicable management system as required in 1.7.3;
(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.

 

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);
(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 shipment is
approved;
(e) Any restrictions on the modes of carriage, type of vehicle, 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 carried.";
(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 which 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 2.2.7.2.3.5 (f) if applicable;;
(k) Any emergency arrangements deemed necessary by the competent authority;
(l) A specification of the applicable management system as required in 1.7.3;
(m) If deemed appropriate by the competent authority, reference to the identity of the applicant;
(n) Signature and identification of the certifying official.

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;
(c) The issue date and an expiry date;
(d) Any restriction on the modes of carriage, 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 carried.";
(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 5.1.5.1.2, if
deemed appropriate;
(i) Identification of the packaging;
(j) Description of the packaging by a reference to the drawings or specification of the design.
If deemed appropriate by the competent authority, a reproducible illustration, not larger
than 21 cm by 30 cm, showing the make-up of the package shall also be provided,
accompanied by a brief description of the packaging, including materials of manufacture, gross
mass, general outside dimensions and appearance;
(k) Specification of the design by reference to the drawings;
(l) A specification of the authorized radioactive content, including any restrictions on the
radioactive contents which 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 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 2.2.7.2.3.5 (f),
if applicable;
(m) A description of the containment system;
(n) For package designs containing fissile material which require multilateral approval of the
package design in accordance with 6.4.22.4:
(i) a detailed description of the authorized radioactive contents;
(ii) a description of the confinement system;
(iii) the value of the criticality safety index;
(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 6.4.11.5 (b)) for a change in neutron multiplication assumed in
the criticality assessment as a result of actual irradiation experience; and
(vii) the ambient temperature range for which the package design has been approved;
(o) For Type B(M) packages, a statement specifying those requirements of 6.4.7.5, 6.4.8.4, 6.4.8.5,
6.4.8.6 and 6.4.8.9 to 6.4.8.15 with which the package does not conform and any amplifying
information which 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 6.4.6.4 which apply if any and any amplifying information which 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
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 6.4.8.5, 6.4.8.6 and 6.4.8.15, as applicable;
(t) A specification of the applicable management system as required in 1.7.3;
(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.

Each certificate issued by a competent authority for alternative activity limits for an exempt
consignment of instruments or articles according to 5.1.5.2.1 (d) 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 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), 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 2.2.7.2.2.2 (b);
(j) If deemed appropriate by the competent authority, reference to the identity of the applicant;
(k) Signature and identification of the certifying official.

The competent authority shall be informed of the serial number of each packaging manufactured to a
design approved by them under 1.6.6.2.1, 1.6.6.2.2, 6.4.22.2, 6.4.22.3 and 6.4.22.4.

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.

6.5

REQUIREMENTS FOR THE CONSTRUCTION AND TESTING OF INTERMEDIATE BULK CONTAINERS (IBCs)

General requirements

Scope

The requirements of this Chapter apply to intermediate bulk containers (IBCs) the use of which is
expressly authorized for the carriage of certain dangerous goods according to the packing instructions
indicated in Column (8) of Table A in Chapter 3.2. Portable tanks and tank-containers which meet the
requirements of Chapter 6.7 or 6.8 respectively are not considered to be IBCs. IBCs which meet the
requirements of this Chapter are not considered to be containers for the purposes of ADR. The letters
IBC only will be used in the rest of the text to refer to intermediate bulk containers.

Exceptionally, IBCs and their service equipment not conforming strictly to the requirements herein,
but having acceptable alternatives, may be considered by the competent authority for approval. In
addition, in order to take into account progress in science and technology, the use of alternative
arrangements which offer at least equivalent safety in use in respect of compatibility with the
properties of the substances carried and equivalent or superior resistance to impact, loading and fire,
may be considered by the competent authority.
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