1. ------IND- 2016 0191 CZ - EN- ------ 20160525 --- --- PROJET 
Draft  
 
DECREE  
of 
concerning the approval of some products in the field of peaceful use of nuclear energy 
and ionising radiation and the carriage of radioactive or fissile material  
The State Off ice for Nuclear Safety stipulates, pursuant to §  236 of Act No .../..., the Atomic 
Act (hereinafter the “Act”), towards the implementation of §  9(4)(a) and (b), §  24(7), 
§ 137(6), §  138(6)(a) to (c), §  141(3)(a) to (e), and §  143(4):  
§ 1 
Subject matter  
This decree incorporates relevant Euratom regulations1) and regulates the type approval 
of certain products in the field of the peaceful use of nuclear energy and ionising radiation and 
the carriage of radioactive or fissile material.  
§ 2 
Definitions  
For the purposes of this implementing decree, the following definitions apply:  
a) the value A 1 is the value of activity of special form radioactive material listed in Table  2 
of Annex  3 to this decree, or stipulated pursuant to  Points  3 to 7 of Annex  3 to this 
decree, and used to stipulate activity limits for purposes of carriage;  
b) the value A 2 is the value of activity of an other than special form radioactive material 
listed in Table 2 of Annex 3 to this decree, or stipulated pu rsuant to Points 3 to 7 of 
Annex 3 to this decree, and used to stipulate activity limits for purposes of carriage;  
c) a package is packaging with its radioactive content;  
d) a confinement system is the organisation of fissile material in packaging or the 
organis ation of part of packaging in a manner necessary to control criticality;  
e) a containment system is the organisation of part of packaging in a manner necessary to 
prevent the escape of the radioactive or fissile material during transport;  
f) a freight container is a device for the carriage of packaged or unpackaged products via 
one or more modes of transport without the handling of individual items of its contents 
that has a permanent closure, is sufficiently rigid and durable for repeated use and has 
equipment t hat permits its handling, especially its transfer among means of transport from 
one mode of transport to another; freight containers are broken down into  
1. small containers with all external dimensions of less than 1.5  m or with an internal 
volume of less th an 3 m3; 
                                                 
1)  Council Directive 2006/117/Euratom of 20  November  2006 on the supervision and control of shipments of 
radioactive waste and spent fuel.  
Commission Decision 2008/312/Euratom of 5 March 2008, establishing the standard document for the 
supervision and control of shipments of radioactive waste and spent fuel referred to in Council D irective 
2006/117/Euratom.  
  - 2 - 
2. intermediate bulk containers for unpackaged substances or items, which are 
mechanical portable containers whose resistance to stress during handling and 
transport is verified by testing, and with an internal volume of no greater than 3 m3; 
3. large c ontainers, which are any container not meeting the definitions in Points  1 and 
2; 
g) an overpack is a protective case used by one carrier as one handling unit to facilitate the 
transport of one or more packages;  
h) a consignment is all packages or packagings or a load of radioactive or fissile substances 
handed over by the carrier for transport;  
i) exclusive use is the use of a conveyance or large container by one carrier, whose 
instructions govern all loading and unloading activity during the entire course of carri age; 
j) a low specific activity material is a radioactive material whose own specific activity is 
naturally limited, or a radioactive material whose mean specific activity has been 
intentionally limited;  
k) a low toxicity radionuclide source emitting alpha radia tion (hereinafter a “low toxicity 
alpha emitter ”) is natural uranium, depleted uranium, natural thorium, 235U, 238U, 232Th, 
228Th, and 230Th contained in ores or in physical or chemical concentrates, or other 
radionuclide sources emitting alpha radiation ( hereinafter “alpha emitter ”) with 
transformation half -lives of less than 10 days;  
l) maximum normal operating pressure is the maximum overpressure that can occur in a 
retention system over the course of one year at a temperature and sunlight corresponding 
to ambient conditions during transport, assuming no ventilation, external cooling via an 
auxiliary system, or operating checks during transport occur;  
m) a surface contaminated object is a solid object that is not itself radioactive but which has 
radioactive or fissile material distributed on its surface;  
n) unirradiated thorium is thorium containing not more than 10-7 g 233U per gram of 232Th; 
o) unirradiated uranium is uranium containing not more than 2.103 Bq of plutonium per 
gram of 235U, at most 9.106 Bq of fissio n products per gram of 235U, and at most 5.10-3 g 
236U per gram of 235U; 
p) uranium  
1. natural uranium, including chemically separated uranium, containing uranium 
isotopes in the following distribution: approximately 99.28  % by mass of 238U, 
approximately 0.72  % by mass of 235U, and an insignificant mass percentage of 234U; 
2. depleted uranium with a smaller mass percentage of 235U than natural uranium; 
depleted uranium also contains an insignificant mass percentage of 234U; 
3. enriched uranium with a higher mass perce ntage of 235U than 0.72  %; enriched 
uranium also contains an insignificant mass percentage of 234U; 
q) routine conditions of carriage are conditions during which no radiation emergency 
occurs;  
r) normal conditions of carriage are conditions during which a radiat ion emergency 
simulated by tests pursuant to Points  19 to 25 of Part  II of Annex  1 to this decree occurs;  
s) accident conditions of carriage are conditions during which a radiation emergency 
simulated by tests pursuant to Points  26 to 37 of Part  II of Annex  1 to this decree occurs.   - 3 - 
§ 3 
Carriage of a radioactive or fissile material requiring authorisation, classification of 
radioactive or fissile material, requirements imposed on radioactive or fissile material  
(Re §  9(4)(a) and (b) of the A tomic Act)  
(1) Carriage requiring authorisation pursuant to §  9(4)(a) or (b) of the Atomic Act is 
carriage of  
a) fissile material if the sum of the criticality safety indices of packages in one conveyance 
or shipping container is greater than 50;  
b) nuclear fuel;  
c) a package containing special form radioactive material with activity greater than 3.103 A1 
or radioactive material other than special form with activity greater than 3.103 A2 or 
radioactive material with activity greater than 1  000 TBq, depending on which of  these 
values is lower;  
d) radioactive or fissile material in packaging of Type B(M) that is not designed for a 
temperature range of minus 40  ºC to plus 70  ºC or is not designed to permit occasional 
controlled ventilation;  
e) radioactive or fissile material via a vessel intended for this purpose with a specified 
radiation protection programme . 
(2) Carriage requiring authorisation pursuant to §  9(4)(a) or (b) of the Atomic Act, and in 
the case of international carriage also authorisation of the relevant authority of t he state that 
the carriage concerns, is carriage of  
a) radioactive or fissile material containing radionuclides whose values of A 1 and A2 not 
listed in Table  2 of Annex  3 to this decree were stipulated by calculation pursuant to 
Points  3 to 7 of Annex  3 to th is decree;  
b) radioactive or fissile material contained in an instrument or product and containing 
radionuclides whose values for a package exception listed in column  5 of Table  2 of 
Annex  3 to this decree were replaced by values calculated according to princ iples and 
methods stipulated in Annex  6 to this decree; and  
c) fissile substances pursuant to Point  17(f) of Annex  3 to this decree.  
(3) Classification of radioactive or fissile substances and packages and requirements 
imposed on them are provided in Points  1 and  8 to 34 of Annex  3 to this decree, and in Part  I 
of Annex  1 to this decree.  
§ 4 
Packaging for the carriage, storage  or deposit of radioactive or fissile material  
(Re §  9(4)(a) and (b) of the Atomic Act)  
(1) Requirements for specification o f the type of packaging for the transport of 
radioactive or fissile material, depending on the radioactive content of the package, are 
stipulated in Annex  3 to this decree.  
(2) Types of packaging for the carriage of a radioactive or fissile material and 
corres ponding packages are as follows:  
a) packaging for a package exception and a package exception;  
b) Type  IP-1 packaging and a Type  IP-1 industrial package;  
c) Type IP -2 packaging and a Type IP -2 industrial package;   - 4 - 
d) Type IP -3 packaging and a Type IP -3 industrial packa ge; 
e) Type  A packaging and a Type  A package;  
f) Type  B(U) packaging and a Type  B(U) industrial package;  
g) Type  B(M) packaging and a Type  B(M) industrial package;  
h) Type  C packaging and a Type  C industrial package.  
(3) Packaging for the transport of radioactive material  that is not fissile material must, 
depending on its type, meet the requirements of Part  I of Annex  1 to this decree, as follows:  
a) every packaging must meet the requirements of Points  7 to 18 and of Points  19 to 21, if it 
is intended for air carriage;  
b) packa ging for package exceptions must meet the requirements of Point  22; 
c) Type IP -1, IP -2, and IP -3 packaging must meet the requirements of Points  23 to 30;  
d) packaging for the transport of 0.1  kg or more of uranium hexafluoride must meet the 
requirements of Point s 31 to 33, or of Point  34; 
e) Type A packaging must meet the requirements of Points  35 to 51;  
f) Type B(U) packaging must meet the requirements of Points  52 to 66;  
g) Type  B(M) packaging must meet the requirements of Points  67 and 68; and  
h) Type C packaging must mee t the requirements of Points  69 to 72.  
(4) Packaging for the transport of fissile material must, depending on its type, meet the 
requirements of (3)(a) to (h) and the requirements of Points  73 to 86 of Part  I of Annex  1 to 
this decree. The requirements of Poin ts 73 to 86 of Part  I of Annex  1 to this decree do not 
apply to packages in a consignment containing only fissile material that meets the 
requirements of one of (a) through (f)  of Point  17 of Annex  3 to this decree (hereinafter 
“exceptions of fissile mater ial”). 
(5) Type S packaging for the storage of radioactive or fissile material and type D 
packaging for the deposit of radioactive or fissile material must, depending on its type, meet 
the requirements of Annex  2 to this decree.  
§ 5 
Require ments regarding the content of documentation for authorisation of carriage of 
radioactive or fissile material  
(Re §  24(7) of the Atomic Act)  
Documentation for authorisation of carriage of radioactive or fissile material contained in 
an instrument or produc t, and containing radionuclides for which values for excepting a 
package have been replaced by values calculated according to the principles and methods 
stipulated in Annex  6 to this decree, must for the purpose of the calculation of individual 
dosages for  a transport worker and a representative individual, and collective dosages under 
routine conditions of carriage, normal conditions of carriage  and under accident conditions of 
carriage, contain data on  
a) the expected use of the device or product and the rad ionuclides it contains;  
b) the maximum activity of the radionuclides in the device or product;  
c) the maximum radiation level on the surface and at a distance of 1  m from the device or 
product;  
d) the chemical and physical form of the radionuclides in the device or  product;  
e) the design of the device or product, especially the containment system and radiation 
shielding for the radionuclides it contains;   - 5 - 
f) the management system used, including quality control, and that the device or product is 
manufactured according to t he design type specifications;  
g) verification procedures to ensure that radionuclide activity and absorbed dose equivalent 
limits declared for the device or product are not exceeded;  
h) the maximum number of devices or products that are to be shipped in one con signment, 
annually.  
§ 6 
The method of stipulating and maximum permissible values of the transport index 
(TI), the criticality safety index, unfixed contamination and absorbed equivalent dose, 
and the manner in which the package category is specified  
(Re §  141(3)(a) of the Atomic Act)  
(1) The method for determining  
a) the TI for a package, an overpack, a freight container, unpackaged material with low 
mass activity in group LSA -I, or an unpackaged surface contaminated item in group 
SCO -I is stipulated in Points  23 and 24 of Annex  4 to this decree;  
b) the criticality safety index for  
1. a consignment, a freight container and an overpack are stipulated in Point  25 of 
Annex  4 to this decree; and  
2. a package is stipulated in Points  84 to 86 of Part  I of Annex  1 to this decree; and 
c) a package category is stipulated in Points  29 of Annex  4 to this decree.  
(2) The maximum permissible values for the TI, criticality safety index, and radiation 
level on the surface and at a given distance from it for a package, an overpack, and a 
conveyanc e are stipulated in Points  26 to 28, 66 to 69, and 73 of Annex  4 to this decree.  
(3) The maximum permissible non -fixed contamination values for a package, an 
overpack, and a conveyance are stipulated in Points  8, 9, 13, and 14 of Annex  4 to this decree.  
§ 7 
Technical and organisational conditions of carriage and transport of radioactive or 
fissile material  
(Re §  141(3)(b) of the Atomic Act)  
(1) Technical and organisational conditions that must be fulfilled  
a) prior to the initial and prior to every further carriage of  radioactive or fissile material are 
stipulated in Points  1 to 3 of Annex  4 to this decree;  
b) to secure the carriage of individual package types are stipulated in Points  4 to 22 of 
Annex  4 to this decree;  
c) for the safe separation of packages, overpacks  or containers containing radioactive or 
fissile material and some radioactive material from transport workers, the population, 
unexposed photographic film, and other dangerous items during carriage and stowage are 
stipulated in Points  62 and 63 of Annex  4 to thi s decree;  
d) for the safe placement of a consignment of packages on or in the means of transport and 
during stowage are listed in Points  64 to 67 of Annex  4 to this decree; and  
e) for the safe mutual separation of groups of packages containing fissile material d uring 
carriage and during stowage are listed in Points  68 to 70 of Annex  4 to this decree.   - 6 - 
(2) Further requirements to ensure safe carriage are stipulated in Annex  4 to this decree, 
and if they apply to  
a) carriage documents and marking in general, in Points  45 to 61;  
b) carriage via rail and road, in Points  71 to 74;  
c) carriage via vessels, in Points  75 and 76;  
d) carriage via air, in Points  77 to 79;  
e) carriage via post, in Point  80; 
f) other essentials of carriage, in Points  81 to 88.  
§ 8 
Requirements regarding the content,  language and availability of documentation 
required for the carriage and transport of radioactive or fissile material  
(Re §  141(3)(c) of the Atomic Act)  
(1) Requirements for  
a) the essentials of a description of a consignment in a carriage document are stipulate d in 
Point  46 of Annex  4 to this decree;  
b) carriage documentation are stipulated in Points  47 to 53 of Annex  4 to this decree; and  
c) documentation and operating rules that the carrier must ensure are available to the 
consignor are stipulated in Points  54 to 56  of Annex  4 to this decree.  
(2) During the cross -border carriage of radioactive waste or spent nuclear fuel pursuant to 
§ 9(4)(d) of the Atomic Act, documentation accompanying carriage also must include relevant 
completed forms A -1 or B -1, A -4a or B -4a, and A -5 or B -5, provided in Annex  5 to this 
decree.  
CELEX: 32006L0117  
§ 9 
The manner, scope and deadlines for notifying the administrative authorities for 
carriage  
(Re §  141(3)(d) of the Atomic Act)  
The manner, scope, and deadlines for notifying  
a) the Office and t he relevant authority of the state that international transport concerns are 
stipulated in Points  57 to 60 of Annex  4 to this decree; and  
b) the consignor by the carrier regarding necessary measures for carriage are stipulated in 
Points  54 to 56 of Annex  4 to this decree.  
§ 10 
The marking, appearance and method of use of labelling to mark a package, freight 
container and conveyance for carriage  
(Re §  141(3)(e) of the Atomic Act)  
(1) The marking of a package and overpack with UN numbers and naming pursuant to 
Table  1 of Annex  3 to this decree is stipulated in Points  30 to 37 of Annex  4 to this decree.   - 7 - 
(2) The use labelling to mark a package, overpack, and freight container is stipulated in 
Points  38 and 39 of Annex  4 to this decree. The completion of these labels is sti pulated in 
Points  40 to 42 of Annex  4 to this decree.  
(3) The use of placards and tables to mark a freight container and conveyance is 
stipulated in Points  43 and 44 of Annex  4 to this decree.  
(4) The appearance and dimensions of the trefoil radioactivity symbol, labels, placards, 
and tables are stipulated in Figures  1 to 7 of Annex  4 to this decree.  
§ 11 
Products subject to Type Approval  
(Re §  137(6) of the Atomic Act)  
(1) Type approval applies to the following packaging intended for carriage, storage or 
deposit of ra dioactive or fissile material, including radioactive waste:  
a) Type  IP-1, IP -2, IP -3 and A for the carriage of fissile material, aside from excepted fissile 
material;  
b) for the carriage of 0.1  kg or more of uranium hexafluoride; in the event of international 
carriage of radioactive shipments pursuant to Point  34 of Part  I of Annex  1 to this decree, 
type approval by the relevant authority of the state that the carriage concerns is also 
necessary;  
c) Type  B(U), B(M) and C packaging for the carriage of radioactive or fissile material; in 
the event of international carriage of Type  B(M) radioactive shipments pursuant to 
Point  67 of Part  I of Annex  1 to this decree, type approval by the relevant authority of the 
state that the carriage concerns is also necessary;  
d) for the  carriage of a radioactive or fissile material requiring multilateral approval 
pursuant to international treaties by which the Czech Republic is bound;  
e) Type  D intended for the deposit of spent or irradiated nuclear fuel or radioactive waste 
produced by its  reprocessing; and  
f) Type  S intended for the storage of radioactive or fissile material, including radioactive 
waste, specifically for special form radioactive material whose activity exceeds A 1, or for 
radioactive material other than special form whose acti vity exceeds A 2. 
(2) Special form radioactive material with properties stipulated in Points  2 to 4 of Part  I 
of Annex  1 to the draft decree and low dispersible radioactive material with properties 
stipulated in Point  5 of Part  I of Annex  1 to the draft decree are subject to type approval.  
§ 12 
Documentation for a type approval application, tests or calculations and analyses and 
the contents of their documentation  
(Re §  138(6)(a) and (b) of the Atomic Act)  
(1) The scope, contents and performance method of tests or c alculations and analyses for 
a type approval application for special form radioactive material, low dispersible radioactive 
material or packaging for the carriage, storage or deposit of radioactive or fissile material are 
stipulated in Part  II of Annex  1 to this decree.  
(2) Documentation for an application for type approval of special form radioactive 
material, low dispersible radioactive material or packaging for the carriage, storage or deposit 
of radioactive or fissile material is product test documentation or documentation of  - 8 - 
calculations, safety assays and analyses, and their independent verification (hereinafter “test 
documentation ”). Documentation for a product type approval application comprises,  
a) for packaging, test documentation pursuant to Points  13 to  37 of Part  II of Annex  1 to this 
decree applicable to the given type of packaging with an evaluation of results in 
accordance with Points  1 and 2 of Part  II of Annex  1 to this decree; evaluation of results 
proves compliance with requirements stipulated fo r the given type of packaging in §  4(3) 
to (5);  
b) for special form radioactive material, test documentation pursuant to Points  4 to 11 of 
Part II of Annex  1 to this decree with an evaluation of results in accordance with Points  1 
and 2 of Part  II of Annex  1 to this decree; evaluation of results proves compliance with 
requirements in Points  2 to 4 of Part  I of Annex  1 to this decree; and  
c) for low dispersible radioactive material, test documentation pursuant to Points  3 and 12 
of Part  II of Annex  1 to this decre e with an evaluation of results in accordance with 
Points  1 and 2 of Part  II of Annex  1 to this decree; evaluation proves compliance with the 
requirements of Point  5 of Part  I of Annex  1 to this decree.  
§ 13 
Requirements for an authorised corporate subject  performing tests and independent 
verification of tests or calculations and analyses for a product type approval 
application;  
(Re § 138(6)(c) of the Atomic Act)  
(1) A corporate entity that performs tests for type approval of a special form radioactive 
material , a low dispersible radioactive material or packaging for the transport, storage or 
deposit of radioactive or fissile material must  
a) have a facility equipped for the performance of tests pursuant to Part  II of Annex  1 to this 
decree appropriate for the give n product type;  
b) have drawn up procedures for the performance of tests pursuant to Part  II of Annex  1 to 
this decree appropriate for the given product type;  
c) have workers trained for the performance of tests pursuant to Part  II of Annex  1 to this 
decree appr opriate for the given product type;  
d) have a quality management system in place; and  
e) be independent of the applicant.  
(2) A corporate entity performing calculations and analyses or independent verification 
of these calculations and analyses instead of tests appl icable to a given type of special form 
radioactive material, low dispersible radioactive material and packaging for the carriage, 
storage or deposit of radioactive or fissile material must, in accordance with Points  1 and 2 of 
Part II of Annex  1 to this de cree:  
a) use a calculation program for such calculations and analyses or independent verification 
of these calculations and analyses that ensures sufficient precision and accuracy of 
results;  
b) must have workers trained to perform the appropriate calculations a nd analyses or 
independent verification of these calculations and analyses;  
c) have a quality management system in place; and  
d) not be in a dependent relationship with the applicant when performing independent 
verification of calculations and analyses.   - 9 - 
§ 14 
Sam ples of standard documents used for cross -border carriage of radioactive waste or 
spent nuclear fuel  
(Re §  143(4) of the Atomic Act)  
Samples of standard documents used in the area of cross -border carriage of radioactive 
waste or spent nuclear fuel are prov ided in Annex  5 to this decree.  
CELEX: 32008D0312  
§ 15 
This decree was notified in accordance with Directive (EU) 2015/1535 of the European 
Parliament and of the Council of 9  September  2015 laying down a procedure for the provision 
of information in the fi eld of technical regulations and of rules on Information Society 
services.  
§ 16 
Entry into force  
This implementing decree shall enter into force on ....  
 
Chair:  
Engineer Dana Drábová Ph. D.   - 10 - 
 
Annex  1 to Decree  No ... 
 
REQUIREMENTS AND TES T PROCEDURES FOR T YPE APPROVAL  
 
PART  I 
 
I. REQUIREMENTS FOR RADIOACTIVE OR FISSILE MATERIALS, 
PACKAGINGS, AND PACKAGES  
 
I.1. REQUIREMENTS FOR RADIOACTIVE OR FISSILE MATERIALS  
 
I.1.1 Requirements for a radioactive material with low specific activity material in group 
LSA -III 
1. A radioact ive material with low specific activity in group LSA -III must be a solid 
material of such a nature that after the entire contents of the package are subjected 
to the test specified in Point  3 of Part  II, the activity of water does not exceed 0.1 
A2. 
 
I.1.2 Requi rements for special form radioactive material  
2. Special form radioactive material must have at least one dimension greater than 
5 mm. 
 
3. Special form radioactive material shall be of such a nature or shall be so designed 
that 
a) it does not break or shatter  under impact or pressure tests pursuant to Points  5 
and 6 or pursuant to Point  9(a), and during bending tests pursuant to Point  7 of 
Part II; 
b) it does not melt or disperse during heat tests pursuant to Point  8 or 9(b) of 
Part II; 
c) the activity of water duri ng the leaching test pursuant to Points  10 and 11 of 
Part II does not exceed 2  kBq, or for sealed sources, the leakage rate during 
volumetric leakage assessment test does not exceed the permitted limit 
pursuant to ISO 9978:1992 (E).  
 
4. When a sealed capsu le constitutes part of the special form radioactive material, 
the capsule shall be so manufactured that it can be opened only by destroying it.  
 
I.1.3 Requirements for low dispersible radioactive material  
5. Low dispersible radioactive material shall be such tha t the total amount of this 
radioactive material in a package shall meet the following requirements:  
a) the radiation level at 3  m from unshielded radioactive material does not exceed 
10 mSv/h;  
b) if subjected to tests specified in Points  36 and  37 of Part  II, th e airborne release 
in gaseous and particulate forms of up to 100  m aerodynamic equivalent 
diameter would not exceed 100 A 2; a separate specimen may be used for each 
test; and  
c) if subjected to the test specified in Point  3 of Part  II, the activity of water 
would not exceed 100  A2; in the application of this test, the damaging effects 
of the tests specified in (b) shall be taken into account.   - 11 - 
 
I.1.4 Requirements for exception of fissile material  
6. An exceptions of fissile material pursuant to Point  17(f) of Annex  3 to this decree 
shall be subcritical without the need for accumulation control under conditions  
a) of Point  73(a);  
b) consistent with requirements for assessing a set of packages under normal 
conditions of carriage pursuant to Point  84(b) and under accident con ditions of 
carriage pursuant to Point  85(b); and  
c) of Point  83(a) for packages transported by air.  
 
 
I.2. GENERAL REQUIREMENTS  FOR PACKAGINGS AND P ACKAGES  
 
7. A package shall be designed so that  
a) it can be easily and  safely transported with regard  to its mass, vol ume, and 
shape, and   
b) it can be secured in or on the conveyance during transport.  
 
8. A package shall be designed so that  
a) any lifting attachments on the package are functional, and if they fail, the 
fulfilment of other requirements of this decree is not thr eatened, and  
b) safety factors for snatch lifting of the package are met.  
 
9. Attachments and any other features on the outer surface of a package that could be 
used to lift it shall be designed either to support its mass in accordance with the 
requirements o f Point  8. If the requirement in the first sentence is not met, they 
shall be removable or otherwise rendered incapable of being used during 
transport.  
 
10. As far as practicable, packaging shall be so designed and finished that the external 
surfaces are f ree from protruding features and can be easily decontaminated.  
 
11. As far as practicable, the outer layer of a package shall be so designed as to 
prevent the collection and retention of water.  
 
12. Equipment carried together with a package shall not reduc e its safety.  
 
13. A package shall be capable of withstanding the effects of any acceleration, 
vibration or vibration resonance that may arise under routine conditions of 
transport and repeated use so that  
a) there is no deterioration in the effectiveness of the closing devices on the 
various receptacles of the package;  
b) its integrity is not compromised; and  
c) nuts, bolts and other securing devices do not become loose or fall off.  
 
14. The material of the packaging and any components or structures shall be 
physic ally and chemically compatible with each other and with the radioactive 
contents; changes in their characteristics due to irradiation must also be taken into 
account.  
  - 12 - 
15. All valves through which the radioactive contents could escape shall be protected 
against unauthori sed operation.  
 
16. The design of the package shall take into account ambient temperatures and 
pressures that are likely to be encountered in routine conditions of transport.  
 
17. A package shall be so designed that it provides sufficient sh ielding to ensure that, 
under routine conditions of transport and with the maximum design activity of its 
radioactive contents, the radiation level at any point on the external surface of the 
package does not exceed the values specified in Points  16, 27, a nd 28 of Annex  4 
to this decree, taking into account Points  66(b) and 73 of Annex  4 to this decree.  
 
18. The design of a package must also take into account other properties of 
radioactive or fissile material pursuant to Point  7 of Annex  4 to this decree.  
 
 
I.3. ADDITIONAL REQUIREME NTS FOR PACKAGES TRA NSPORTED BY AIR  
 
19. For a package 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.  
 
20. A package  to be transported by air shall be so designed that if it is exposed to 
ambient temperatures ranging from minus 40  °C to plus 55  °C, the integrity of the 
containment system would not be breached.  
 
21. A package to be transported by air shall be capable of withstanding an internal 
pressure that produces a pressure differential of not less than maximum normal 
operating pressure plus 95  kPa, without loss or dispersal of radioactive contents.  
 
 
I.4. REQUIREMENTS FOR PAC KAGE EXCEPTIONS  
 
22. A package exception shall be designed to meet the requirements of Points  7 to 18 
and of Points  19 to 21, if carried by air.  
 
 
I.5. REQUIREMENTS FOR IND USTRIAL PACKAGES  
 
I.5.1. Requirements for Type IP -1 
23. A package exception shall be designed to meet the requirements of Points  7 to 18 
and 36 , and of Points  19 to 21, if carried by air.  
 
I.5.2. Requirements for Type  IP-2 
24. A Type IP -2 package shall be designed to meet the requirements for Type IP -1 as 
specified in Point  23, and so that performance of tests in Points  22 and 23 of 
Part II does not cau se: 
a) loss or dispersal of the radioactive contents; and  
b) more than a 20  % increase in the maximum radiation level on an arbitrary 
location on the external surface of the package.   - 13 - 
 
I.5.3. Requirements for Type IP -3 
25. A Type IP -3 package shall be designed to meet t he requirements for Type IP -1 as 
specified in Point  23, and requirements in Points  37 to 49.  
 
I.5.4. Alternative requirements for Type IP -2 and Type IP -3 
26. A package may be used as Type IP -2 if: 
a) it meets requirements for Type IP -2 specified in Point  23; 
b) it is d esigned to meet requirements for UN Packing Group I or II according to 
the United Nations Recommendations on the Transport of Dangerous Goods, 
Model Regulations; and   
c) performance of tests stipulated for UN Packing Group I or II does not result in  
1. loss or d ispersal of the radioactive contents; and  
2. more than a 20  % increase in the maximum radiation level on an 
arbitrary location on the external surface of the package.  
 
27. A portable tanks may be used as Type IP -2 or Type IP -3, provided that:  
a) it meets require ments for Type  IP-1 specified in Point  23; 
b) it is designed so that  
1. it meets the requirements of the United Nations Recommendations on 
the Transport of Dangerous Goods, Model Regulations, or other 
requirements guaranteeing the same or higher level of protect ion; and  
2. is capable of withstanding a test pressure of 265  kPa; and  
c) is designed so that any additional shielding that is provided  
1. withstands the static and dynamic stresses resulting from handling and 
routine conditions of transport; and  
2. prevents more than  a 20 % increase in the maximum radiation level on 
an arbitrary location on the external surface of the package.  
 
28. Tanks, other than portable tanks, may be used as Type IP -2 or Type IP -3 for 
transporting LSA -I and LSA -II liquids and gases as prescribed in Table  1 of 
Annex  4 to this decree, provided that:  
a) it meets requirements for Type IP -1 specified in Point  23; 
b) it is designed so that  
1. it complies with relevant requirements of the European Agreement 
concerning the International Carriage of Dangerous Goods  by Road 
(ADR)2)or other requirements guaranteeing the same or greater level of 
protection; and  
2. is capable of withstanding a test pressure of 265  kPa; and  
c) is designed so that any additional shielding that is provided  
1. withstands the static and dynamic stres ses resulting from handling 
under routine conditions of transport; and   
2. prevents more than a 20  % increase in the maximum radiation level on 
an arbitrary location on the external surface of the package.  
 
29. A freight container with the characteristics of a permanent enclosure may be used 
as Type IP -2 or Type IP -3, provided that:  
a) its radioactive contents are restricted to solid material;  
                                                 
2)  The European Agreement concerning the International Carriage of Dangerous Goods by Road (ADR), 
decreed under No  64/1987, as amended.   - 14 - 
b) it meets requirements for Type IP -1 specified in Point  23; and  
c) it is designed to meet requirements pursuant to ISO 1496:1 990(E), except for 
dimensions and ratings. If subjected to the tests prescribed in the first sentence 
and to acceleration occurring during routine conditions of transport it would 
prevent:  
1. loss or dispersal of the radioactive contents; and  
2. more than a 20  % increase in the maximum radiation level on an 
arbitrary location on the external surface of the package.  
 
30. A metal intermediate bulk container may also be used as Type IP -2 or Type IP -3, 
provided that:  
a) it meets requirements for Type IP -1 specified in P oint 23; and  
b) it is designed to meet requirements for UN Packing Group I or II pursuant to 
the United Nations Recommendations on the Transport of Dangerous Goods - 
Model Regulations . If subjected to the tests prescribed in the first sentence, but 
with the d rop test performed with the most damaging orientation of the test 
container, it would prevent:  
1. loss or dispersal of the radioactive contents; and  
2. more than a 20  % increase in the maximum radiation level on an 
arbitrary location on the external surface of t he package.  
 
 
I.6. REQUIREMENTS FOR PAC KAGES CONTAINING URA NIUM HEXAFLUORIDE  
 
31. A package intended for the transport of uranium hexafluoride shall meet the 
requirements that pertain to the radioactive and fissile properties of the transported 
material. Except  as allowed in Point  34, uranium hexafluoride in quantities of 
0.1 kg or more shall be packaged and transported in accordance with ISO 
7195:2005(E)  and the requirements of Points  32 and 33.  
 
32. A package intended for contents of 0.1  kg or more of uranium hexafluoride shall 
be designed so that it shall:  
a) withstand a pressure test specified in Point  18 of Part  II without leakage and 
without unacceptable stress, as specified in  ISO 7195:2005(E), except for cases 
specified in Point  34; 
b) withstand the free drop t est specified in Point  22 of Part  II without loss or 
dispersal of the uranium hexafluoride; and  
c) withstand the thermal test specified in Point  28 of Part  II without rupture of the 
containment system, except as allowed in Point  34. 
 
33. A package intended fo r contents of 0.1  kg or more of uranium hexafluoride shall 
not be equipped with pressure relief devices.  
 
34. A package intended for contents of 0.1  kg or more of uranium hexafluoride that  
a) is designed to standards other than ISO 7195:2005(E) guaranteeing t he same or 
higher degree of nuclear safety and radiation protection;  
b) withstands, without leakage and without unacceptable stress, a pressure test 
specified in point 18 of Part II only at a pressure less than 2.76  MPa; or  
c) is designed to contain 9  000 kg or more of uranium hexafluoride and does not 
meet the requirements of Point  32(c);   - 15 - 
may be used for carriage only if its type has been approved by the Office, and in 
the case of international carriage, also by the relevant authority of the state that the 
carriage concerns; other requirements in Points  31 to 33 must be fulfilled.  
 
 
I.7. REQUIREMENTS FOR TYP E A PACKAGES  
 
35. A Type A package shall be designed to meet the requirements of Points  7 to 18, 
36 to 51, and of Points  19 to 21, if carried by air.  
 
36. The smal lest overall external dimension of the package shall not be less than 
10 cm. 
 
37. 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 op ened in an unauthorised manner.  
 
38. 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 this decree.  
 
39. The design of the package shall take into account temperatures ranging from –
40 °C to +70  °C for the components of the packaging. Special attention shall be 
given to freezing temperatures for liquids and to the potential degradation of  
packaging material within the temperature range from –40 °C to +70  °C. 
 
40. The design and manufacturing techniques shall be in accordance with national, 
foreign or international standards or legislation if, during the use of the packaging 
for transport, they ensure the same or greater degree of nuclear safety, radiation 
protection, physical protection and handling of a radiation emergency as stipulated 
by the Atomic Act and its implementing legislation.  
 
41. The design of the package shall include a conta inment system securely closed by a 
positive fastening device that cannot be opened unintentionally or due to pressure 
that may arise within the package.  
 
42. Special form radioactive material may be considered part of the containment 
system.  
 
43. If the co ntainment 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 package.  
 
44. Any component of the containment system must be designed to withst and any 
radiolytic decomposition of liquids and other volatile materials and the generation 
of gas by chemical reaction and radiolysis.  
 
45. The containment system shall retain its radioactive contents during reduction of 
ambient pressure to 60  kPa. 
  - 16 - 
46. All valves, other than pressure relief valves, shall be provided with an enclosure to 
retain any leakage.  
 
47. A radiation shield that encloses a component of the package that is part of the 
containment system shall be so designed as to prevent the unintent ional release of 
that component from the shielded area. Where the radiation shield pursuant to the 
first sentence forms a separate unit, it must be capable of being securely closed by 
a positive fastening device that is independent of any other part of the  packaging.  
 
48. A package shall be so designed that if it were subjected to the tests specified in 
Points  19 to 24 of Part  II, it would prevent:  
a) loss or dispersal of the radioactive contents; and  
b) more than a 20  % increase in the maximum radiation level on  an arbitrary 
location on the external surface of the package.  
 
49. The design of a package intended for liquid radioactive or fissile material shall 
expand with space to accommodate thermal changes in the volume of the liquid 
radioactive contents, dynamic  effects  and filling dynamics.  
 
50. A Type A package designed to contain liquid radioactive or fissile material shall:  
a) meet the conditions specified in Point  48(a) if subjected to tests specified in 
Point  25 of Part  II; and  
b) either contain sufficient absorb ent material that  
1. will absorb at least twice its volume of liquid contents; and   
2. is suitably positioned so as to contact the liquid in the event of leakage; 
or 
c) 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.  
 
51. A package designed for gases shall prevent loss or dispersal of t he radioactive 
contents during tests specified in Point  25 of Part  II, except for a Type A package 
designed for tritium gas or for noble gases.  
 
 
I.8. REQUIREMENTS FOR TYP E B(U) PACKAGES  
 
52. A Type  B(U) package shall be designed to meet the requirements of Poi nts 7 to 
18, 36 to 47, 48(b), 49, 53 to 66 and of Points  19 to 21 if carried by air.  
 
53. 1. A package shall be so designed that heat generated within the package by its 
contents shall not negatively affect compliance with containment system and 
shielding requirements, as follows:  
a) under ambient conditions specified in Points  56 and 57;  
b) under normal conditions of transport specified in Points  19 to 24 of Part  II; and  
c) if left unattended for seven days.  
 
2. Particular attention shall be paid to the effects of heat that may   - 17 - 
a) alter the arrangement, the geometrical form, or the physical state of the 
radioactive contents;  
b) cause deformation or melting of the radioactive content, receptacle, or 
packaging enclosing the radioactive content;  
c) reduce the efficiency of the packaging through differential thermal expansion, 
cracking or melting of the shielding material; and  
d) accelerate corrosion when combined with moisture.  
 
54. Except for a package transported under exclusive use, a package shall be so 
designed that the temper ature of an arbitrary part of an easily accessible surface 
shall not exceed 50  °C 
a) under ambient conditions specified in Point  56; and   
b) if it is not exposed to sunlight.  
 
55. 1. Except for a package transported by air pursuant to Point  19, the maximum 
tempe rature of an arbitrary part of an easily accessible surface of a package shall 
not exceed 85  °C 
a) under conditions of exclusive use under ambient conditions pursuant to 
Point  56; 
b) if it is not exposed to sunlight; and  
c) if left unattended for seven days.  
 
2. Barriers or screens intended for protection of transport workers may be taken 
into account without the need for these to be tested as packages.  
 
56. Ambient temperature is defined as 38  °C. 
 
57. Sunlight exposure conditions and their values are specified in Table  1. 
 
58. A package that includes thermal protection for the purpose of satisfying the 
requirements of the thermal test specified in Point  28 of Part  II shall be so 
designed that such protection will remain effective if the package is subjected to 
the tests specified in Points  19 to 24, and also either in Points  27(a) and 27(b), or 
in Points  27(b) and 27(c) of Part  II, according to rules specified in Point  59(b) 
depending on the mass, average specific mass  and activity of the package. 
Thermal protection  on the exterior of the package shall not be rendered ineffective 
by ripping, cutting, skidding, abrading or rough handling.  
 
Table  1 Insolation values  
Case  Form and location of surface  Insolation for 12  h per day 
(W/m2) 
1 Flat surfaces transported horizo ntally — downward facing  0 
2 Flat surfaces transported horizontally — upward facing  800 
3 Surfaces transported vertically  200a) 
4 Other downward facing (not horizontal) surfaces  200a) 
5 All other surfaces  400a) 
Legend:  
a) Alternatively, a sine functio n may be used, with an absorption coefficient adopted and the effects of possible 
reflection from neighbouring objects neglected.  
  - 18 - 
59. 1. A package shall be designed so that  
a) it restricts the loss of radioactive contents to not more than 10-6 A2 per hour 
after performance of tests specified in Part  19 to 24 of Part  II;  
b) it retains sufficient shielding to ensure that the radiation level 1 m from the 
surface of the package does not exceed 10 mSv/hwith the maximum 
radioactive contents that the package is design ed to contain, according to  
1. Point  27(c) of Part  II, if the package has a mass not greater than 500  kg, 
a mean density not greater than 1  000 kg/m3 based on its external 
dimensions, and radioactive contents greater than 1  000 A2 not as 
special form radioact ive material; or  
2. Point  27(a) of Part  II for other packages; and   
c) the accumulated loss of radioactive contents in a period of seven days does not 
exceed 10 A 2 for krypton -85 and A 2 for all other radionuclides after the 
performance of tests specified in (a) or (b).  
 
2. Where mixtures of different radionuclides are present, the provisions of 
Points  5 to 7 of Annex  3 to this decree shall apply to the calculation of A 2 , except 
that for krypton -85 an effective A 2(i) value equal to 10  A2 may be used. When 
determi ning loss of radioactive contents pursuant to (1)(a), the assessment shall 
take into account the external contamination limits specified in Point  8 of Annex  4 
to this decree.  
 
60. A package for the transport of radioactive contents with activity greater th an 105 
A2 shall be so designed that if it were subjected to the enhanced water immersion 
test specified in Point  30 of Part  II, there would be no rupture of the containment 
system.  
 
61. Compliance with the permitted activity release limits shall depend nei ther upon 
filters nor upon a mechanical cooling system.  
 
62. 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 specifie d in Points  19 to 24 and 26 to 29 of Part  II. 
 
63. 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 19 to 24 and 26 to 29 of 
Part II, the levels of strains in the contai nment system would not attain values that 
would adversely affect the fulfilment of other requirements of this decree.  
 
64. A package shall not have a maximum normal operating pressure in excess of 
700 kPa. 
 
65. A package containing low dispersible radioact ive 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 
characteristics of the low dispersible radioactive ma terial.  
 
66. A package shall be designed for an ambient temperature range of –40 °C to 
+38 °C. 
  - 19 - 
 
I.9. REQUIREMENTS FOR TYP E B(M) PACKAGES  
 
67. 1. Type B(M) packages shall meet the requirements for Type B(U) packages 
specified in Point  52. 
 
2. The requirements o f (1) need not be met during carriage within the Czech 
Republic or during carriage solely between the Czech Republic and certain states 
if the Office or the Office and a relevant authority of those states approve the 
packaging type pursuant to requirements  other than those specified in Points  37, 
55 to 57 and 60 to 66. Notwithstanding, the requirements for Type B(U) packages 
specified in Points  55 and 60 to 66 shall be met as far as practicable.  
 
68. Intermittent venting of Type  B(M) packages is possible pr ovided the the Office 
stipulates this in a type approval decision or if, in the case of international 
carriage, the Office and the relevant authority of the state that the carriage 
concerns stipulate this.  
 
 
I.10. REQUIREMENTS FOR TYP E C PACKAGES  
 
69. A Type C p ackage shall be designed to meet the requirements of Points  7 to 21, 
36 to 47, 48(b), 49, 53 to 57, 61 to 66  and 70 to 72.  
 
70. A package shall be capable of meeting the assessment criteria prescribed for tests 
in Points  59(b) and 63 after being placed 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 assessment of the package are that any thermal insulation of 
the package remains intact, the package is at the maximum n ormal operating 
pressure, and the ambient temperature is 38  °C. 
 
71. 1. A package shall be designed so that  
a) at maximum normal operating pressure and after the performance of tests 
specified in Points  19 to 24, it would restrict the loss of radioactive cont ents to 
not more than 10-6 A2 per hour; and   
b) after performance of the series of tests specified in Point  34 of Part  II 
1. it retains sufficient shielding to ensure that the radiation level 1  m from 
the surface of the package does not exceed 10  mSv/h with the 
maximum radioactive contents that the package is designed to contain; 
and 
2. the accumulated loss of radioactive contents in a period of seven days 
does not exceed 10 A 2 for krypton -85 and A 2 for other radionuclides.  
 
2. Where mixtures of different radionucli des are present, the provisions of 
Points  5 to 7 of Annex  3 to this decree shall apply to the calculation of A 2, except 
that for krypton -85 an effective A 2(i) value equal to 10 A 2 may be used. When 
determining loss of radioactive contents pursuant to (1), external non -fixed 
contamination limits specified in Point  8 of Annex  4 to this decree shall be taken 
into account.  
  - 20 - 
72. A package shall be so designed that if it were subjected to the enhanced water 
immersion test specified in Point  30 of Part  II, there w ould be no rupture of the 
containment system.  
 
 
I.11. REQUIREMENTS FOR PAC KAGES CONTAINING FIS SILE MATERIAL  
 
73. Fissile material shall be transported so as to:  
a) Maintain subcriticality during routine, normal and accident conditions of 
transport; in particular, t he following contingencies shall be considered:  
1. leakage of water into or out of the package;  
2. loss of efficiency of built -in neutron absorbers or moderators;  
3. rearrangement of the contents either within the package or as a result of 
loss from the package;  
4. reduction of spaces within or between packages;  
5. packages becoming immersed in water or buried in snow;  
6. temperature changes; and  
b) meet the requirements:  
1. of Point  36 except for unpackaged material when specifically allowed 
by Point  17(e) of Annex  3 to this decr ee; 
2. of radioactive properties of fissile material stipulated by this decree;  
3. of Point  37 unless the material is excepted by Point  17 of Annex  3 to 
this decree;  
4. of Points  76 to 86 unless the material is excepted by Point  17 of 
Annex  3 to this decree, and Po int 74 or 75.  
 
74. A package containing fissile material that meets the requirements of (d) and one 
of the provisions of (a) to (c) is excepted from the requirements of Points  76 to 86 
of Part  I. 
a) A package containing fissile material in any form provided t hat: 
1. the smallest external dimension of the package is not less than 10  cm; and  
2. the criticality safety index of the package does not exceed 10, where it is 
calculated using the following formula:  
CSI = 50 × 5 × {[mass of uranium -
 ss of other 
fissile radionuclides* in the package (g)]/280}, where the values of Z are 
taken from Table  2. 
b) A package containing fissile material in any form provided that:  
1. the smallest external dimension of the package is not less than 30  cm; 
2. the package, after being subjected to the tests specified in Points  19 to 
24 of Part  II, retains its fissile material contents, preserves the minimum 
overall outside dimensions of at least 30  cm, and prevents the entry of a 
10 cm cube; and  
3. the criticality safety index of the package does not exceed 10, where it 
is calculated using the following formula:  
CSI = 50 × 2 × {[mass of uranium -
other fissile radionuclides in the package (g)]/280}, where the values of 
Z are taken from Table 2.  
c) A package containing fissile material in any form provided that:  
                                                 
*  Plutonium může mít libovolné izotopové složení za předpokladu, že množství plutonia -241 v  radioaktivní 
zásilce je menší než množství plutonia -240.  - 21 - 
1. the smallest external dimension of the package is not less than 10  cm; 
2. the package, after being subjected to the tests specified in Points  19 to 
24 of Part  II, retains its fissile material conte nts, preserves the minimum 
overall outside dimensions of at least 10  cm, and prevents the entry of a 
10 cm cube;  
3. the criticality safety index is calculated using the following formula:  
CSI = 50 × 5 × {[mass of uranium -235 in package (g)]/Z
other fissile radionuclides* in the package (g)]/280}, where the values 
of Z are taken from Table  2; and  
4. the maximum mass of fissile radionuclides in any package does not 
exceed 15  g. 
d) The total mass of beryllium, hydrogenous material enriched i n deuterium, 
graphite and other allotropic forms of carbon in an individual package shall not 
be greater than the mass of fissile radionuclides in the package except where 
their total concentration does not exceed 1  g in any 1  000 g of material. 
Beryllium incorporated in copper alloys up to 4  % by weight of the alloy does 
not need to be considered.  
 
Table  2 Values of Z for calculation of the criticality safety index pursuant to Point  74 
 
Enrichmenta) Z 
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%  45 
 
Legend:  
a) If a package contains uranium with varying enrichments of uranium -235, then the value corresponding to the 
highest enrichment shall be u sed for Z.  
 
 
75. A package containing not more than 1  000 g of plutonium are excepted from the 
requirements of Points  76 to 86 provided that:  
a) not more than 20  % of the plutonium by mass is fissile radionuclides;  
b) the criticality safety index is calculated u sing the following formula: CSI = 50 
× 2 × [mass of plutonium (g)/1000]; and  
c) the amount of uranium contained along with plutonium in the package does not 
exceed 1  % of the mass of the plutonium.  
 
I.11.1.  Contents specification for assessments of package designs co ntaining fissile material  
76. Where the chemical or physical form, isotopic composition, mass or 
concentration, moderation ratio or density, or geometric configuration is not 
known, the assessments of Points  80 to 85 shall be performed assuming that each 
unknown parameter has a value that gives the maximum neutron multiplication  - 22 - 
consistent with known conditions and parameters in these assessments.  
 
77. The assessment of irradiated nuclear fuel according to Points  80 to 85 shall be 
based on:  
a) either an isotop ic composition demonstrated to provide maximum neutron 
multiplication during irradiation history;  
b) or a conservative estimate of the neutron multiplication for assessment of the 
package. After irradiation but prior to shipment, a measurement shall be 
perfor med to confirm the conservatism of the isotopic composition.  
 
I.11.2.  Geometry and temperature requirements  
78. A package, after being subjected to the tests specified in Points  19 to 24:  
a) shall preserve minimum overall outside dimensions of at least 10  cm; and  
b) shall prevent the entry of a 10  cm cube.  
 
79. A package shall be designed for an ambient temperature range of –40 °C to 
+38 °C unless the Office specifies otherwise in a type approval decision.  
 
I.11.3.  Assessment of an individual package in isolation  
80. For a packa ge 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. If the 
design incorporates special features to prevent leakage of water into or out of void 
spaces, even as a result of operator error, it may be assumed that water leaks 
neither into or out of these spaces. Special features are  
a) either multiple high standard water barriers, not less than two of which would 
remain watertight if the package were subject to the tests prescribed in 
Point  85(b), a high degree of quality control in the manufacture, maintenance 
and repair of packaging, and tests to demonstrate the closure of each package 
before each shipment; or  
b) for packages containing uranium hexafluoride with a max imum uranium 
enrichment of 5  % by mass uranium -235: 
1. no physical contact between the valve and any other component of the 
packaging other than at its original point of attachment for the test 
specified in Point  85(b), and perfectly leak -proof valves after t he 
performance of tests specified in Point  28 of Part  II; and   
2. a high degree of quality control in the manufacture, maintenance and 
repair of packaging, and tests to demonstrate closure of each package 
before each shipment.  
 
81. When assessing an isolated package, it shall be assumed that the confinement 
system causes reflection of neutrons as would be caused by a layer of water at 
least 20  cm thick or additional reflection of neutrons as may be provided by the 
surrounding material of the packaging. When it  can be demonstrated that the 
confinement system remains within the packaging following the tests prescribed 
in Point  85(b), the reflection of neutrons by a layer of water at least 20  cm thick 
may be assumed in Point  82(c).  
 
82. A package shall remain subc ritical under the assumptions of Points  80 and 81 and 
under conditions that result in the maximum neutron multiplication consistent 
with:   - 23 - 
a) routine conditions of transport;  
b) the tests specified in Point  84(b); and  
c) the tests specified in Point  85(b).  
 
83. For a package transported by air:  
a) the package shall be subcritical under conditions consistent with the Type C 
package tests specified in Point  34 of Part  II, assuming reflection by at least 
20 cm of water but no leakage of water into the package; and  
b) in the a ssessment pursuant to Point  82, special features pursuant to Point  80 are 
not allowed, unless following Type C package tests specified in Point  34 of 
Part II and water ingress tests for a package pursuant to Point  33 of Part  II, 
leakage of water into and o ut of void spaces is prevented.  
 
I.11.4.  Assessment of package arrays under normal transport conditions  
84. A number N shall be derived, such that a set of five times N packages shall be 
subcritical for the arrangement and package conditions that provide the maxim um 
neutron multiplication, where:  
a) there shall not be any substance between the packages, and the package 
arrangement is exposed on all sides to neutron reflection as would be caused by 
a layer of water at least 20  cm thick; and   
b) the state of each package c orresponds to a condition after the performance of 
tests specified in Points  19 to 24 of Part  II. 
 
I.11.5.  Assessment of package arrays under accident conditions of transport  
85. A number N shall be derived, such that a set of two times N packages shall be 
subcrit ical for the arrangement and package conditions that provide the maximum 
neutron multiplication, where:  
a) there is a hydrogen moderator between the packages, and the package 
arrangement is exposed on all sides to neutron reflection as would be caused by 
a layer of water at least 20  cm thick;  
b) the state of each package corresponds to a condition after the performance of 
tests specified in Points  19 to 24 of Part  II and after the performance of the 
more limiting of the following tests:  
1. for packages having a mass  not greater than 500  kg and an overall 
density not greater than 1  000 kg/m3 based on external dimensions, 
according to Point  27(b), Point  27(c), Point  28, and either according to 
Point  29 or according to Points  31 to 33 of Part  II; or  
2. for other packages a ccording to Point  27(a), Point  27(b), Point  28, and 
either according to Point  29 or according to Points  31 to 33 of Part  II; 
and 
c) when part of the fissile material escapes from the containment system 
following the tests specified in Point  85(b), it shall be  assumed that fissile 
material escaped from each package in the array. All of the fissile material 
shall be arranged and moderated to achieve maximum neutron multiplication 
and neutron reflection as would be caused by a layer of water at least 20  cm 
thick.  
 
I.11.6.  Stipulation of the criticality safety index  
86. The criticality safety index for packages containing fissile material is calculated 
according to the formula: CSI = 50/N, where N is the smaller of two values of N  - 24 - 
according to Points  84 and 85.  
The value o f 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).  
 
 
PART  II 
 
II. TEST PROCEDURES  
 
II.1. DEMONSTRATION OF COM PLIANCE  
 
1. Demonstration of compliance with the performance stand ards required in Part  I 
shall be accomplished by one or more of the methods listed in (a) to (d). The 
methods are as follows:  
a) a test with specimens representing LSA -III material, special form radioactive 
material, or low dispersible radioactive material, o r with prototypes or samples 
of the packaging. The contents of the specimen or the packaging for the tests 
shall simulate as closely as practicable the expected range of radioactive 
contents. The specimens or packaging to be tested shall be prepared as 
presented for transport;  
b) presentation of documentation from a prior successful demonstration of 
conformance pursuant to (a), (c) and (d) of a sufficiently similar nature;  
c) tests with models of appropriate scale with features that are significant with 
respect t o the tested properties, if engineering experience has shown the results 
of such tests to be suitable for design purposes; when a scale model is used, the 
need to adjust certain test parameters shall be taken into account; and  
d) calculation, or reasoned argu ment, when the calculation procedures and 
parameters are generally considered to be reliable or conservative.  
 
2. Appropriate assessment methods shall be used to assess tests performed on the 
specimen, prototype  or sample. Test assessment must prove compli ance with 
requirements stipulated in Part I and compliance of test procedures with 
requirements in Part  II. 
 
 
II.2. LEACHING TESTS FOR A  GROUP LSA -III MATERIAL WITH LO W SPECIFIC 
ACTIVITY AND FOR A L OW DISPERSIBLE RADIO ACTIVE MATERIAL  
 
3. A solid material sample representing the entire contents of the package shall be 
immersed for seven days in water at room temperature. The volume of water to be 
used in the test shall be sufficient to ensure that at the end of the seven -day test 
period, the free volume of the una bsorbed and unreacted water remaining shall be 
at least 10  % of the volume of the solid test sample. The water shall have an initial 
pH of 6 to 8 and a maximum conductivity of 1  mS/m at 20  °C. The total activity 
of the free volume of water shall be measure d following the seven -day immersion 
of the test sample.  
 
  - 25 - 
II.3. TESTS FOR SPECIAL FO RM RADIOACTIVE MATER IAL 
 
II.3.1.  General requirements  
4. Specimens that contain or simulate special form radioactive material shall be 
subjected to an impact test, the percussion test, t he bending test and the heat test 
specified in Points  5 to 9. 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 tha n the methods given 
in Point  10 for non -dispersible solid material or in Point  11 for encapsulated 
material.  
 
II.3.2.  Test methods  
5. Impact test: The specimen shall drop onto the target from a height of 9  m. The 
target shall be as defined in Point  17. 
 
6. Percuss ion 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 pa rt 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 sheet, 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.  
 
7. 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 ra tio 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 steel 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 th e edges 
rounded off to a radius of 3.0 ± 0.3  mm. 
 
8. 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.  
 
9. Specimens that comprise or simulate r adioactive material enclosed in a sealed 
capsule may be excepted from:  
a) the tests prescribed in Points  5 and 6, provided that the specimens are 
alternatively subjected to the impact test for the appropriate class pursuant to 
ISO 2919:2012(E) : 
1. the Class  4 im pact test if the mass of the special form radioactive 
material is less than or equal to 200  g; or 
2. the Class  5 impact test if the mass of the special form radioactive 
material is greater than 200  g but less than 500  g; and  
b) the tests prescribed in Point  8, provided that the specimens are alternatively 
subjected to the Class 6 heat test pursuant to ISO 2919:2012(E) . 
  - 26 - 
II.3.3.  Leaching and volumetric leakage test methods  
10. For specimens that comprise or simulate non -dispersible solid material, a leaching 
assessment sh all be performed as follows:  
a) The specimen shall be immersed for seven days in water at room temperature. 
The volume of water to be used in the test shall be sufficient to ensure that at 
the end of the seven -day test period, the free volume of the unabsorbe d 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 to 8 and a maximum 
conductivity of 1  mS/m at 20  °C; 
b) The water with the specimen shall then be heated to a temperat ure of 50 ± 5  °C 
and maintained at this temperature for 4  h; 
c) The activity of the water shall then be determined;  
d) The specimen shall then be kept for at least seven 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  hours;  
f) The activity of the water shall then be determined.  
 
11. For specimen s 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:  
a) a leaching test:  
The specimen shall be immersed in water at room temperature. The 
water shall have an initial pH of 6 to 8 and a maximum conductivity of 
1 mS/m at 20  °C; 
1. The water with the specimen shall then be heated to a temperature of 50 
± 5 °C and maintained at this temperature for 4  h; 
2. The activity of the water shall then be deter mined;  
3. The specimen shall then be kept for at least seven days in still air at not 
less than 30  °C and with a relative humidity of not less than 90  %; 
4. The process according to Points  1, 2, and 3 shall be repeated once;  
b) The alternative volumetric leakage as sessment shall include any of the tests 
prescribed in ISO 9978:1992(E).  
 
 
II.4. TESTS FOR LOW DISPER SIBLE RADIOACTIVE MA TERIAL  
 
12. A specimen that comprises or simulates low dispersible radioactive material shall 
be subjected to the enhanced thermal test specif ied in Point  36 and the impact test 
specified in Point  37. A different specimen may be used for each of the tests. 
Following the test in the first sentence, the specimen shall be subjected to the 
leach test specified in point 3. After each test it shall be  determined if the 
applicable requirements of Point  5 of Part  I have been met.  
 
 
II.5. TESTS FOR PACKAGES  
 
II.5.1.  Test specimen preparation  
13. All specimens shall be inspected before testing in order to identify and record  - 27 - 
faults or damage, including the following:  
a) divergence from design;  
b) manufacturing defects;  
c) corrosion or other damage; and  
d) deformation.  
 
14. The containment system of the package shall be clearly specified.  
 
15. 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.  
 
II.5.2.  Testing the integrity of the containment system and shielding and assessing criticality 
safety  
16. After performance of tests specified in Points  18 to 37:  
a) faults and damage shall be identified and r ecorded;  
b) it shall be determined whether the integrity of the containment system and 
shielding has been retained to the extent required in Part  I for the package 
under test; and  
c) for a package containing fissile material, it shall be determined whether the 
assumptions and conditions used in the assessments required by Points  73 to 86 
of Part  I also apply to the tested package.  
 
II.5.3.  Target for drop tests  
17. The target for the drop test specified in Points  5, 22, 25(a), 27  and 35 shall be a 
flat, horizontal surfac e 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.  
 
II.5.4.  Test for packages designed to contain uranium hexafluoride  
18. Specimens that com prise 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. For stipulated periodic review of packaging, an equivalent 
non-destructive test may be appli ed that is stipulated in documentation used as the 
basis for a packaging type approval decision issued by the Office, and, in the case 
of international carriage, also by the relevant authority of the state that the 
carriage concerns.  
 
II.5.5.  Tests demonstrating t he ability to withstand normal transport conditions  
19. Tests demonstrating the ability to withstand normal conditions of transport are the 
water spray test, the free drop test, the stacking test and the penetration test. A 
specimen 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 pursuant to the first sentence, provided that 
the requirements of Point  20 are fulfilled . 
 
20. The time interval between the conclusion of the water spray test and the 
subsequent 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. However, if the water spray is  - 28 - 
applied from each of the four directions consecutively, the subsequent test shall be 
performed immediatel y after the end of the water spray test.  
 
21. 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. 
 
22. 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  3 for the app licable package mass. The target shall meet the 
requirements of Point  17; and  
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; or  
c) for c ylindrical fibreboard not exceeding a mass of 100  kg, a separate specimen 
shall be subjected to a free drop onto each of the quarters of each rim from a 
height of 0.3  m. 
 
23. Stacking test: Unless the shape of the packaging effectively prevents stacking, t he 
specimen shall be subjected, for a period of 24  h, to a compressive load equal to 
the greater of the following:  
a) five times the maximum weight of the package; or  
b) the product of the vertically projected area of the package and a pressure of 
13 kPa. 
 
Table  3 Free drop distance for tests proving the ability of a package to withstand normal 
conditions of transport  
Mass of packaging with rated content (kg)  Free drop distance (m)  
less than 5  000 1.2 
greater than or equal to 5  000 and less than 10  000 0.9 
greater than or equal to 10  000 and less than 15  000 0.6 
greater than or equal to 15  000 0.3 
 
24. 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 con tainment system. The bar shall not be significantly deformed by 
the test performance; and  
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. 
 
II.5.6.  Additional tests for Typ e A packages designed for liquids and gases  
25. A specimen, or separate specimens, shall be subjected to tests specified in (a) and 
(b). If it can be demonstrated that one test is more severe for the specimen, the 
specimen shall be subjected to the more se vere test:  
a) Free drop test: the specimen shall drop onto the target so as to cause the most 
damage to the containment system. The height of the drop measured from the  - 29 - 
lowest part of the specimen to the upper surface of the target shall be 9  m. The 
target sh all be as defined in Part  17; 
b) Penetration test: the specimen shall be subjected to the test specified in 
Point  24 with a drop height of 1.7  m. 
 
II.5.7.  Tests demonstrating the ability to withstand accident conditions during transport  
26. The specimen shall be subj ected to the cumulative effects of the tests specified in 
Points  27 and 28, in that order. Following these tests, either this specimen or 
another separate specimen shall be subjected to the water immersion test as 
specified in Point  29, and in the case of a Type B(U) or Type B(M) package 
containing more than 105 A2 and a Type C package, also the test as specified in 
Point  30. 
 
27. Mechanical test: the mechanical test consists of three different drop tests:  
a) drop test I: the specimen shall drop onto the targe t 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 Point  17. 
b) drop test II: the specimen shall drop onto a bar rigidly m ounted 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, 1 5.0 ± 0.5  cm in diameter and 20  cm long, unless a longer bar would 
cause greater damage. Otherwise 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 shall meet 
the requirements of Point  17; 
c) drop test III: the specimen shall be subjected to a dynamic crush test by 
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 
1 m × 1  m solid mild steel plate 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 d rop shall be measured from 
the underside of the plate to the highest point of the specimen. The target shall 
meet the requirements of Point  17. 
Each specimen shall be subjected to the applicable drops, as specified in Point  59 
or 85 of Part  I. The order of  the drop tests shall be such that, on completion of the 
mechanical test, the specimen shall have suffer maximum damage in the thermal 
test that follows.  
 
28. Thermal test: the specimen shall be in thermal equilibrium under conditions of an 
ambient tempera ture of 38  °C, subject to insolation conditions specified in Table  1 
and subject to the design maximum rate of internal heat generation within the 
package from the radioactive contents. 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 specimen must be 
exposed to the following in the specified order:  
a) 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  - 30 - 
0.9 and an average temperature of at least 800  °C, fully engulfing the 
specimen, with a surfac e absorptivity coefficient of 0.8 or that value that the 
package may be demonstrated to possess if exposed to the fire specified;  
b) an ambient temperature of 38  °C, subject to insolation conditions specified in 
Table  1 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. 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. 
During and following the test, the specimen shall not be artificially cooled and 
any combustion of materia ls of the specimen shall be permitted to proceed 
naturally.  
 
29. Water immersion test: the specimen shall be immersed under at least 15  m of 
water for a period of not less than 8  h in the attitude that will lead to maximum 
damage. For demonstration purpose s, an external gauge pressure of at least 
150 kPa shall be considered to meet these conditions.  
 
II.5.8.  Enhanced water immersion test for Type  B(U) and Type  B(M) packages containing 
more than 105 A2 and for Type  C packages  
30. Water immersion test: the specimen s hall be immersed under at least 200  m of 
water 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.  
 
II.5.9.  Water immersion test for radioactive packages containi ng fissile material  
31. A package for which it has been assumed for purposes of assessment under 
Points  80 to 85 of Part  I that water leaks in and out to the extent that results in 
greatest reactivity shall be excepted from the test specified in Point  33. 
 
32. Before the specimen is subjected to the water leakage test specified in Point  33, it 
shall be subjected to the tests in Point  27(b) and Point  27(a), or 727(c) and 28.  
 
33. The specimen shall be immersed under at least 0.9  m of water for a period of no t 
less than 8  h in the attitude for which maximum leakage is expected.  
 
II.5.10.  Tests for type C packages  
34. Specimens shall be subjected to the following series of tests:  
a) as specified Points  27(a), 27(c), 35, and 36, in that order; and  
b) as specified in (37).  
Sepa rate specimens may be used for the series of tests in (a) and for the test in (b).  
 
35. 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 Point  34(a).  
a) A specimen representing a package having a mass of less than 250  kg, shall be 
placed on a target and subjecte d 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  - 31 - 
frustum of a right circular cone with the following dimen sions: 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 
Point  17. 
b) For a package having a mass of 250  kg or more, the base of the pro be 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 specimen is placed shall be as specified in Point  17. 
 
36. Enhanced thermal test: the conditions for this test shall be as specified in Point  28, 
except that the exposure to the thermal environment shall be for a period of 60 
min. 
 
37. 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 Point  17, except that the target surface may be at any 
orientation as long as the surface is normal to the specimen path.   - 32 - 
 
Annex  2 to Decree  No …………  
 
REQUIREMENTS FOR TYP E D AND S  PACKAGES  
 
1. Type D and S packaging:  
a) shall have mechanical ruggedness demonstrably enough with regard to 
designed manner of manipulation; and  
b) shall be manufactured from materials whose service life demonstrably 
corresponds to the designed service life of the packaging. Materials with a 
shorter service life may be used for packaging components if are readily 
replaceable during storage or repository operation.  
 
2. The contents of Type D or Type S packaging shall be sufficiently dried out and 
surrounded by a defined medium. The Office shall decide on the dryness criteria 
and parameters of this medium in the type approval decision when requested by 
the applicant.  
 
3. A Type D or S packaging shall be designed to comply with limits and conditions 
for the handling  of radioactive waste, including relevant acceptability criteria, 
approved by the Office.  
 
4. Type S packaging shall be manufactured:  
a) to meet the requirements specified in Points  6 to 11 and 13 to 16 of Part  I of 
Annex  1 to this decree, and other requireme nts stipulated by the Office in the 
type approval decision, taking into account manner of use;  
b) to ensure feasibility of checking package leak -tightness during storage;  
c) to preserve adequate shielding during normal operation, abnormal operation, 
design basis  accidents  and beyond design basis accidents that are not serious 
accidents. The shielding of the package shall ensure that the radiation level on 
the exterior does not exceed 10  mSv/h, even at the maximum design contents 
of radioactive content;  
d) so that th e heat generated inside the packaging by its radioactive contents does 
not under the normal conditions and at the ambient temperature of 38  °C have a 
negative effect on compliance with leak -tightness and shielding criteria if the 
packaging and its contents  are left unattended for seven days;  
e) to eliminate the influence of generated heat, the heat shall not:  
1. change the spacing, geometrical form or physical state of the 
radioactive contents, or if radionuclides are sealed within special 
capsule – cause deforma tion or melting of this capsule or its radioactive 
contents;  
2. reduce the efficiency of the packaging through differential thermal 
expansion, cracking, or melting of the shielding material;  
3. accelerate corrosion when combined with moisture; and  
4. cause the inte rruption of the residual heat removal; elimination of 
residual heat shall also be ensured also under beyond design basis 
accident conditions that are not serious accidents.   - 33 - 
 
Annex  3 to Decree  No …………  
 
ACTIVITY LIMITS AND CLASSIFICATION  
 
1. GENERAL REQUIREMEN TS 
 
1. A radioactive or fissile material is assigned one of the UN numbers listed in 
Table  1, in accordance with the requirements of Points  8 to 34.  
 
Table  1 Selected UN numbers, names and descriptions  
UN 
number  NAME a) and description  
Excepted packages  
UN 2908  RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - EMPTY PACKAGINGS  
UN 2909  RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - PRODUCTS OF NATURAL 
URANIUM or DEPLETED URANIUM or THORIUM  
UN 2910  RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - A LIMITED AMOUNT OF 
MATERIAL  
UN 2911  RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - DEVICES or PRODUCTS   
UN 3507  RADIOACTIVE MATERIAL, EXCEPTED PACKAGE – URANIUM HEXAFLUORIDE , 
less than 0.1  kg in a package, excepted fissile material or non -fissile material  
Materials with low specific activ ity 
UN 2912  RADIOACTIVE MATERIAL, MATERIAL WITH  LOW SPECIFIC ACTIVITY (LSA -I) 
excepted fissile material or non -fissile material  
UN 3321  RADIOACTIVE MATERIAL, MATERIAL WITH  LOW SPECIFIC ACTIVITY (LSA -II) 
excepted fissile material or non -fissile material  
UN 3322  RADIOACTIVE MATERIAL, MATERIAL WITH  LOW SPECIFIC ACTIVITY (LSA -III) 
excepted fissile material or non -fissile material  
UN 3324  RADIOACTIVE MATERIAL, MATERIAL WITH  LOW SPECIFIC ACTIVITY (LSA -II), 
FISSILE MATERIAL  
UN 3325  RADIOACTIVE MATERIAL, MATER IAL WITH  LOW SPECIFIC ACTIVITY (LSA -
III), FISSILE MATERIAL  
Surface contaminated objects  
UN 2913  RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO -I or SCO -
II), excepted fissile substance  or non-fissile substance  
UN 3326  RADIOACTIVE MATERIAL, SURFA CE CONTAMINATED OBJECTS (SCO -I or SCO -
II), FISSILE SUBSTANCE  
Type A packages  
UN 2915  RADIOACTIVE MATERIAL, TYPE A PACKAGE other than special form radioactive 
material, exceptions of fissile material  or non-fissile material  
UN 3327  RADIOACTIVE MATERIAL, TYPE A PACKAGE, FISSILE MATERIAL other than 
special form radioactive material  
UN 3332  RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM RADIOACTIVE 
MATERIAL, exceptions of fissile material  or non-fissile material  
UN 3333  RADIOACTIVE MATERIAL, TYPE A PAC KAGE, SPECIAL FORM RADIOACTIVE 
MATERIAL, FISSILE MATERIAL  
Type B(U) packages  
UN 2916  RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE  
exceptions of fissile material or non -fissile material  
UN 3328  RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, FISSILE MATERIAL   - 34 - 
Type B (M) packages  
UN 2917  RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE  
exceptions of fissile material or non -fissile material  
UN 3329  RADIOACTIVE MATERIAL, TYPE B(M) PACKAGE, FISSILE MATERIAL  
Type C packages  
UN 3323  RADIOACTIVE MATERIAL, TYPE C PACKAGE  
exception s of fissile material or non -fissile material  
UN 3330  RADIOACTIVE MATERIAL, TYPE C PACKAGE, FISSILE MATERIAL  
Transport under special arrangement  
UN 2919  RADIOACTIVE MATERIAL, TRANSPORT UNDER SPECIAL ARRANGEMENT  
excepted fissile material or non -fissile m aterial  
UN 3331  RADIOACTIVE MATERIAL, TRANSPORT UNDER SPECIAL ARRANGEMENT, 
FISSILE MATERIAL  
Uranium hexafluoride  
UN 2977  RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, FISSILE MATERIAL  
UN 2978  RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE  
excepted fissile ma terial or non -fissile material  
Legend:  
a) NAME can be found in the 'NAME and description' field and is limited to the part written in CAPITAL 
LETTERS. In Items  UN 2909, UN 2911, UN 2913, and UN 3326, only the appropriate NAME from alternative 
NAMES  separa ted by the conjunction 'or'.  
 
 
2. BASIC RADIONUCLIDE V ALUES  
 
2. Table  2 lists basic radionuclide values:  
a) A1 and A 2 in TBq;  
b) activity concentration limits for exceptions of material in Bq/g; and  
c) activity limits for exceptions of material in Bq.  
 
Table  2 Basic r adionuclide values  
Radionuclide (atomic number)  A1 
[TBq]  A2 
[TBq]  Activity 
concentrati
on limits 
for 
exceptions 
of material  
[Bq/g]  Activity 
limits for 
an 
exceptions 
of 
consignme
nt 
[Bq] 
Actinium (89)      
Ac-225a)  8x10-1 6x10-3 1x101 1x104 
Ac-227 (a)  9x10-1 9x10-5 1x10-1 1x103 
Ac-228 6x10-1 5x10-1 1x101 1x106 
Silver (47)      
Ag-105 2x100 2x100 1x102 1x106 
Ag-108m (a)  7x10-1 7x10-1 1x101(b) 1x106(b) 
Ag-110m (a)  4x10-1 4x10-1 1x101 1x106 
Ag-111 2x100 6x10-1 1x103 1x106 
Aluminium (13)      
Al-26 1x10-1 1x10-1 1x101 1x105  - 35 - 
Americium (95)      
Am-241 1x101 1x10-3 1x100 1x104 
Am-242m (a)  1x101 1x10-3 1x100(b) 1x104(b) 
Am-243 (a)  5x100 1x10-3 1x100(b) 1x103(b) 
Argon (18)      
Ar-37 4x101 4x101 1x106 1x108 
Ar-39 4x101 2x101 1x107 1x104 
Ar-41 3x10-1 3x10-1 1x102 1x109 
Arsenic (33)      
As-72 3x10-1 3x10-1 1x101 1x105 
As-73 4x101 4x101 1x103 1x107 
As-74 1x100 9x10-1 1x101 1x106 
As-76 3x10-1 3x10-1 1x102 1x105 
As-77 2x101 7x10-1 1x103 1x106 
Astatine (85)      
At-211 (a)  2x101 5x10-1 1x103 1x107 
Gold ( 79)     
Au-193 7x100 2x100 1x102 1x107 
Au-194 1x100 1x100 1x101 1x106 
Au-195 1x101 6x100 1x102 1x107 
Au-198 1x100 6x10-1 1x102 1x106 
Au-199 1x101 6x10-1 1x102 1x106 
Barium (56)      
Ba-131 (a)  2x100 2x100 1x102 1x106 
Ba-133 3x100 3x100 1x102 1x106 
Ba-133m  2x101 6x10-1 1x102 1x106 
Ba-140 (a)  5x10-1 3x10-1 1x101(b) 1x105(b) 
Beryllium (4)      
Be-7 2x101 2x101 1x103 1x107 
Be-10 4x101 6x10-1 1x104 1x106 
Bismuth (83)      
Bi-205 7x10-1 7x10-1 1x101 1x106 
Bi-206 3x10-1 3x10-1 1x101 1x105 
Bi-207 7x10-1 7x10-1 1x101 1x106 
Bi-210 1x100 6x10-1 1x103 1x106 
Bi-210m (a)  6x10-1 2x10-2 1x101 1x105 
Bi-212 (a)  7x10-1 6x10-1 1x101(b) 1x105(b) 
Berkelium (97)      
Bk-247 8x100 8x10-4 1x100 1x104 
Bk-249 (a)  4x101 3x10-1 1x103 1x106 
Bromine (35)      
Br-76 4x10-1 4x10-1 1x101 1x105 
Br-77 3x100 3x100 1x102 1x106 
Br-82 4x10-1 4x10-1 1x101 1x106 
Carbon (6)      
C-11 1x100 6x10-1 1x101 1x106 
C-14 4x101 3x100 1x104 1x107  - 36 - 
Calcium (20)      
Ca-41 Unlimited  Unlimited  1x105 1x107 
Ca-45 4x101 1x100 1x104 1x107 
Ca-47 (a)  3x100 3x10-1 1x101 1x106 
Cadmium (48)      
Cd-109 3x101 2x100 1x104 1x106 
Cd-113m  4x101 5x10-1 1x103 1x106 
Cd-115 (a)  3x100 4x10-1 1x102 1x106 
Cd-115m  5x10-1 5x10-1 1x103 1x106 
Cerium (58)      
Ce-139 7x100 2x100 1x102 1x106 
Ce-141 2x101 6x10-1 1x102 1x107 
Ce-143 9x10-1 6x10-1 1x102 1x106 
Ce-144 (a)  2x10-1 2x10-1 1x102(b) 1x105(b) 
Californium (98)      
Cf-248 4x101 6x10-3 1x101 1x104 
Cf-249 3x100 8x10-4 1x100 1x103 
Cf-250 2x101 2x10-3 1x101 1x104 
Cf-251 7x100 7x10-4 1x100 1x103 
Cf-252 1x10-1 3x10-3 1x101 1x104 
Cf-253 (a)  4x101 4x10-2 1x102 1x105 
Cf-254 1x10-3 1x10-3 1x100 1x103 
Chlorine (17)      
Cl-36 1x101 6x10-1 1x104 1x106 
Cl-38 2x10-1 2x10-1 1x101 1x105 
Curium (96)      
Cm-240 4x101 2x10-2 1x102 1x105 
Cm-241 2x100 1x100 1x102 1x106 
Cm-242 4x101 1x10-2 1x102 1x105 
Cm-243 9x100 1x10-3 1x100 1x104 
Cm-244 2x101 2x10-3 1x101 1x104 
Cm-245 9x100 9x10-4 1x100 1x103 
Cm-246 9x100 9x10-4 1x100 1x103 
Cm-247 (a)  3x100 1x10-3 1x100 1x104 
Cm-248 2x10-2 3x10-4 1x100 1x103 
Cobalt (27)      
Co-55 5x10-1 5x10-1 1x101 1x106 
Co-56 3x10-1 3x10-1 1x101 1x105 
Co-57 1x101 1x101 1x102 1x106 
Co-58 1x100 1x100 1x101 1x106 
Co-58m 4x101 4x101 1x104 1x107 
Co-60 4x10-1 4x10-1 1x101 1x105 
Chromium (24)      
Cr-51 3x101 3x101 1x103 1x107 
Caesium (5 5)     
Cs-129 4x100 4x100 1x102 1x105 
Cs-131 3x101 3x101 1x103 1x106  - 37 - 
Cs-132 1x100 1x100 1x101 1x105 
Cs-134 7x10-1 7x10-1 1x101 1x104 
Cs-134m  4x101 6x10-1 1x103 1x105 
Cs-135 4x101 1x100 1x104 1x107 
Cs-136 5x10-1 5x10-1 1x101 1x105 
Cs-137 (a)  2x100 6x10-1 1x101(b) 1x104(b) 
Copper (29)      
Cu-64 6x100 1x100 1x102 1x106 
Cu-67 1x101 7x10-1 1x102 1x106 
Dysprosium (66)      
Dy-159 2x101 2x101 1x103 1x107 
Dy-165 9x10-1 6x10-1 1x103 1x106 
Dy-166 (a)  9x10-1 3x10-1 1x103 1x106 
Erbium (68)      
Er-169 4x101 1x100 1x104 1x107 
Er-171 8x10-1 5x10-1 1x102 1x106 
Europium (63)      
Eu-147 2x100 2x100 1x102 1x106 
Eu-148 5x10-1 5x10-1 1x101 1x106 
Eu-149 2x101 2x101 1x102 1x107 
Eu-150 (with short half -life) 2x100 7x10-1 1x103 1x106 
Eu-150 (with long half -life) 7x10-1 7x10-1 1x101 1x106 
Eu-152 1x100 1x100 1x101 1x106 
Eu-152m  8x10-1 8x10-1 1x102 1x106 
Eu-154 9x10-1 6x10-1 1x101 1x106 
Eu-155 2x101 3x100 1x102 1x107 
Eu-156 7x10-1 7x10-1 1x101 1x106 
Fluorine (9)      
F-18 1x100 6x10-1 1x101 1x106 
Iron (26)      
Fe-52 (a)  3x10-1 3x10-1 1x101 1x106 
Fe-55 4x101 4x101 1x104 1x106 
Fe-59 9x10-1 9x10-1 1x101 1x106 
Fe-60 (a)  4x101 2x10-1 1x102 1x105 
Gallium (31)      
Ga-67 7x100 3x100 1x102 1x106 
Ga-68 5x10-1 5x10-1 1x101 1x105 
Ga-72 4x10-1 4x10-1 1x101 1x105 
Gadolinium (64)      
Gd-146 (a)  5x10-1 5x10-1 1x101 1x106 
Gd-148 2x101 2x10-3 1x101 1x104 
Gd-153 1x101 9x100 1x102 1x107 
Gd-159 3x100 6x10-1 1x103 1x106 
Germanium (32)      
Ge-68 (a)  5x10-1 5x10-1 1x101 1x105 
Ge-71 4x101 4x101 1x104 1x108 
Ge-77 3x10-1 3x10-1 1x101 1x105  - 38 - 
Hafnium (72)      
Hf-172 (a)  6x10-1 6x10-1 1x101 1x106 
Hf-175 3x100 3x100 1x102 1x106 
Hf-181 2x100 5x10-1 1x101 1x106 
Hf-182 Unlimited  Unlimited  1x102 1x106 
Mercury (80)      
Hg-194 (a)  1x100 1x100 1x101 1x106 
Hg-195m (a)  3x100 7x10-1 1x102 1x106 
Hg-197 2x101 1x101 1x102 1x107 
Hg-197m  1x101 4x10-1 1x102 1x106 
Hg-203 5x100 1x100 1x102 1x105 
Holmium (67)      
Ho-166 4x10-1 4x10-1 1x103 1x105 
Ho-l66m  6x10-1 5x10-1 1x101 1x106 
Iodine (53)      
I-123 6x100 3x100 1x102 1x107 
I-124 1x100 1x100 1x101 1x106 
I-125 2x101 3x100 1x103 1x106 
I-126 2x100 1x100 1x102 1x106 
I-129 Unlimited  Unlimited  1x102 1x105 
I-131  3x100 7x10-1 1x102 1x106 
I-132 4x10-1 4x10-1 1x101 1x105 
I-133 7x10-1 6x10-1 1x101 1x106 
I-134 3x10-1 3x10-1 1x101 1x105 
I-135 (a)  6x10-1 6x10-1 1x101 1x106 
Indium (49)      
In-111 3x100 3x100 1x102 1x106 
In-113m  4x100 2x100 1x102 1x106 
In-114m (a)  1x101 5x10-1 1x102 1x106 
In-115m  7x100 1x100 1x102 1x106 
Iridium (77)      
Ir-189 (a)  1x101 1x101 1x102 1x107 
Ir-190 7x10-1 7x10-1 1x101 1x106 
Ir-192 1x100(c) 6x10-1 1x101 1x104 
Ir-194 3x10-1 3x10-1 1x102 1x105 
Potassium (19)      
K-40 9x10-1 9x10-1 1x102 1x106 
K-42 2x10-1 2x10-1 1x102 1x106 
K-43 7x10-1 6x10-1 1x101 1x106 
Krypton (36)      
Kr-79 4x101 2x100 1x103 1x105 
Kr-81 4x101 4x101 1x104 1x107 
Kr-85 1x101 1x101 1x105 1x104 
Kr-85m 8x100 3x100 1x103 1x1010 
Kr-87 2x10-1 2x10-1 1x102 1x109 
Lanthanum (57)      
La-137 3x101 6x100 1x103 1x107  - 39 - 
La-140 4x10-1 4x10-1 1x101 1x105 
Lutetium (71)      
Lu-172 6x10-1 6x10-1 1x101 1x106 
Lu-173 8x100 8x100 1x102 1x107 
Lu-174 9x100 9x100 1x102 1x107 
Lu-174m  2x101 1x101 1x102 1x107 
Lu-177 3x101 7x10-1 1x103 1x107 
Magnesium (12)      
Mg-28 (a)  3x10-1 3x10-1 1x101 1x105 
Manganese (25)      
Mn-52 3x10-1 3x10-1 1x101 1x105 
Mn-53 Unlimited  Unlimited  1x104 1x109 
Mn-54 1x100 1x100 1x101 1x106 
Mn-56 3x10-1 3x10-1 1x101 1x105 
Molybdenum (42)      
Mo-93 4x101 2x101 1x103 1x108 
Mo-99 (a)  1x100 6x10-1 1x102 1x106 
Nitrogen (7)      
N-13 9x10-1 6x10-1 1x102 1x109 
Sodium (11)      
Na-22 5x10-1 5x10-1 1x101 1x106 
Na-24 2x10-1 2x10-1 1x101 1x105 
Niobium (41)      
Nb-93m 4x101 3x101 1x104 1x107 
Nb-94 7x10-1 7x10-1 1x101 1x106 
Nb-95 1x100 1x100 1x101 1x106 
Nb-97 9x10-1 6x10-1 1x101 1x106 
Neodymium (60)      
Nd-147 6x100 6x10-1 1x102 1x106 
Nd-149 6x10-1 5x10-1 1x102 1x106 
Nickel (28)      
Ni-59 Unlimited  Unlimited  1x104 1x108 
Ni-63 4x101 3x101 1x105 1x108 
Ni-65 4x10-1 4x10-1 1x101 1x106 
Neptunium (93)      
Np-235 4x101 4x101 1x103 1x107 
Np-236 (with short half -life) 2x101 2x100 1x103 1x107 
Np-236 (with long half -life) 9x100 2x10-2 1x102 1x105 
Np-237 2x101 2x10-3 1x100(b) 1x103(b) 
Np-239 7x100 4x10-1 1x102 1x107 
Osmium (76)      
Os-185 1x100 1x100 1x101 1x106 
Os-191 1x101 2x100 1x102 1x107 
Os-191m  4x101 3x101 1x103 1x107 
Os-193 2x100 6x10-1 1x102 1x106 
Os-194 (a)  3x10-1 3x10-1 1x102 1x105 
Phosphorus (15)       - 40 - 
P-32 5x10-1 5x10-1 1x103 1x105 
P-33 4x101 1x100 1x105 1x108 
Protactinium (91)      
Pa-230 (a)  2x100 7x10-2 1x101 1x106 
Pa-231 4x100 4x10-4 1x100 1x103 
Pa-233 5x100 7x10-1 1x102 1x107 
Lead (82)      
Pb-201 1x100 1x100 1x101 1x106 
Pb-202 4x101 2x101 1x103 1x106 
Pb-203 4x100 3x100 1x102 1x106 
Pb-205 Unlimited  Unlimited  1x104 1x107 
Pb-210 (a)  1x100 5x10-2 1x101(b) 1x104(b) 
Pb-212 (a)  7x10-1 2x10-1 1x101(b) 1x105(b) 
Palladium (46)      
Pd-103 (a)  4x101 4x101 1x103 1x108 
Pd-107 Unlimited  Unlimited  1x105 1x108 
Pd-109 2x100 5x10-1 1x103 1x106 
Promethium (61)      
Pm-143 3x100 3x100 1x102 1x106 
Pm-144 7x10-1 7x10-1 1x101 1x106 
Pm-145 3x101 1x101 1x103 1x107 
Pm-147 4x101 2x100 1x104 1x107 
Pm-148m (a)  8x10-1 7x10-1 1x101 1x106 
Pm-149 2x100 6x10-1 1x103 1x106 
Pm-151 2x100 6x10-1 1x102 1x106 
Polonium (84)      
Po-210 4x101 2x10-2 1x101 1x104 
Praseodymium (59)      
Pr-142 4x10-1 4x10-1 1x102 1x105 
Pr-143 3x100 6x10-1 1x104 1x106 
Platinum (78)      
Pt-188 (a)  1x100 8x10-1 1x101 1x106 
Pt-191 4x100 3x100 1x102 1x106 
Pt-193 4x101 4x101 1x104 1x107 
Pt-193m  4x101 5x10-1 1x103 1x107 
Pt-195m  1x101 5x10-1 1x102 1x106 
Pt-197 2x101 6x10-1 1x103 1x106 
Pt-197m  1x101 6x10-1 1x102 1x106 
Plutonium (94)      
Pu-236 3x101 3x10-3 1x101 1x104 
Pu-237 2x101 2x101 1x103 1x107 
Pu-238 1x101 1x10-3 1x100 1x104 
Pu-239 1x101 1x10-3 1x100 1x104 
Pu-240 1x101 1x10-3 1x100 1x103 
Pu-241 (a)  4x101 6x10-2 1x102 1x105 
Pu-242 1x101 1x10-3 1x100 1x104 
Pu-244 (a)  4x10-1 1x10-3 1x100 1x104  - 41 - 
Radium (88)      
Ra-223 (a)  4x10-1 7x10-3 1x102(b) 1x105(b) 
Ra-224 (a)  4x10-1 2x10-2 1x101(b) 1x105(b) 
Ra-225 (a)  2x10-1 4x10-3 1x102 1x105 
Ra-226 (a)  2x10-1 3x10-3 1x101(b) 1x104(b) 
Ra-228 (a ) 6x10-1 2x10-2 1x101(b) 1x105(b) 
Rubidium (37)      
Rb-81 2x100 8x10-1 1x101 1x106 
Rb-83 (a)  2x100 2x100 1x102 1x106 
Rb-84 1x100 1x100 1x101 1x106 
Rb-86 5x10-1 5x10-1 1x102 1x105 
Rb-87 Unlimited  Unlimited  1x104 1x107 
Rb (natural)  Unlimited  Unlimited  1x104 1x107 
Rhenium (75)      
Re-184 1x100 1x100 1x101 1x106 
Re-184m  3x100 1x100 1x102 1x106 
Re-186 2x100 6x10-1 1x103 1x106 
Re-187 Unlimited  Unlimited  1x106 1x109 
Re-188 4x10-1 4x10-1 1x102 1x105 
Re-189(a)  3x100 6x10-1 1x102 1x106 
Re (natural)  Unlimited  Unlimited  1x106 1x109 
Rhodium (45)      
Rh-99 2x100 2x100 1x101 1x106 
Rh-101 4x100 3x100 1x102 1x107 
Rh-102 5x10-1 5x10-1 1x101 1x106 
Rh-102m  2x100 2x100 1x102 1x106 
Rh-103m  4x101 4x101 1x104 1x108 
Rh-105 1x101 8x10-1 1x102 1x107 
Radon (86)      
Rn-222 (a)  3x10-1 4x10-3 1x101(b) 1x108(b) 
Ruthenium (44)      
Ru-97 5x100 5x100 1x102 1x107 
Ru-103 (a)  2x100 2x100 1x102 1x106 
Ru-105 1x100 6x10-1 1x101 1x106 
Ru-106 (a)  2x10-1 2x10-1 1x102(b) 1x105(b) 
Sulfur (16)     
S-35 4x101 3x100 1x105 1x108 
Antimony (51)      
Sb-122 4x10-1 4x10-1 1x102 1x104 
Sb-124 6x10-1 6x10-1 1x101 1x106 
Sb-125 2x100 1x100 1x102 1x106 
Sb-126 4x10-1 4x10-1 1x101 1x105 
Scandium (21)      
Sc-44 5x10-1 5x10-1 1x101 1x105 
Sc-46 5x10-1 5x10-1 1x101 1x106 
Sc-47 1x101 7x10-1 1x102 1x106 
Sc-48 3x10-1 3x10-1 1x101 1x105  - 42 - 
Selenium (34)      
Se-75 3x100 3x100 1x102 1x106 
Se-79 4x101 2x100 1x104 1x107 
Silicon (14)      
Si-31 6x10-1 6x10-1 1x103 1x106 
Si-32 4x101 5x10-1 1x103 1x106 
Samarium (62)      
Sm-145 1x101 1x101 1x102 1x107 
Sm-147 Unlimited  Unlimited  1x101 1x104 
Sm-151 4x101 1x101 1x104 1x108 
Sm-153 9x100 6x10-1 1x102 1x106 
Tin (50)      
Sn-113 (a)  4x100 2x100 1x103 1x107 
Sn-117m  7x100 4x10-1 1x102 1x106 
Sn-119m  4x101 3x101 1x103 1x107 
Sn-121m (a)  4x101 9x10-1 1x103 1x107 
Sn-123 8x10-1 6x10-1 1x103 1x106 
Sn-125 4x10-1 4x10-1 1x102 1x105 
Sn-126 (a)  6x10-1 4x10-1 1x101 1x105 
Strontium (38)      
Sr-82 (a)  2x10-1 2x10-1 1x101 1x105 
Sr-85 2x100 2x100 1x102 1x106 
Sr-85m 5x100 5x100 1x102 1x107 
Sr-87m 3x100 3x100 1x102 1x106 
Sr-89 6x10-1 6x10-1 1x103 1x106 
Sr-90 (a)  3x10-1 3x10-1 1x102(b) 1x104(b) 
Sr-91 (a)  3x10-1 3x10-1 1x101 1x105 
Sr-92 (a)  1x100 3x10-1 1x101 1x106 
Tritium (1)      
T(H-3) 4x101 4x101 1x106 1x109 
Tantalum (73)      
Ta-178 (with long half -life) 1x100 8x10-1 1x101 1x106 
Ta-179 3x101 3x101 1x103 1x107 
Ta-182 9x10-1 5x10-1 1x101 1x104 
Terbium (65)      
Tb-157 4x101 4x101 1x104 1x107 
Tb-158 1x100 1x100 1x101 1x106 
Tb-160 1x100 6x10-1 1x101 1x106 
Technetium (43)      
Tc-95m (a)  2x100 2x100 1x101 1x106 
Tc-96 4x10-1 4x10-1 1x101 1x106 
Tc-96m (a)  4x10-1 4x10-1 1x103 1x107 
Tc-97 Unlimited  Unlimited  1x103 1x108 
Tc-97m 4x101 1x100 1x103 1x107 
Tc-98 8x10-1 7x10-1 1x101 1x106 
Tc-99 4x101 9x10-1 1x104 1x107 
Tc-99m 1x101 4x100 1x102 1x107  - 43 - 
Tellurium (52)      
Te-121 2x100 2x100 1x101 1x106 
Te-121m  5x100 3x100 1x102 1x106 
Te-123m  8x100 1x100 1x102 1x107 
Te-125m  2x101 9x10-1 1x103 1x107 
Te-127 2x101 7x10-1 1x103 1x106 
Te-127m (a)  2x101 5x10-1 1x103 1x107 
Te-129 7x10-1 6x10-1 1x102 1x106 
Te-129m (a)  8x10-1 4x10-1 1x103 1x106 
Te-131m (a)  7x10-1 5x10-1 1x101 1x106 
Te-132 (a)  5x10-1 4x10-1 1x102 1x107 
Thorium (90)      
Th-227 1x101 5x10-3 1x101 1x104 
Th-228 (a)  5x10-1 1x10-3 1x100(b) 1x104(b) 
Th-229 5x100 5x10-4 1x100(b) 1x103(b) 
Th-230 1x101 1x10-3 1x100 1x104 
Th-231 4x101 2x10-2 1x103 1x107 
Th-232 Unlimited  Unlimited  1x101 1x104 
Th-234 (a)  3x10-1 3x10-1 1x103(b) 1x105(b) 
Th (natural)  Unlimited  Unlimited  1x100(b) 1x103(b) 
Titanium (22)      
Ti-44 (a)  5x10-1 4x10-1 1x101 1x105 
Thalliu m (81)      
Tl-200 9x10-1 9x10-1 1x101 1x106 
Tl-201 1x101 4x100 1x102 1x106 
Tl-202 2x100 2x100 1x102 1x106 
Tl-204 1x101 7x10-1 1x104 1x104 
Thulium (69)      
Tm-167 7x100 8x10-1 1x102 1x106 
Tm-170 3x100 6x10-1 1x103 1x106 
Tm-171 4x101 4x101 1x104 1x108 
Uranium (92)      
U-230 (rapid lung retention) (a)(d)  4x101 1x10-1 1x101(b) 1x105(b) 
U-230 (medium lung retention) (a)(e)  4x101 4x10-3 1x101 1x104 
U-230 (slow lung retention) (a)(f)  3x101 3x10-3 1x101 1x104 
U-232 (rapid lung retention) (d)  4x101 1x10-2 1x100(b) 1x103(b) 
U-232 (medium lung retention) (e)  4x101 7x10-3 1x101 1x104 
U-232 (slow lung retention) (f)  1x101 1x10-3 1x101 1x104 
U-233 (rapid lung retention) (d)  4x101 9x10-2 1x101 1x104 
U-233 (medium lung retention) (e)  4x101 2x10-2 1x102 1x105 
U-233 (slow lung retention) (f)  4x101 6x10-3 1x101 1x105 
U-234 (rapid lung retention) (d)  4x101 9x10-2 1x101 1x104 
U-234 (medium lung retention) (e)  4x101 2x10-2 1x102 1x105 
U-234 (slow lung retention) (f)  4x101 6x10-3 1x101 1x105 
U-235 (all types of lung retention) 
(a)(d)(e)(f)  Unlimited  Unlimited  1x101(b) 1x104(b) 
U-236 (quick retention) (d)  Unlimited  Unlimited  1x101 1x104  - 44 - 
U-236 (medium retention rate) (e)  4x101 2x10-2 1x102 1x105 
U-236 (slow retention) (f)  4x101 6x10-3 1x101 1x104 
U-238 (all types of lung retention) 
(d)(e)(f)  Unlimited  Unlimited  1x101(b) 1x104(b) 
U (natural)  Unlimited  Unlimited  1x100(b) 1x103(b) 
U (enriched up to 20 % or less) (g)  Unlimited  Unlimited  1x100 1x103 
U (depleted)  Unlimited  Unlimited  1x100 1x103 
Vanadium (23)      
V-48 4x10-1 4x10-1 1x101 1x105 
V-49 4x101 4x101 1x104 1x107 
Wolfram (74)      
W-178 (a)  9x100 5x100 1x101 1x106 
W-181 3x101 3x101 1x103 1x107 
W-185 4x101 8x10-1 1x104 1x107 
W-187 2x100 6x10-1 1x102 1x106 
W-188 (a)  4x10-1 3x10-1 1x102 1x105 
Xenon (54)     
Xe-122 (a)  4x10-1 4x10-1 1x102 1x109 
Xe-123 2x100 7x10-1 1x102 1x109 
Xe-127 4x100 2x100 1x103 1x105 
Xe-131m  4x101 4x101 1x104 1x104 
Xe-133 2x101 1x101 1x103 1x104 
Xe-135 3x100 2x100 1x103 1x1010 
Yttrium (39)      
Y-87 (a)  1x100 1x100 1x101 1x106 
Y-88 4x10-1 4x10-1 1x101 1x106 
Y-90 3x10-1 3x10-1 1x103 1x105 
Y-91 6x10-1 6x10-1 1x103 1x106 
Y-91m 2x100 2x100 1x102 1x106 
Y-92 2x10-1 2x10-1 1x102 1x105 
Y-93 3x10-1 3x10-1 1x102 1x105 
Ytterbium (70)      
Yb-169 4x100 1x100 1x102 1x107 
Yb-175 3x101 9x10-1 1x103 1x107 
Zinc (30)      
Zn-65 2x100 2x100 1x101 1x106 
Zn-69 3x100 6x10-1 1x104 1x106 
Zn-69m (a)  3x100 6x10-1 1x102 1x106 
Zirconium (40)      
Zr-88 3x100 3x100 1x102 1x106 
Zr-93 Unlimited  Unlimited  1x103(b) 1x107(b) 
Zr-95 (a)  2x100 8x10-1 1x101 1x106 
Zr-97 (a)  4x10-1 4x10-1 1x101(b) 1x105(b) 
Legend:  
(a) For the listed parent radionuclides, the values A 1 and A 2 include contributions from radioactive decay 
products with a decay half -life of less than 10 days:  
Mg-28 Al-28 
Ar-42 K-42 
Ca-47 Sc-47  - 45 - 
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 
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  - 46 - 
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 
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 radionuclides and products of their radioactive decay corresponding to perma nent equilibrium:  
Sr-90 Y-90 
Zr93  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-201, 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, Pb212, Bi -212, Tl2 08 (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, R a-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 
(c) Activity may be determined from a measurement of the rate of decay or a measurement of the radiation level 
at a prescribed distance from the radionuclide source of ionising radiation.  
(d) These values apply only to uranium compounds UF 6, U 2F2 and UO 2(NO 3)2 in both normal and accident 
conditions of transport.  
(d) These values apply only to uranium compounds UO 3, UF 4, UCl 4 and hexavalent uranium compounds in both 
normal and accident conditions of transport.  
(f) These values apply to all compounds of ur anium other than those specified in (d) and (e).  
(g) These values apply to unirradiated uranium only.  
 
 
3. DETERMINATION OF BAS IC RADIONUCLIDE VALU ES 
 
3. 1. For a radionuclide not listed in Table  2, specific activity limits for material 
exception and activity  limits for package exception shall be calculated in 
accordance with principles and methods stipulated in Annex  6 to this decree, or  - 47 - 
values in Table  3 shall be used. The value of A 2 may also be calculated using the 
dose coefficient for the relevant lung ab sorption type, according to International 
Atomic Energy Agency recommendations, where the calculation shall take into 
account the chemical form of each radionuclide under normal conditions of 
transport and under accident conditions of transport.  
 
2. For a radionuclide enclosed or contained in an instrument or product that meets 
the requirements of Point  23(c), an alternative basic value may be used to the 
basic value for the specific activity limit for material exception listed in Table  2. 
This alternative value shall be calculated in accordance with procedures and 
methods described in Annex  6 to this decree.  
 
4. In the calculations of A 1 a A 2 for a radionuclide not in Table  2: 
a) 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 A 1 and A 2 values to be applied shall be those corresponding to the 
parent nuclide of that chain; or  
b) a radioactive decay chain in which any daughter nuclide has a half -life either 
longer than 10 days or greater than that of the parent nuclide, the parent and 
such da ughter nuclides shall be considered as mixtures of different nuclides.  
 
5. For mixtures of radionuclides for which basic radionuclide values are provided in 
Table  2, basic values shall be determined using the formula:  
Xm = 1 / Σ[f(i)/X(i)],  
 I 
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 1 or A 2 or the activity concentration for exempt 
material or the activity limit for an exempt consignment  for the relevant 
radionuclide i; and  
Xm is the basic value derived for a mixture from A 1 or A 2, or the activity 
concentration for exempt material or the activity limit for an exempt consignment.  
 
6. 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 
according to the type of emitted radiation (alpha, beta, or gamma) with known 
overall activities for the given group, and calculations may be performed 
accor ding to formula s in Points  5 and 30 using appropriate lowest radionuclide 
values from A 1, A 2,, specific activity limits for exempt material, or activity limits 
for the exempt consignment in each group. For groups based on total alpha 
activity, the lowest r adionuclide values for alpha emitters in the given group shall 
be used. For groups based on the total beta or gamma activity, the lowest 
radionuclide values for radionuclide sources emitting beta or gamma radiation 
(hereinafter an “beta or gamma emitter ”) in the given group shall be used.  
 
7. For radionuclides or for mixtures of radionuclides for which relevant data for the  - 48 - 
use of Table  2 is not available, the values shown in Table  3 shall be used.  
 
Table  3 Basic radionuclide values for unknown radionuclide s or mixtures  
 
Radioactive contents  A1 A2 Activity 
concentratio
n limits for 
exception of 
material  Activity limits 
for an exempt 
consignment  
 [TBq]  [TBq]  [Bq/g]  [Bq] 
Only beta or gamma emitters are known to be 
present  0.1 0.02 1x101 1x104 
Alpha emitters are known to be present, but 
radionuclide sources emitting neutrons are 
not known to be present  0.2 9x10-5 1x10-1 1x103 
Radionuclide sources emitting neutrons are 
known to be present or no relevant data are 
available  0.001  9x10-5 1x10-1 1x103 
 
 
4. MATERIA L CLASSIFICATION  
 
4.1. Materials with low specific activity  
8. A radioactive or fissile material is classified as material with low specific activity 
if 
a) it conforms to the definition in §  2(j); 
b) it meets the requirements of Points  9 to 11; and  
c) it meets relevant requirements of Points  17 to 22 of Annex  4 to this decree.  
 
9. 1. A material with low specific activity is classified in group LSA -I, LSA -II, or 
LSA -III. 
 
2. Group LSA -I includes:  
a) uranium and thorium ores, their concentrates, and other ores containing 
naturally occurring radionuclides;  
b) natural or depleted uranium, natural thorium  or their compounds or mixtures, 
which have not been irradiated and are in solid or liquid form;  
c) a radioactive material for which A 2 is unlimited; of fissile material, only an 
exemp t fissile material may be included; and  
d) other radioactive material in which activity is uniformly distributed throughout 
their volume, and the calculated mean specific activity does not exceed 30 
times the specific activity limit for material exemption sti pulated pursuant to 
Points  2 and 7, where external shielding materials surrounding the LSA 
material are not taken into account in determining the mean specific activity; of 
fissile material, only an exempt fissile material may be included.  
 
3. Group LSA -II includes:  
a) water with tritium with concentration up to 0.8  TBq/l; and  
b) other materials in which activity is uniformly distributed throughout their 
volume, and the calculated mean specific activity does not exceed 10-4 A2/g for  - 49 - 
solids and gases and 10-5 A2/g for liquids, where external shielding materials 
surrounding the LSA material are not taken into account in determining the 
mean specific activity.  
 
4. Group LSA -III includes solids, except for powdered materials, that meet the 
requirements of Point  1 of P art I of Annex  1 to this decree, and in which:  
a) the radioactive or fissile material is uniformly distributed throughout the 
volume of the solid material or in an array of several solid objects, or is 
relatively uniformly distributed in a compact bonding age nt; 
b) the radioactive or fissile material is relatively insoluble or is contained in a 
relatively insoluble matrix in such a manner that even in the event of loss of 
packaging, the loss of radioactive or fissile material from one package through 
leaching in water for 7 days does not exceed 0.1 A 2; and  
c) the calculated mean specific activity of solid material without shielding does 
not exceed 2.10-3 A2/g, where external shielding materials surrounding the LSA 
material are not taken into account in determining th e mean specific activity.  
 
10. A package with non -flammable solid material of group LSA -II or LSA -III must 
not contain activity greater than 3  000 A2 when being transported by air.  
 
11. The radioactive contents in a single package of LSA material shall be so restricted 
that the radiation level specified in Point  17 of Annex  4 to this decree shall not be 
exceeded, and the activity in a single package shall be so restricted that the 
activity limits for a conveyance specified in Point  22 of Annex  4 to this dec ree 
shall not be exceeded.  
 
4.2. Surface contaminated object  
12. A radioactive or fissile material is classified as a surface contaminated object 
(SCO) if:  
a) it conforms to the definition in §  2(m);  
b) it meets the requirements of Points  13 and 14; and  
c) it meets rele vant requirements of Points  17 to 22 of Annex  4 to this decree.  
 
13. 1. A surface contaminated object is classified in group SCO -I or SCO -II. 
 
2. Group SCO -I includes a solid object for which:  
a) non-fixed contamination on the accessible surface averaged over  300 cm2 (or 
the entire surface if less than 300  cm2) does not exceed:  
1. 4 Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters;  
2. or 0.4  Bq/cm2 for all other alpha emitters;  
b) fixed contamination on the accessible surface averaged over 300  cm2 (or the 
entire surface if less than 300 cm2) does not exceed:  
1. 4.104 Bq/cm2 for beta and gamma emitters and low toxicity alpha 
emitters, or  
2. 4.103 Bq/cm2 for all other alpha emitters; and  
c) the sum of fixed and non -fixed contamination on the accessible surface 
averaged over 300  cm2 (or the entire surface if less than 300  cm2) does not 
exceed:  
1. 4.104 Bq/cm2 for beta and gamma emitters and low toxicity alpha 
emitters, or   - 50 - 
2. 4.103 Bq/cm2 for all other alpha emitters.  
 
3. Group SCO -II includes a solid object on which eith er the fixed or non -fixed 
contamination on the surface exceeds the applicable limits specified in (2) and for 
which:  
a) non-fixed contamination on the accessible surface averaged over 300  cm2 (or 
the entire surface if less than 300  cm2) does not exceed:  
1. 400 Bq/cm2 for beta and gamma emitters and low toxicity alpha 
emitters;  
2. 40 Bq/cm2 for all other alpha emitters;  
b) fixed contamination on the accessible surface averaged over 300  cm2 (or the 
entire surface if less than 300  cm2) does not exceed:  
1. 8.105 Bq/cm2 for be ta and gamma emitters and low toxicity alpha 
emitters, or  
2. 8.104 Bq/cm2 for all other alpha emitters; and  
c) the sum of fixed and non -fixed contamination on the accessible surface 
averaged over 300  cm2 (or the entire surface if less than 300  cm2) does not 
exceed: 
1. 8.105 Bq/cm2 for beta and gamma emitters and low toxicity alpha 
emitters, or  
2. 8.104 Bq/cm2 for all other alpha emitters.  
 
14. The radioactive contents in a package with an SCO shall be so restricted that the 
radiation level specified in Point  17 of Anne x 4 to this decree shall not be 
exceeded, and the activity in a single package shall be so restricted that the 
activity limits for a conveyance specified in Point  22 of Annex  4 to this decree 
shall not be exceeded.  
 
4.3. Special form radioactive material  
15. A radioactive or fissile material is classified as a special form radioactive material 
if: 
a) it meets the requirements of Points  2 to 4 of Part  I of Annex  1 to this decree, 
and 
b) it is type -approved as a special form radioactive material pursuant to 
§ 137(1)(b) of the Atomic Act.  
 
4.4. Low dispersible radioactive material  
16. A radioactive or fissile material is classified as a slow dispersible radioactive 
material if:  
a) it meets the requirements of Point  5 of Part  I of Annex  1 to this decree;  
b) it is type -approved as a l ow dispersible radioactive material pursuant to 
§ 137(1)(c) of the Atomic Act; and  
c) the package containing it meets the requirements of Point  65 of Part  I of 
Annex  1 to this decree.  
 
4.5. Fissile material  
17. Fissile material and a package containing fissile mat erial shall be classified as 
FISSILE MATERIAL  under the relevant entry in Table  1. Assuming that they are 
transported in packages that meet the requirements of Point  36 of Part  I of 
Annex  1 to this decree, and pursuant to the requirements of Point  70 of An nex 4  - 51 - 
to this decree, the following are exempt from the above requirement:  
a) uranium enriched with 235U to a maximum of 1  % by mass, and with a total 
plutonium and 233U content not exceeding 1  % of the mass of 235U provided 
that the fissile nuclides are dist ributed essentially homogeneously throughout 
the material. If 235U is present in metallic, oxide or carbide forms, it shall not 
form a lattice arrangement.  
b) liquid solutions of uranyl nitrate enriched with 235U to a maximum of 2  % by 
mass, with a total plut onium and 233U content not exceeding 0.002  % of the 
mass of uranium, and with a minimum nitrogen to uranium atomic ratio (N/U) 
of 2; 
c) uranium enriched with 235U to a maximum of 5  % by mass, assuming:  
1. the mass of 235U is no greater than 3.5  g per package;  
2. total plutonium and 233U content does not exceed 1  % of the mass of 235U per 
package; and  
3. transport of the package is restricted by limits for a consignment specified in 
Point  70(c) of Annex  4 to this decree;  
d) fissile radionuclides with total mass not exceedi ng 2 g per package, assuming 
that transport of the package is restricted by limits for a consignment specified 
in Point  70(d) of Annex  4 to this decree;  
e) fissile radionuclides with a total mass not exceeding 45  g in packaging or 
unpackaged, assuming that tr ansport is restricted by limits for a consignment 
specified in Point  70(e) of Annex  4 to this decree; and  
f) fissile materials that meet the requirements of Point  70(b) of Annex  4 to this 
decree and Point  6 of Part  I of Annex  1 to this decree;  
if they are tra nsported, except for unpackaged fissile radionuclides pursuant to (e), 
in a package whose smallest external overall dimension is greater than or equal to 
10 cm. 
 
18. The contents of a package containing fissile material must meet the requirements 
stipulate d for package design by this decree or a type approval decision.  
 
4.6. Uranium hexafluoride  
19. Uranium hexafluoride is classified under one of the following UN numbers:   
a) UN 2977, RADIOACTIVE MATERIAL, URANIUM HEXAFLUORIDE, 
FISSILE MATERIAL;  
b) UN 2978, RADIOACTIV E MATERIAL, URANIUM HEXAFLUORIDE, 
exempt fissile material or non -fissile material;  
c) UN 3507  URANIUM HEXAFLUORIDE , RADIOACTIVE MATERIAL, 
PACKAGE EXCEPTIONS – less than 0.1  kg in package, exempt fissile 
material or non -fissile material.  
 
20. Packages containi ng uranium hexafluoride shall comply with the following:  
a) the mass of uranium hexafluoride shall correspond to this permitted mass for 
the given package type;  
b) the mass of uranium hexafluoride shall not be greater than a value that would 
lead to an ullage sm aller than 5  % at the maximum temperature of the package 
as specified for facilities where the package shall be used; and  
c) the uranium hexafluoride shall be in solid form and the internal pressure shall 
not be greater than atmospheric pressure when handed o ver for carriage.  
  - 52 - 
 
5. CLASSIFICATION OF PA CKAGES  
 
21. The quantity of radioactive or fissile material in a package shall not exceed the 
relevant limits for the given package type in Points  22 to 33.  
 
5.1. Classification as a package exception  
22. A packages is cl assified as a package exception if:  
a) it is an empty package that had contained radioactive material;  
b) it contains an instrument or product whose activity does not exceed limits 
specified in Table  4; 
c) it contains a product manufactured from natural uranium, de pleted uranium, or 
natural thorium;  
d) it contains a radioactive material whose activity does not exceed the limits 
specified in Table  4; or  
e) it contains less than 0.1  kg of uranium hexafluoride, whose activity does not 
exceed the limits specified in the colum n ‘Materials - Package limits ’ in 
Table  4. 
 
Table  4 Activity limits for package exception  
Physical state of contents (phase)  Device or product  Materials - 
Package 
limitsa) Item 
limitsa) Package 
limitsa)  
Solids:     
special form radioactive material  10-2A1 A1 10-3A1 
radioactive material other than special form  10-2A2 A2 10-3A2 
Liquid  10-3A2 10-1A2 10-4A2 
Gases:     
Tritium (3H) 2x10-2A2 2x10-1A2 2x10-2A2 
special form radioactive material  10-3A1 10-2A1 10-3A1 
radioactive material other than special form  10-3A2 10-2A2 10-3A2 
Legend:  
a) For mixtures of radionuclides, see Points  4 to 6.  
 
 
23. 1. Radioactive material that is enclosed in or contained in an instrument or 
product may be classified under UN  2911, RADIOACTIVE MATERIAL, 
PACKAGE EXCEPTION - DEVICES or PRODUCTS, if: 
a) the radiation level at 10  cm from any point on the external surface of any 
unpackaged instrument or product is less than or equal to 0.1  mSv/h;  
b) each device or product is marked ' RADIOACTIVE '. Marking is not required 
for: 
1. the faces of  timepieces or other devices marked with radioluminescent 
paint;  
2. consumer products that have either received type approval from the 
Office or do not individually exceed the activity limit for an exempt 
consignment in the column marked “Activity limit for a n exempt 
consignment [Bq] ” in Table  2, provided that they are transported in a  - 53 - 
package that is marked “RADIOACTIVE ” on an internal surface in 
such a manner that it is visible when the package is opened; and  
3. other devices or products that are too small to b e marked with 
“RADIOACTIVE ”, if they are transported in packaging that is marked 
“RADIOACTIVE ” on an internal surface in such a manner that is 
visible when the package is opened;  
c) the radioactive material is completely enclosed by a non -active compound; a 
device performing the sole function of containing radioactive material shall not 
be considered to be an instrument or product pursuant to Point  23; and  
d) the activity limits specified in the column ‘Item limits ’ in Table  4 are met for an 
instrument or product , and the activity limits specified in the column ‘Package 
limits ’ in Table  4 are met for a package.  
 
24. Radioactive material in forms other than as specified in Point  23 and with an 
activity not exceeding the limits specified in the column ‘Materials - Package 
limits ’ of Table  4 is classified under UN 2910, RADIOACTIVE MATERIAL, 
PACKAGE EXCEPTION - LIMITED QUANTITY OF MATERIAL , provided 
that: 
a) the package retains its radioactive contents under routine conditions of 
transport; and  
b) the package is marked “RAD IOACTIVE ” 
1. on an internal surface in such a manner that is visible when the package 
is opened, or  
2. elsewhere than on the package if marking the internal surface is not 
feasible.  
 
25. Uranium hexafluoride, if its activity does not exceed the limits specified in the 
column ‘Materials - Package limits ’ of Table  4 is classified under UN 3507  
URANIUM HEXAFLUORIDE , RADIOACTIVE MATERIAL, PACKAGE 
EXCEPTION – less than 0.1  kg in the package, exempt fissile material or non -
fissile material, if:  
a) the mass of uranium hexa fluoride in the package is less than 0.1  kg, and  
b) the requirements of Points  20 and 24 are met.  
 
26. Articles manufactured of natural uranium, depleted uranium or natural thorium 
and articles in which the sole radioactive material is unirradiated natural ur anium, 
unirradiated depleted uranium  or unirradiated natural thorium may be classified 
under UN 2909, RADIOACTIVE MATERIAL, PACKAGE EXCEPTION - 
PRODUCTS MADE FROM N ATURAL URANIUM or DEPLETED URANIUM 
or THORIUM, if the outer surface of the uranium or thoriu m is enclosed in an 
inactive sheath made of metal or some other substantial material.  
 
5.2. Additional requirements and controls for transport of empty packagings  
27. An empty packaging that had previously contained radioactive material may be 
classified under UN 2908, RADIOACTIVE MATERIAL, PACKAGE 
EXCEPTION - EMPTY PACKAGING, if: 
a) it is defect -free 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;   - 54 - 
c) the level of internal non -fixed contamination does not exceed one hundred 
times the limits specified in Point  8 of Annex  4 to this decree; and  
d) any labels which may have been displayed on it in conformity with Point  38 of 
Annex  4 to this decree a re no longer visible.  
 
5.3. Classification as a Type  A radioactive package  
28. A package containing radioactive or fissile material is classified as a Type A 
package if it adheres to the requirements of Points  29 and 30.  
 
29. Type A packages shall not contain a ctivities greater than the following::  
a) A1 for special form radioactive material; and  
b) A2 for radioactive material other than special form.  
 
30. For mixtures of radionuclides whose identities and activities are known, the 
following condition shall apply to t he radioactive contents of a Type A package:  
Σ [B(i)/A 1(i)] + Σ [C(j)/A 2(j)]  1, 
 i j 
where:  
B(i) is the activity of radionuclide i as special form radioactive material;  
A1(i) value of A 1 for radionuclide  i; 
C(j) is the activity of radionuclide j as other  than special form radioactive material; 
and 
A2(j) is the value of A 2 for radionuclide  j. 
 
5.4. Classification as a Type B(U), B(M), and C radioactive package  
31. A Type B(U), Type B(M) and Type C package shall be classified in accordance 
with a type approval d ecision issued by the Office or in accordance with 
document issued by a competent authority of the country of origin of design.  
 
32. A Type  B(U), Type  B(M) and Type  C package shall meet specifications in a type 
approval decision issued by the Office or spe cifications in a document issued by a 
competent authority of the country of origin of the design.  
 
33. A Type B(U) and Type B(M) package, if transported by air, shall meet the 
requirements of Point  32 and shall not contain activities greater than the 
follo wing:  
a) for low dispersible radioactive material, activity values approved for the given 
design;  
b) for special form radioactive material, 3  000 A1 or 100  000 A2, whichever is 
less; 
c) for other than special form radioactive material, 3000  A2. 
 
 
6. TRANSPORT UNDER SP ECIAL ARRANGEMENTS  
 
34. Radioactive or fissile material shall be classified as transported under special 
arrangements if it is carried pursuant to §  9(4)(c) of the Atomic Act.   - 55 - 
 
Annex  4 to Decree  No …………  
 
TECHNICAL AND ORGANI SATIONAL CONDITIONS OF CARRIAGE  AND 
TRANSPORT OF RADIOAC TIVE OR FISSILE MATE RIAL  
 
1. REQUIREMENTS BEFORE THE FIRST SHIPMENT  
 
1. Before a packaging is first used to transport radioactive or fissile material:  
a) it shall be confirmed that it has been manufactured in conformity with design 
speci fications, and  
b) meets the following requirements:  
1. if the design pressure of the containment system exceeds 35 kPa, the 
containment system of each packaging shall conform to approved 
design requirements relating to the capability of that system to maintain 
its integrity under that pressure;  
2. the effectiveness of shielding and containment and, where necessary, 
the heat transfer characteristics and the effectiveness of the confinement 
system of packaging intended for use as a Type  B(U), Type  B(M) or 
Type  C packa ge and packaging intended for the carriage of fissile 
material shall be within the limits of the approved design; and  
3. packaging intended for the carriage of fissile material it shall be capable 
of ensuring effectiveness of the criticality safety features w ithin the 
limits applicable to or specified for the design. Where, in order to 
comply with the requirements of Point  73 of Part  I of Annex  1 to this 
decree, neutron poisons are included in the packaging, checks shall be 
performed to confirm the presence an d distribution of those neutron 
poisons.  
 
 
2. REQUIREMENTS BEFORE EACH SHIPMENT  
 
2. Before shipment of a package, it shall be ensured that it contain:  
a) radionuclides different from those specified for the package design; and  
b) contents in a form, or physical or chemical state, different from those specified 
for the package design.  
 
3. Before shipment of a package:  
a) lifting attachments that do not meet the requirements of Point  8 of Part  I of 
Annex  1 to this decree shall be removed or otherwise rendered incapable o f 
being used for lifting the package, in accordance with Point  9 of Part  I of 
Annex  1 to this decree;  
b) a Type B(U), Type B(M) and Type C package shall achieve equilibrium 
conditions sufficient to demonstrate compliance with the requirements for 
temperature and pressure, pursuant to the packaging type approval decision 
issued by the Office or a relevant authority of the state of origin of the 
packaging;  
c) closures, valves or other openings of the containment system through which the 
radioactive contents of a Ty pe B(U), B(M) or C package might escape are 
closed and, where feasible, sealed in a manner where checks or suitable tests  - 56 - 
are capable of demonstrating compliance with the requirements of Points  59 
and 71 of Part  I of Annex  1 to this decree; and  
d) for a packa ge containing fissile material, the measurements specified in 
Point  77(b) of Part  I of Annex  1 to this decree and the tests to demonstrate 
closure of the package as specified in Point  80 of Part  I of Annex  1 to this 
decree shall be performed.  
 
 
3. TRANSPORT O F OTHER GOODS  
 
4. A package may contain only instruments necessary for the handling of the 
radioactive content. The interaction between these instruments and the package, 
under the conditions of transport applicable to its design, shall not reduce the its 
safety.  
 
5. Freight containers, IBCs, packagings, and overpacks used for the transport of 
radioactive or fissile material may be used for the storage or transport of other 
goods if after their decontamination, the value of non -fixed surface contamination:  
a) is less than 0.4  Bq/cm2 for beta and gamma emitters and low -toxicity alpha 
emitters; and  
b) is less than 0.04  Bq/cm2 for all other alpha emitters.  
 
6. A consignment shall be segregated from other dangerous goods during transport 
in compliance with the relevan t regulations for carriage of dangerous goods of the 
country of origin, transit  and destination; regulations of a qualified carrier may 
also be used if they ensure the same or a greater level of protection.  
 
 
4. OTHER DANGEROUS PROP ERTIES OF CONTENTS  
 
7. Any other dangerous properties of the contents of the package, such as 
explosiveness, flammability, pyrophoricity, chemical toxicity and corrosiveness, 
shall be taken into account in the packing, labelling, marking, placarding, storage 
and transport.  
 
 
5. REQUIRE MENTS FOR DETECTING CONTAMINATION AND FO R SECURING 
LEAKING PACKAGES  
 
8. The non -fixed contamination on the external surfaces of a package shall be kept as 
low as practicable and, under routine conditions of transport, shall not exceed the 
following limits:  
a) 4.0 Bq/cm2 for gamma and beta emitters and low -toxicity alpha emitters; and  
b) 0.4 Bq/cm2 for all other alpha emitters;  
these limits are applicable when averaged over any area of 300  cm² of any part of 
the surface.  
 
9. The level of non -fixed contamination on  the external and internal surfaces of a 
freight container, IBC, packaging, and overpack shall not exceed the limits 
specified in Point  8.  - 57 - 
 
10. If there is suspicion or it is evident that a package is damaged or that radioactive 
contents are leaking, acces s to the package shall be restricted and a qualified 
person shall assess the extent of contamination and the resultant radiation level of 
the package. The assessment shall include the package, the conveyance, the 
adjacent loading and unloading areas and, i f necessary, all other material that has 
been carried on or in the conveyance.  
 
11. A damaged package or a package leaking radioactive contents in excess of 
allowable limits for normal conditions of transport shall be repaired or otherwise 
restored to a fu nctional state and decontaminated prior to being forwarded for 
further carriage. Until it is forwarded for further carriage, it may be temporarily 
placed in a monitored location.  
 
12. A conveyance and equipment used regularly for the transport of radioacti ve or 
fissile material shall be periodically checked to determine the level of 
contamination. The frequency of such checks shall be correspond to the likelihood 
of contamination and the extent to which radioactive or fissile material is being 
transported.  
 
13. A conveyance, part thereof, or equipment that has become contaminated above the 
limits specified in Point  8 during the transport of radioactive or fissile material, or 
that shows a radiation level in excess of 5  Sv/h, shall be decontaminated by a 
qualified person. They may be reused if:  
a) non-fixed contamination does not exceed the limits specified in Point  8; 
b) the radiation level resulting from fixed contamination does not exceed 5  Sv/h 
on the external surface.  
 
14. A freight container, tank, IBC or co nveyance dedicated to the transport of 
unpackaged material under exclusive use shall be excepted from the requirements 
for non -fixed contamination on the internal surface of Points  9 and 13 for as long 
as it remains under exclusive use.  
 
 
6. REQUIREMENTS AND CONTROLS FOR TRANSPO RT OF PACKAGE 
EXCEPTIONS  
 
15. 1. A package exception need only meet the requirements of Points  3 to 5, 7 to 13, 
16, 30 to 33, 45, 46 introductory sentence, 46(a), 46(k), 50, 53, 55, 56, 61, 64, 82 
and 83; all other relevant requirements  of this decree shall be met.  
 
2. If the package exception contains fissile material, one of the conditions in 
Point  17(a) to (f) of Annex  3 to this decree for an exempt fissile material must be 
met. 
 
16. The radiation level at any point on the external su rface of a package exception 
shall not exceed 5  Sv/h.  
  - 58 - 
7. REQUIREMENTS AND CON TROLS FOR TRANSPORT OF LSA MATERIAL AND 
SCO ITEMS IN INDUSTR IAL PACKAGES OR UNPA CKAGED  
 
17. The quantity of LSA material or SCO in a single Type  IP-1, IP -2, IP -3 package, or 
object  or collection of objects shall be so restricted that the external radiation level 
at 3 m from the unshielded material or object or collection of objects does not 
exceed 10  mSv/h.  
 
18. LSA material and SCO that are or contain fissile material that do not m eet 
conditions for use in one of the exceptions pursuant to Point  17(a) to (f) of 
Annex  3 to this decree for an exempt fissile material shall meet the applicable 
requirements of Points  68 and 69.  
 
19. LSA material and SCO that are or contain fissile materi al shall meet the 
applicable requirements of Point  73. 
 
20. LSA material and SCO in groups LSA -I and SCO -I may be transported, 
unpackaged, under the following conditions:  
a) other than ores containing only naturally occurring radionuclides, they are 
transport ed in such a manner that under routine conditions of transport there 
will be no escape of the radioactive contents from the conveyance nor loss of 
shielding;  
b) they conveyance shall be under exclusive use, except when only transporting 
SCO -I on which the con tamination on the accessible and the inaccessible 
surfaces is not greater than the limit specified in Point  8; 
c) for SCO -I where it is suspected that non -fixed contamination exists on 
inaccessible surfaces in excess of the values specified in Point  13(2)(a) of 
Annex  3 to this decree, measures shall be taken to ensure that the radioactive or 
fissile material is not released into the conveyance; and  
d) unpackaged fissile material meets the requirements of Point  17(e) of Annex  3 
to this decree.  
 
21. LSA material an d SCO, except as otherwise specified in Point  20, shall be 
packaged in accordance with the requirements of Table  1. 
 
Table  1 Industrial package requirements for materials with low mass activity and surface 
contaminated items  
Radioactive contents  Industrial  package type  
 Transport under exclusive use  Transport not under exclusive 
use 
LSA -I Solid a) 
 Liquid  Type IP -1 
Type IP -1 Type IP -1 
Type IP -2 
LSA -II Solid  
 Liquid and gas  Type IP -2 
Type IP -2 Type IP -2 
Type IP -3 
LSA -III Type IP -2 Type IP -3 
SCO -I a) Type IP-1 Type IP -1 
SCO -II Type IP -2 Type IP -2 
Legend:  
a) Under the conditions specified in Point  20, LSA -I material and SCO -I may be transported unpackaged.  
  - 59 - 
 
22. The total activity in a single hold or compartment of an inland waterway craft, or 
in another  conveyance, for carriage of LSA material or SCO in a Type IP -1, IP -2 
or IP-3 package or unpackaged, shall not exceed the limits shown in Table  2. 
 
Table  2 Activity limits for materials with low mass activity and surface contaminated items in 
industrial pa ckages or transported as unpackaged  
Type of material or object  Activity limit for 
conveyances other than 
inland waterway craft  Activity limit for a hold or 
compartment of an inland 
waterway craft  
LSA -I Unlimited  Unlimited  
LSA -II and LSA -III 
non-combustib le solids  Unlimited  100 A 2 
LSA -II and LSA -III 
combustible solids  
and all liquids and gases  100 A 2 10 A 2 
SCO  100 A 2 10 A 2 
 
 
8. DETERMINATION OF THE  TRANSPORT INDEX  
 
23. The TI for a package, freight container, overpack, unpackaged material in group 
LSA -I or unpackaged object in group SCO -I is a number derived in accordance 
with the following procedure:  
a) multiply the maximum radiation level in units of millisieverts per hour (mSv/h) 
at a distance of 1  m from the external surfaces of the package, freight 
contai ner, overpack  or unpackaged LSA -I or SCO -I by 100. For uranium and 
thorium ores and their concentrates, the maximum radiation level at any point 
1 m from the external surface of the load may alternatively be taken as:  
1. 0.4 mSv/h for ores and physical concen trates of uranium and thorium;  
2. 0.3 mSv/h for chemical concentrates of thorium;  
3. 0.02 mSv/h for chemical concentrates of uranium, other than uranium 
hexafluoride;  
b) for tanks, freight containers and unpackaged LSA -I materials and unpackaged 
SCO -I items, the va lue determined in step (a) shall be multiplied by the 
appropriate factor from Table  3; and  
c) the value obtained in steps (a) and (b) shall be rounded up to the first decimal 
place, except for values of 0.05 or less, which may be considered to be zero.  
 
Table  3 Multiplication factors for large loads  
Load dimensions a) Multiplication factor  
load dimensions ≤ 1 m2 1 
1 m2 < load dimensions ≤ 5 m2 2 
5 m2 < load dimensions ≤ 20 m2 3 
load dimensions > 20  m2 10 
Legend:  
a) Largest cross -sectional area of the load  being measured.   - 60 - 
 
 
24. The TI shall be determined, for:  
a) a non -rigid overpack, as the sum of the TIs of packages it contains; and  
b) a freight container, overpack  or conveyance, as either the sum of the TIs of all 
the packages it contains, or by direct measure ment of radiation level.  
 
 
9. DETERMINATION OF THE  CRITICALITY SAFETY I NDEX FOR FREIGHT 
CONTAINERS, OVERPACK S, AND CONSIGNMENTS  
 
25. The CSI for a freight container, overpack, consignment, or conveyance shall be 
determined as the sum of the individual CSIs of  all the packages it contains.  
 
 
10. LIMITS FOR THE TRANS PORT INDEX, CRITICAL ITY SAFETY INDEX, AN D 
RADIATION LEVELS FOR  PACKAGES AND OVERPAC KS 
 
26. 1. Except for consignments under exclusive use, the TI of any package or 
overpack shall not exceed 10.  
 
2. The C SI of any package or overpack shall not exceed 50.  
 
27. The radiation level at any point on the external surface of a package or overpack 
shall not exceed 2  Sv/h. The requirement of the introductory sentence does not 
apply to packages or overpacks transpor ted under exclusive use by rail or by road 
in accordance with the conditions specified in Point  73(a), or under exclusive use 
and special arrangement by vessel or by air in accordance with the conditions 
specified in Point  75 or 79.  
 
28. The radiation leve l at any point on the external surface of a package or overpack 
transported under exclusive use shall not exceed 10  Sv/h.  
 
 
11. CATEGORY  
 
29. Packages, freight containers  and overpacks shall be placed in either category I -
WHITE, II -YELLOW, or III -YELLOW pursua nt to the requirements specified in 
Table  4 and pursuant to the requirements of (a) to (d):  
a) if the TI satisfies the condition for one category but the surface radiation level 
satisfies the condition for a different category, the package, freight container  or 
overpack shall be assigned to the higher category; category I -WHITE is 
regarded as the lowest category;  
b) the TI shall be determined via the procedures specified in Points  23 and 24;  
c) except for Point  30, a package transported under special arrangements is  placed 
in category III -YELLOW; and  
d) except for Point  30, an overpack containing packages transported under special 
arrangement is placed in category III -YELLOW.  
  - 61 - 
Table  4 Categories of packages and overpacks  
Conditions   
Transport index  Maximum radiation l evel at any point on the external 
surface  Category  
0 a) at most 0.0005 mSv/h  I-WHITE  
more than 0, but not 
more than 1 a) 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 tha n 2 mSv/h  III-YELLOW  
more than 10  more than 2  mSv/h, but not more than 10  mSv/h  III-YELLOW 
b) 
Legend:  
a) If the measured TI is not greater than 0.05, the TI value may be considered to be zero in accordance with 
Point  23(c).  
b) Shall also be transported u nder exclusive use except for freight containers, see Table  6. 
 
 
12. MARKING, LABELLING, AND PLACARDING  
 
30. 1. A package or overpack shall be assigned a UN number and named pursuant to 
Table  1 of Annex  3 to this decree.  
 
2. In cases of international transport  of packages requiring competent authority 
approval of design or shipment, for which packaging type approval or transport 
authorisation by the relevant authority of the country the shipment concerns, the 
UN number, proper shipping name, categorisation, lab elling and marking shall be 
in accordance with the decision of the relevant authority of the country of origin 
of the design.  
 
12.1. Marking  
31. 1. A package shall be legibly and durably marked on the outside of the packaging 
with an identification of either the  consignor or consignee, or both.  
 
2. If the markings of all the packages within the overpack are not clearly visible, 
the outside of the overpack shall be legibly and durably marked with an 
identification of either the consignor or consignee, or both.  
 
32. 1. A package shall be legibly and durably marked on the outside with the UN 
marking as specified in Table  5. 
 
2. If the markings of all the packages within the overpack are not clearly visible, 
the overpack shall be legibly and durably marked with the wo rd ‘OVERPACK ’ 
and the UN marking as specified in Table  5. 
 
Table 5 UN markings for packages and overpacks  
Item UN marking a) 
Package  
(other than a package exception)  UN number, preceded by the letters 
 
Package exception  UN number, preceded by the letters ‘UN’ 
UN number, preceded by the letters ‘UN’
 - 62 - 
 for each applicable UN number in the 
overpack, followed by the proper shipping 
name in the case of a n on-excepted package  
Overpack containing only package 
exceptions  UN number, preceded by the letters ‘UN’
for each applicable UN number in the 
overpack  
Legend:  
a)for a list of UN numbers and proper shipping names, see Table  1 of Annex  3 to this decree.  
 
 
33. A package of gross mass exceeding 50  kg shall have its permissible gross mass 
legibly and durably marked on the external surface.  
 
34. A 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 ’; 
c) an IP -2, IP -3, or a Type A package design shall be legibly and durably 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 identification of the packaging specified by the Office.  
 
35. The packaging manufactu red pursuant to a type approval decision shall be legibly 
and durably marked with the following on the outside surface:  
a) the type identification mark in accordance with a type approval decision issued 
by the Office;  
b) a serial number to uniquely identify each  packaging of approved type; and  
c) for Type B(U), B(M), or C packages, ‘TYPE B(U) ’, ‘TYPE B(M) ’, or ‘TYPE 
C’, as applicable.  
 
36. A package that conforms to a Type B(U), Type B(M), or Type C design shall have 
the outside of its packaging marked by embossing,  stamping or other means 
resistant to the effects of fire and water with the trefoil symbol. Table  1 contains 
an example of the trefoil symbol.  
 
37. LSA -I material or an SCO -I object that is contained in receptacles or wrapping 
materials and is transported  under exclusive use pursuant to Point  20 shall be 
marked on the outer surface of these receptacles or wrapping materials with 
‘RADIOACTIVE LSA -I’ or ‘RADIOACTIVE SCO -I’, as appropriate.  
  - 63 - 
 
 
Figure  1 Basic trefoil symbol with proportions based on a central  circle of radius  X. The 
minimum permitted size of X is 4  mm. 
 
 
12.2. Labelling  
38. 1. Except for Point  43, a package, overpack, and freight container shall bear 
labels conforming to the models in:  
a) Figure  2 for the category I -WHITE;  
b) Figure  3 for the category II -YELLOW;  
c) Figure  4 for the category III -YELLOW.  
 
2. Except for an exempt fissile material pursuant to Point  17 of Annex  3 to this 
decree, a package, overpack, and freight container containing fissile material shall 
also bear labels conforming to the model in  Figure  5. 
 
3. Other labels that are not related to the contents shall be removed or covered.  
 
39. 1. Labels conforming to the models in Figures  2, 3 or 4 shall be affixed to two 
opposite sides of the outside of a package or overpack or on the outside of a ll four 
sides of a freight container or tank.  
 
2. The label conforming to the model in Figure  5 shall be affixed adjacent to the 
labels specified in (1).  
 
3. The labels shall not cover the markings specified in Points  31 to 36.  
  - 64 - 
 
 
Figure  2 Category I -WHIT E 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. [TRANSLATION NOT REQ UIRED]  
 
 
12.3. Labelling for radioactive contents  
40. Each label conformin g to the models in Figures  2, 3 and 4 shall be completed with 
the following information on  
a) content:  
1. except for LSA -I material, the names of the radionuclides pursuant to 
Table  2 of Annex  3 to this decree, 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. For materials in an 
LSA group or objects in an SCO group, the names of the radionuclides 
shall be followed by “LSA -II”, “LSA -III”, “SCO -I”, or “SCO -II” as 
applicable; and  
2. for LSA -I material, the term ‘LSA -I’ shall be filled in.  
b) activity: the maximum activity of the radioactive contents during transport 
expressed in units of becquerels (Bq) with the appropriate SI prefix symbol. 
For fissile material, t he total mass of fissile nuclides in units of grams (g), or 
multiples thereof, may be used in place of activity. For an overpack or freight 
container, the ‘contents ’ and ‘activity ’ entries on the label shall bear the  - 65 - 
information in accordance with Letter  (a) and (b). Labels for an overpack or 
freight container containing a mixed load of packages containing different 
radionuclides, entries in the content and activity rows may read: “See Transport 
Documents ”; and  
c) transport index: the number determined in acco rdance with Points  23 and 24; 
no TI entry is required for Category I -WHITE.  
 
12.4. Labelling for criticality safety  
41. Each label conforming to the model in Figure  5 shall be completed with the  CSI 
as stated in the transport authorisation or packaging type appr oval decision issued 
by the Office, in a decision issued by the relevant authority of the country of 
origin of the packaging or the country of origin of carriage in the case of 
international carriage, or in accordance with the requirements of Point  74 or 7 5 of 
Part I to Annex  1 to this decree.  
 
42. For an overpack or freight container, the label conforming to the model in 
Figure  5 shall bear the sum of the CSIs of all the packages contained therein.  
 
12.5. Placarding  
43. A large freight container carrying package s other than package exceptions, and a 
tank shall bear placards that conform to the model given in Figure  6. The placards 
shall be affixed in a vertical orientation to the front, each side wall  and to the rear 
wall of the large freight container or tank. O ther labels that do not relate to the 
contents shall be removed. Instead of using both labels and placards, it is possible 
to use only enlarged labels as shown in Figures  2, 3, 4, or 5, enlarged so they have 
the minimum dimensions as specified in the model  in Figure  6. 
  - 66 - 
 
 
Figure  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.  [TRANSLATION  NOT REQUIRED]  
 
 
44. 1. Where a consignment of unpackaged LSA -I or SCO -I being shipped in a 
freight container or tank is or a consignment of packaged radioactive material 
being shipped under exclusive use can be marked with a single UN number,  the 
UN number for the consignment shall be displayed in black digits not less than 
65 mm high:  
a) in the lower half of the placard shown in Figure  6 on a white background; or  
b) on a placard pursuant to the model shown in Figure  7. 
 
2. When marking pursuant to (1)(b), the subsidiary placard pursuant to the model 
in Figure  7 shall be affixed immediately adjacent to the main placard pursuant to 
the model in Figure  6 on all four sides of the freight container or tank.  
  - 67 - 
 
 
Figure 4 Category III -YELLOW label. The bac kground 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. [TRANSLATION  NOT REQUIRED]  
 
 
13. THE CARRIER'S OBLIGA TIONS  
 
45. Unless otherwise specified in this decree, no radioactive or fissile material shall be 
provided for transport unless it is properly marked, labelled, placarded, described 
in transport documents, includes a declaration of the carrier or confirmation of 
freight container or conveyance loading, as applicable, and is in every aspect 
suitable for transport.  
  - 68 - 
 
 
Figure  5 Criticality safety index label. The background colour of the label shall be white, the 
colour of the printing shall be black. [TRANSLATION  NOT REQUIRED]  
 
 
13.1. Particulars of consignment description in the carriage document  
46. 1. In the transport documents accompanying a consignment, the carrier shall 
include identification of the consignor and consignee, in the case of a natural 
person their name(s) , surname and addresses, and in the case of a corporate entity 
its name and registered address, and the relevant information in the following 
order:  
a) the UN number assigned to the radioactive or fissile material, preceded by the 
letters ‘UN’; 
b) the proper shi pping name assigned to the radioactive or fissile material;  
c) UN class number ‘7’; 
d) subsidiary hazard class numbers corresponding to the label numbers required if 
the radioactive or fissile material is also classified in other classes or subclasses 
of dangero us goods; the subsidiary hazard class numbers shall follow the 
primary hazard class number in brackets;  
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 radioactive or fissile 
material, or information that the material is special form radioactive material or  - 69 - 
low dispersible radioactive material; the chemical form may be stated as a 
chemical formula;  
g) the maximum activity of the radioactive contents during transport expressed in 
units of becquerels (Bq) with the appropriate SI prefix symbol. In place of 
activity, the following may be provided:  
1. for fissile material, total mass in grams (g) or multiples t hereof; and  
2. for a mixture of fissile radionuclides, the mass of each fissile nuclide 
present in grams (g) or multiples thereof;  
h) the category of the package, i.e. I -white , II-yellow , or III-yellow;  
i) the TI for categories II-YELLOW and III-YELLOW ; 
j) for fissile  material:  
1. shipped under one of the exceptions in Point  17(a) to (f) of Annex  3 to 
this decree, a reference to this provision;  
2. shipped under one of the exceptions in Point  17(c) to (e) of Annex  3 to 
this decree, the total mass of fissile radionuclides;  
3. shipped in a package with the use of one of the provisions of 
Point  74(a) to (c) of Annex  1 to this decree, a reference to this 
provision; and  
4. the criticality safety index;  
k) the identification mark of a type approval or transport authorisation decision 
issued by the Office, and in the case of international transport, also the 
identification mark of the authorisation of the relevant authority of the country 
the transport concerns that is required for the consignment;  
l) for a consignment shipped under exclusive use , the statement “EXCLUSIVE 
USE SHIPMENT ”; and  
m) for a consignment of LSA -II, LSA -III, SCO -I and SCO -II, the total activity of 
the consignment as a multiple of A 2; for a consignment of radioactive or fissile 
material for which the A 2 value is unlimited, the m ultiple of A 2 is equal to zero.  
 
2. For a consignment of more than one package, the information pursuant to 
(1)(a) to (k) shall be given for each package. For packages in an overpack, freight 
container, or conveyance, a detailed statement of the contents o f each package 
within the overpack, freight container  or conveyance and, where appropriate, of 
each overpack, freight container  or conveyance shall be included. If individual 
packages are to be removed from the overpack, freight container  or conveyance at 
a point of intermediate unloading, appropriate transport documents for these 
packages shall be made available.  
  - 70 - 
 
Figure  6 Placard Except for Point  71, minimum dimensions shall be as shown; when different 
dimensions are used, the relative proportions shall  be maintained. The numeral ‘7’ shall not be 
less than 25  mm high. 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. 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. [TRANSLATION NOT 
REQUIRED]  
 
  - 71 - 
 
Figure  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 is to be displayed, as 
specified in Table  1 of Annex  3 to this decree. [TRANSLATION NOT REQUIRED]  
 
 
13.2. Consignor ’s declaration  
47. The consignor shall include the following in the transport documents: “I hereby 
declare that the contents of this consignment are fully and accurately described 
above by the proper shipping name and are classified, packaged, mark ed and 
labelled/placarded, and are in all respects in proper condition for transport 
pursuant to applicable international agreements and the legislation of the Czech 
Republic, and in the case of international transport, also pursuant to the legislation 
of the state that the carriage concerns. ” 
 
48. The consignor need not provide a declaration pursuant to Point  47 for that part of 
the transport covered by the obligation to provide a declaration with similar 
content stipulated by an international convention b y which the Czech Republic is 
bound.  
 
49. The declaration pursuant to Point  47 shall be signed and dated by the consignor.  
 
50. Documentation for the transport of dangerous goods may be provided to the 
carrier in writing, or with his/her approval, electron ically.  
 
51. During marine transport of radioactive or fissile material placed or loaded into a 
freight container or on a vehicle, those responsible for loading the container or 
vehicle shall provide a container/vehicle packing certificate specifying the 
container/vehicle identification number and certifying that the operation has been 
carried out in accordance with international requirements.  
 
52. The information required in the transport documents and the container/vehicle 
packing certificate may be incor porated into a single document or attached one to 
each other. If the information is incorporated into a single document, the 
document shall include a signed declaration stating:  
‘I hereby declare that the packing and loading of radioactive or fissile mater ial 
into the container/vehicle has been carried out in accordance with the applicable 
provisions. ’ 
 
53. The declaration pursuant to Point  52 shall be dated and the person signing it shall 
be identified in the document. The declaration shall be made on the transport 
document that contains the information specified in Point  46. 
 
13.3. Information for carriers  
54. The consignor shall provide in the transport documents instructions regarding 
actions that must be taken by the carrier. The instructions shall be in the languages 
required by the carrier, the Office and, in the case of international transport, also 
the appropriate authority of the country the transport concerns. The instructions 
include at least the following:   - 72 - 
a) supplementary requirements for loading, stowag e, carriage, handling  and 
unloading of the package, overpack, or freight container, including any special 
stowage provisions for the safe dissipation of heat, or instructions that no such 
requirements are necessary;  
b) information regarding restrictions on th e mode of transport or conveyance and 
any necessary routing instructions;  
c) instructions regarding emergency arrangements for the given consignment.  
 
55. The consignor shall retain a copy of each of the transport documents containing 
the information specifie d in Points  46, 47, 51, 52 and 54 for at least three months. 
When the documents are kept electronically, the consignor shall be able to 
reproduce them in printed form.  
 
56. The type approval decision and transport authorisation need not accompany the 
consi gnment. However, the consignor shall make them available to the carrier(s) 
before loading and unloading.  
 
13.4. Notification of administrative authorities  
57. Before the first shipment of any package requiring type approval or authorisation 
for transport, the co nsignor shall ensure that copies of the type approval or 
authorisation for transport documents have been submitted to the competent 
authority of the country that the transport concerns.  
 
58. 1. The consignor shall notify the Office, and in the case of inte rnational transport, 
also the competent authority of the country that the transport concerns, regarding 
transport:  
a) of Type C packages containing radioactive or fissile material with activity 
greater than 3.103 A1 or 3.103 A2 or 1 000 TBq, whichever is less ; 
b) of Type B(U) packages containing radioactive or fissile material with activity 
greater than 3.103 A1 or 3.103 A2 or 1 000 TBq, whichever is less;  
c) of Type  B(M) packages; and  
d) under special arrangement.  
 
2. The Office and other competent authorities must re ceive notification pursuant 
to (1) at least seven days prior to the start of transport.  
 
59. The consignment notification shall include:  
a) information enabling the identification of the package or packages, including 
all identification marks in accordance wi th a type approval decision issued by 
the Office, and in the case of international transport, also identification marks 
for the authorisation of the competent authority of the country that the transport 
concerns;  
b) information on the date of shipment, the ex pected date of arrival, and the 
proposed route;  
c) the names of the radioactive or fissile material or radionuclides;  
d) a description of the physical and chemical form of the radioactive or fissile 
material, or information that the material is special form radi oactive material or 
low dispersible radioactive material; and   - 73 - 
e) information regarding the maximum activity of the radioactive contents during 
transport expressed in units of becquerels (Bq) with the appropriate SI prefix 
symbol. In place of activity, the fol lowing may be provided:  
1. for fissile material, total mass in grams (g) or multiples thereof; and  
2. for a mixture of fissile radionuclides, the mass of each fissile nuclide 
present in grams (g) or multiples thereof;  
 
60. The consignor is not required to send a  separate notification pursuant to Points  58 
and 59 if the required information has been included in the transport approval 
application.  
 
13.5. Documents and operating rules the consignor must have available  
61. The consignor shall have available a copy of a dec ision of the decision of the 
Office regarding transport, and in the case of international transport, also a copy 
of a decision of the competent authority of the country that the transport concerns, 
a copy of the instructions with regard to the proper closi ng of the package, and 
preparations for shipment, before making any shipment.  
 
 
14. TRANSPORT AND STORAG E IN TRANSIT  
 
14.1. Segregation during transport and storage in transit  
62. A package, overpack, or freight containers containing radioactive or fissile 
material and unpackaged material shall be segregated during transport and during 
storage in transit from:  
a) workers in regularly occupied working areas by distances calculated using a 
maximum permissible effective dose criterion of 5  mSv in a year and 
conservative mo del parameters;  
b) members of the public in areas where the public has regular access by distances 
calculated using a maximum permissible effective dose criterion of 1  mSv in a 
year and conservative model parameters;  
c) undeveloped photographic film by distances  calculated using a maximum dose 
criterion of 0.1  mGy due to the transport of one consignment of radioactive or 
fissile material on this film; and  
d) other dangerous goods in accordance with Point  6. 
 
63. 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 authorised to accompany such packages or 
overpacks.  
 
14.2. Stowage on or in the conveyance during transport and storage in transit  
64. During t ransport and storage, the consignment shall be securely stowed so that it 
cannot move, turn over  or fall. 
 
65. 1. A package or overpack may be carried or stored among other packaged cargo 
without any special stowage provisions, if:  
a) its average surface heat  flux does not exceed 15  W/m2, and  
b) the immediate surrounding cargo is packaged in a manner other than sacks or 
bags.   - 74 - 
 
2. The provisions of (1) shall not be applied if the Office, and in the case of 
international transport, also the competent authority of t he country that the 
transport concerns, specifies otherwise in a type approval decision.  
 
66. For the loading of freight containers and accumulation of packages, overpacks and 
freight containers, the following applies:  
a) except under the condition of exclusi ve use, and for consignments of LSA -I 
material, the total number of packages, overpacks, and freight containers on or 
in a single conveyance shall not exceed the values shown in Table  6; 
b) the radiation level under routine conditions of transport shall not e xceed 
2 mSv/h at any point on, and 0.1  mSv/h at 2  m from, the external surface of the 
conveyance; for consignments transported under exclusive use by road or rail, 
radiation limits around the vehicle are stipulated in Points  73(b) and (c); and  
c) the sum of t he CSIs in a freight container and on or in a conveyance shall not 
exceed the values shown in Table  7. 
 
Table  6 TI limits for freight containers and conveyances not under exclusive use  
Type of freight container or conveyance  Limit on total sum of 
transport  indexes in a 
freight container or 
aboard a conveyance  
Freight container  small  
 Large  50 
50 
Vehicle  50 
Aircraft  passenger  
 Cargo  50 
200 
Inland waterway vessel  50 
Seagoing vessel a) 
(1) Hold, compartment  or defined deck area:  
 packages, overpacks  or small freight containers  
 large freight containers  
(2) Total vessel:  
 packages, overpacks  or small freight containers  
 large freight containers   
 
50 
200 
 
200 
unlimited  
Legend:  
a) Packages or overpacks on vehicles that meet the requirements of Point  73 may b e transported by vessels 
provided that they are not removed from the vehicle at any time while it is on board the vessel.  
 
67. Packages or overpacks with a TI greater than 10 and consignments with a 
criticality safety index greater than 50 shall be transpo rted only under exclusive 
use. 
 
14.3. Additional transport and storage requirements during transport of fissile material  
68. The number total sum of the criticality safety indexes in a group of packages, 
overpacks  or freight containers containing fissile materia l stored in transit shall 
not exceed 50 in a storage area. The distance between individual groups pursuant 
to the first sentence shall be at least 6  m. 
  - 75 - 
Table  7 CSI limits for freight containers and conveyances containing fissile material  
Type of freight c ontainer or conveyance  Limit on total sum of 
criticality safety indexes in a 
freight container or aboard a 
conveyance  
Other 
transport  Transport 
under 
exclusive use  
Freight container  small  
 Large  50 
50 – 
100 
Vehicle  50 100 
Aircraft  passenger  
 Cargo  50 
50 – 
100 
Inland waterway vessel  50 100 
Seagoing vessel a): 
(1) Hold, compartment  or defined deck area  
 packages, overpacks  or small freight containers  
 large freight containers  
(2) Total seagoing vessel  
 packages, overpacks  or small freight containers  
 large freight containers   
 
50 
50 
 
200 b) 
unlimited b)  
 
100 
100 
 
200 c) 
unlimited c) 
Legend:  
a) Packages or overpacks on a vehicle that meets the requirements of Point  73, may be transported by vessel 
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.  
b) The consignment shall be so handled and stowed that the total sum of CSIs in any group does not exceed 50, 
and that each group is handled and sto wed so that the groups are separated from each other by at least 6  m. 
c) The consignment shall be so handled and stowed that the total sum of CSIs in any group does not exceed 100, 
and that each group is handled and stowed so that the groups are separated from each other by at least 6  m. The 
intervening space between groups may be occupied by other cargo in accordance with Point  6. 
 
 
69. Where the total sum of the criticality safety indexes on board a conveyance or in a 
freight container exceeds 50, storage  shall be such as to maintain a spacing of at 
least 6  m from other groups of packages, overpacks  or freight containers 
containing fissile material or other conveyances carrying radioactive material.  
 
70. Additional requirements relating to transport of fis sile material classified pursuant 
to one of Point  17(a) to (f) of Annex  3 to this decree are as follows:  
a) for a consignment, one in Point  17(a) to (f) of Annex  3 to this decree may be 
used;  
b) a consignment may carry only one exempted fissile material in packa ges 
pursuant to Point  17(f) of Annex  3 to this decree, unless specified otherwise by 
the Office, and in the case of international transport, also the competent 
authority of the country that the transport concerns, in the authorisation for 
transport;  
c) exempt ed fissile material in packages pursuant to Point  17(c) of Annex  3 to 
this decree shall be transported in a consignment containing at most 45  g of 
fissile radionuclides;   - 76 - 
d) exempted fissile material in packages pursuant to Point  17(d) of Annex  3 to 
this decre e shall be transported in a consignment containing at most 15  g of 
fissile radionuclides; and  
e) unpackaged and packaged exempted fissile material in packages pursuant to 
Point  17(e) of Annex  3 to this decree shall be transported in a consignment 
containing a t most 45  g of fissile radionuclides, and must be transported under 
exclusive use.  
 
14.4. Additional requirements relating to transport by rail and road  
71. 1. Rail and road vehicles carrying packages, overpacks or freight containers 
labelled with any of the lab els shown in Figure  2, 3, 4 or 5 or carrying 
consignments under exclusive use shall display the placards shown in Figure  6: 
a) on the two external lateral walls in the case of a rail vehicle; or  
b) on the two external lateral walls and the rear wall in the case of a road vehicle.  
 
2. In the case of a vehicle without sides, the placards may be affixed directly on 
the chassis carrying the cargo provided that they are readily visible; in the case of 
large -volume tanks or freight containers, the placards shall be pla ced only on 
them. In the case of vehicles which have insufficient area to allow the fixing of 
larger placards with dimensions as described in Figure  6, the dimensions the sides 
of the placard may by reduced to 100  mm. Other labels that do not relate to the  
radioactive contents of the vehicle shall be removed.  
 
72. 1. Where a consignment of unpackaged LSA -I or SCO -I being on or in a vehicle 
or a consignment of packaged radioactive or fissile material being shipped under 
exclusive use on or in a vehicle can b e marked with a single UN number, the UN 
number for the consignment shall be displayed in black digits not less than 65  mm 
high:  
a) on a white background in the lower half of the placard shown in Figure  6; or 
b) on a placard pursuant to the model shown in Figure  7. 
 
2. When marking pursuant to (1)(b), the placard pursuant to the model in Figure  7 
shall be affixed immediately adjacent to the main placard pursuant to the model in 
Figure  6 on the two external lateral walls in the case of a rail vehicle or on the two  
external lateral walls and the rear wall in the case of a road vehicle.  
 
73. 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; the 
radiation level shall ho wever not exceed 2  mSv/h in the following situations:  
1. the vehicle is not equipped with an enclosure that during routine 
conditions of transport prevents unauthori sed persons from accessing 
the interior of the enclosure;  
2. provisions are not made to secure th e package or overpack so that its 
position within the vehicle remains fixed during routine conditions of 
transport; and  
3. there is loading or unloading during the shipment;  
b) 2 mSv/h at any point:  
1. on the outer surfaces of an enclosed vehicle, including roof an d floor 
areas; or   - 77 - 
2. on a vertical plane projected from the outer edge of an open vehicle, the 
surface of the load and the lower external surface of the vehicle; and  
c) 0.1 mSv/h at any point 2  m from:  
1. the external surface of a vertical plane of an enclosed vehi cle; or  
2. the vertical plane that intersects the external edge of an open vehicle.  
 
74. 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 ca tegory II -YELLOW or III -YELLOW labels.  
 
14.5. Additional requirements relating to transport by vessels  
75. Packages or overpacks having a surface radiation level greater than 2  mSv/h shall 
not be transported by vessel. The provision of the first sentence does no t apply to 
packages or overpacks:  
a) transported under exclusive use in accordance with Table  6, column “Transport 
under exclusive use ” or on a vehicle that meets the requirements of Point  73, 
provided that they are not unloaded from the vehicle during its pr esence on 
board the vessel; or  
b) transported under special arrangement.  
 
76. The transport of consignments by means of a special use vessel is exempt from 
the requirements specified in Point  66 if:  
a) a radiation protection programme for the shipment has been d rawn up and has 
been approved by the Office or a competent authority of the flag state of the 
vessel, if the operator of the special use vessel is a foreign entity, and also, if 
requested, by the competent authority at each port of call;  
b) stowage arrangemen ts shall be predetermined for the entire route including any 
consignments to be loaded at ports of call en route;  
c) the loading, carriage and unloading of the consignments shall be supervised by 
persons qualified in the transport of radioactive and fissile m aterial.  
 
14.6. Additional requirements relating to air transport  
77. Type B(M) packages and consignments under exclusive use shall not be 
transported on passenger aircraft.  
 
78. Vented Type B(M) packages, packages that require external cooling by an 
auxiliary c ooling system, packages subject to operational controls during 
transport, and packages containing liquid pyrophoric material shall not be 
transported by air.  
 
79. Packages or overpacks having a surface radiation level greater than 2  mSv/h shall 
not be tran sported by aircraft. The provision of the first sentence does not apply to 
packages or overpacks transported under special arrangements.  
 
14.7. Transport by post  
80. The transport of radioactive or fissile material via post is prohibited in the Czech 
Republic.  
 
  - 78 - 
15. OTHER REQUIREMENTS  
 
81. Customs inspection of the radioactive contents of a package shall be performed in 
a location with facilities required to limit and monitor radiation exposure, and in 
the presence of qualified individuals.  
 
82. A package opened upon  the instructions of the Customs Office must be returned 
to its original condition prior to being handed over for further transport.  
 
83. A package that cannot be delivered must be placed in a safe location. The Office 
must be informed of this fact immedia tely. 
 
 
16. CARRIAGE DOCUMENTS K EPT BY AND AVAILABLE  FROM THE CARRIER  
 
84. A carrier shall not accept a consignment for transport unless copies of the 
transport documents, other documents, or information have been handed over, or 
provided electronically.  
 
85. The information applicable to the consignment shall accompany the consignment 
to final destination and must be given to the consignee upon delivery.  
 
86. Information applicable to the consignment given to the carrier in electronic form 
shall be available t o the carrier at all times during transport to the final destination, 
and it must be possible to print out a paper version at any time.  
 
87. The carrier shall retain a copy of the transport document and additional 
information and documentation pursuant to this decree for at least three months.  
 
88. When the documents pursuant to this decree are kept electronically, the consignor 
shall be able to reproduce them in printed form.   - 79 - 
 
Annex  5 to Decree  No …………  
 
SAMPLES OF STANDARD DOCUMENTS  
 
General Comments  
 
Parts A-1 to A -6 are filled in for shipment of radioactive waste  
Parts  B-1 to B -6 are filled in for shipment of spent fuel (including spent fuel intended for final 
deposit, which is therefore classified as waste).  
 
Part  A-1 or B -1 (application for shipment au thorisation): filled in by the applicant, which 
depending on the type of shipment, is  
— a holder in the case of shipment between Member States (Type  MM) or export from the 
Community to third countries (type  ME);  
— a recipient in the case of import to the C ommunity from a third country (Type  IM); 
— a person responsible for shipment in a Member State through which radioactive waste or 
spent fuel enters the Community in the case of transit through the Community (Type  TT). 
 
Part  A-2 or B -2 (acknowledgement of r eceipt): to be filled in by the competent authorities, 
which depending on the type of shipment, are the competent authorities of  
— the country of origin in the case of a Type  MM or ME shipment;  
— the destination country in the case of Type IM shipment;  
— the country where the shipment first enters the Community in the case of a Type  TT 
shipment, and all competent authorities of any transit Member States.  
 
Part  A-3 or B -3 (consent or refusal): to be filled in by all relevant competent authorities.  
 
Part  A-4a/A-4b or B -4a/B -4b (consent or refusal of transport): to be filled in by the 
competent authority responsible for issuing the authorisation, which depending on the type of 
shipment, is the competent authority of  
— the country of origin in the case of Type M M and ME shipment;  
— the destination Member State in the case of type IM shipment; or  
— the first Member State where the shipment enters the Community, in the case of a 
Type  TT shipment.  
 
Part  A-5 or B -5 (a description of the consignment/list of packagings ): filled in by the applicant 
stipulated in Part A-1 or B -1. 
 
Part  A-6 or B -6 (acknowledgement of receipt of the shipment): to be filled in by the recipient 
(for shipment Type  MM and IM) or the holder (for a Type  ME shipment), or the person 
responsible for  shipment (in the case of a Type  TT shipment).  
32008D0312   - 80 - 
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Annex  6 to Decree  No …………  
 
REQUIREMENTS FOR CAL CULATION OF ACTIVITY  VALUES FOR 
EXCEPTION OF A PACKA GE FOR TRANSPORT OF RAD IOACTIVE OR FISSILE 
MATERIAL IN IN STRUMENTS OR PRODUCT S 
 
Principles and methods for calculation of activity values for exception of a package for 
transport of radioactive or fissile material in instruments or products are stipulated in IAEA 
document Radiation Protection and Safety of Radia tion Sources: International Basic Safety 
Standards, General Safety Requirements, IAEA Safety Standards Series No.  GSR, Part 3, 
International Atomic Energy Agency, Vienna, 2014.