317/2002 Sb.



The DECREE



The State Office for nuclear safety



of 13 June. June 2002



on the type approval of packaging for the transport, storage and

storage of nuclear materials and radioactive substances, the rating

approval of ionizing radiation sources and the transport of nuclear materials

and specified radioactive substances (type approval and transport)



Change: 317/2002 Coll. (part)



Change: 77/2009 Sb.



The State Office for nuclear safety provides under section 47, paragraph. 7 of the Act to

the implementation of § 9 (2). 1 (a). m) and (p)), section 13 (3). 3 (b). (d)), section 20 (2).

1 (a). (b)), and (d)) and section 23 of Act No. 18/1997 Coll. on peaceful uses of

of nuclear energy and ionizing radiation (the Atomic Act) and on the amendment and

supplementing certain acts, as amended by Act No. 13/2002 Coll. (hereinafter referred to as

the "law"):



§ 1



The subject of the edit



This Decree



and the details and procedure) regulates the type approval of packaging

for the transport of storage or disposal of nuclear materials and

radioactive substances and ionizing radiation sources, authentication, and

the substantiation of their conformity with the approved type



(b)) provides for nuclear materials and radioactive substances, the transport

It is necessary to permit, security of transport, content, scope and method

the implementation of the approval documentation, which is part of the application for

the authorization,



(c)), adjusted in accordance with the law of the European communities the scope and ways of

the international transport of radioactive wastes and sealed sources. ^ 1)



PART THE FIRST



THE TYPE-APPROVAL OF



§ 2



Type-approved products



(To section 23 (1) of the Act)



(1) Type approval shall be subject to



and these kinds of containers) intended for the transport, storage and

storage of nuclear materials and radioactive substances



1. the packaging files of type IP-1, IP-2 and IP-3 for the transport of nuclear

materials,



2. packaging the files for the transport of 0.1 kg or more of uranium hexafluoridu,



3. packaging the files of the type and for the transport of nuclear materials,



4. packaging files of type B (U), (B) to (M) and (C) for the carriage of nuclear materials

and radioactive substances,



5. packaging files of type D, designed to store the spent or irradiated

nuclear fuels or radioactive wastes arising from his

processing,



6. packaging files of type S, intended for storage of nuclear materials and

radioactive substances and radioactive substances for specific forms,

the activity exceeds the values A1, or radioactive substances, other

than the specific form, the activity exceeds the value A2. The values of A1 and

A2 are listed in table 1. (I) Annex 3,



(b)) radioactive substances of special forms, which are fixed

nerozptýlitelné a radioactive substance or radioactive substances in just

the enclosed sleeve and radioactive substances with little rozptýlitelností,

which are radioactive substances in the solid state, which have

limited ability to be distracted, or radioactive substances in closed

sleeve,



(c)) sources of ionizing radiation



1. radiation generators, in addition to the non-ionizing radiation sources,



2. closed radionuclide sources and devices, which sealed sources

contain,



3. open the radionuclide emitters for use in the medical

exposure and in industrial applications, in addition to radiopharmaceuticals registered

under special legislation ^ 2) with the consent of the national authority for

nuclear safety (hereinafter referred to as "the authority"),



4. ionization smoke detectors,



5. light sources with radionuklidovými radiators,



6. consumer products, established a special legal regulation, ^ 3) that

they contain radioactive substances, and to products which were in their manufacture

radioactive substances intentionally added.



(2) Type-approval are also subject to the products referred to in paragraph 1

(a). (b)), and (c)), if they are placed on the market or used as after total

repair, and the products referred to in paragraph 1 (b). and) in cases which

provides for a decision on the type of approval.



(3) the products referred to in paragraph 1 which are intended for demonstration or

testing and are not intended for placing on the market, type approval

are not subject to.



§ 3



Particulars of the application for type-approval



(Section 23, paragraph 2, of the Act)



(1) the application for type approval has



and in the case of a natural person) business name, date of birth, address of location

permanent residence, identification number, if one has been assigned, or

name and surname, date of birth, address of residence

the responsible representative ^ 4) if appointed; in the case of a legal person business

name, registered office, registration number, if it has been assigned, the name and

the last name, the address of the place of residence of the person or persons who are

its statutory authority or the designated representative responsible



(b) identification of the manufacturer, it is)-if different from the applicant; in the case of a natural person

business name, head office or place of business, the identification number, if

has been allocated; in the case of a legal person, business name, address, identification

If the number has been assigned,



(c) the identification of the approved product), name, description, designation

design type, its parts, classification, ^ 3) use and packing

file limits its use,



(d) a description of the purpose and mode of) placing of a product on the market and for the resources

ionizing radiation also justify its use pursuant to section 4, paragraph 4. 2

the law,



e) a list of the legislation and technical standards applied in the

documents for type-approval,



(f) the determination of the period for the regular) repetition of operational controls and their

the method and extent, with ionizing radiation sources also data on the scale and

How to conduct the acceptance tests, tests of long-term stability and

operational stability under special legislation, ^ 3)



g) directions for use in English covering the rules of safe

the treatment of the product,



(h) the period of validity of) the type-approval,



I) a description of how the security quality laid down specific legal

Regulation, ^ 5)



j) documentation of the tests in accordance with section 4.



(2) the application for type approval under



and) for all packaging



1. material specifications of radioactive substances or nuclear

materials for which the packaging is designed, in particular, a description of the file

their physical and chemical States,



2. a detailed description of the type of packaging, including the design

the documentation complete technical drawings, a list of materials and

technological methods that have been used for its manufacture,



3. a description of how the quality of security provided for a particular legal

Regulation, ^ 5)



4. technological and production documentation with detailed description of the materials and

technological methods, used in the manufacture of restraint (kontejmentového)

the system, a description of the sampling and the types of tests to be performed,

If the package file has been designed for the maximum normal operating

pressure greater than 100 kPa,



5. the documents to ensure radiation protection or securing documents

nuclear safety, if the packaging has been designed for a specific file

fissile materials or 241Pu,



6. listing and justification of the assumptions relating to the characteristics of the

irradiated nuclear fuel used in safety analyses in the

podkritičnosti calculations, if the packaging file designed for the irradiated

nuclear fuel,



7. list the specific requirements necessary for the heat dissipation for packaging

files containing nuclear materials or radioactive substances

producing heat, in relation to a particular type of transport and transport

resource,



8. fine illustrations of the appearance of the packaging file format

A4 on the maximum dimensions 21 cm to 30 cm,



(b)) for packaging files of type B (M) is also under-



1. list of additional technical, operational and administrative

measures to ensure nuclear safety and radiological protection, if the

This package file does not meet requirements set out in paragraphs 43,

59, 60. and 63. up to 70. Part I of annex 1,



2. particulars of any restriction due to the type of transport and of all

special procedures during the loading, carriage, unloading or handling,



3. the highest and lowest values of the surrounding effects (temperature, solar

radiation), which can be expected during transport, and in the design of

the design was based on the type,



(c)) with ionizing radiation sources



1. a detailed description of the basic technical data of a particular type,

design drawings, descriptions and explanations used in the manufacture,



2. a list of the legislation and technical standards which have been applied

in the production, when under the descriptions of the technical solutions and standards documents

compliance with the requirements of ensuring radiation protection,



3. measuring Protocol (test report) processed by the device manufacturer,

including information on the actual operational parameters,



(d)) with ionizing radiation sources, which are radioactive substances,

Furthermore, under



1. particulars of the nature of the radionuclide, its type, manufacturer, activity, chemical and

physical form, descriptions of the radiation protection requirements, proof of

manufacturing authorization in the country of the manufacturer, in the case of open radionuclide emitters

Passport radionuklidového issued by the manufacturer of the heater open for

closed data on radionuclide emitters classification of resistance,

the method of isolation, a description of the structure, the recommended checks
closedness, time of application of the radionuclide, or certificate

the closed radionuklidového, issued by the manufacturer of the heater,



2. the concept of the decommissioning of the containing (i) a description of the safe

the method of management of radioactive waste.



§ 4



Documentation of the tests



(Section 23, paragraph 3, of the Act)



Documentation of the tests are



and the packaging) the results of the tests carried out according to annex No 1

Part II. paragraph. 13. up to 37. and evaluated in accordance with Annex No 1

Part II. paragraph. 1 and 2, which show compliance with the applicable requirements of

referred to at paragraphs 1. up to 9, and it:



1. the requirements of paragraphs 9. up to 21. Part I of Annex No. 1 for all

packaging files



2. the requirements of paragraphs 26. up to 34. Part I of Annex No. 1 for packaging

files of type IP-1, IP-2 and IP-3,



3. the requirements of paragraphs 35. up to 38. Part I of Annex No. 1 for packaging

the files for the transport of 0.1 kg or more of uranium hexafluoridu,



4. the requirements of paragraphs 39. up to 55. Part I of Annex No. 1 for packaging

files of type A,



5. the requirements of paragraphs 56. up to 70. Part I of Annex No. 1 for packaging

files of type B (U),



6. the requirements of paragraphs 71. and 72. Part I of Annex No. 1 for packaging

files of type B (M)



7. the requirements of paragraphs 73. up to 76. Part I of Annex No. 1 for packaging

files of type C,



8. the requirements of paragraphs 77. up to 88. Part I of Annex No. 1 for packaging

files containing fissile materials,



9. the requirements of paragraphs 56. up to 70. Part I of annex 1 and the requirements of the

Annex No 2 for packaging files of type D and type of packaging files with,



(b)) for radioactive substances special forms of the results of the tests carried out

in accordance with paragraph 4. up to 11. Part II. Annex No 1,



(c)) for radioactive substances with a rozptýlitelností test results

carried out in accordance with paragraph 12. Part II. Annex No 1,



(d)) for generators, radiation test results demonstrating the conformity with the relevant

technical standards, ^ 6)



(e)) for closed radionuclide emitters test results proving the

their closeness and degree of resistance in accordance with the relevant technical

standards, ^ 7)



(f)) for equipment containing radionuclide emitters test results

proving the conformity of the device and its classification in accordance with the

technical standards, ^ 8)



(g)) at the open sources, where appropriate, for radionuclide products

tagged open radionuclide emitters in the range test results

the accompanying sheet of open emitters laid down specific legal

Regulation, ^ 3)



(h) the ionization detector) at the fire with closed radionuclide emitter

the results of tests showing the degree of fire resistance, very

high temperatures and the tightness in accordance relevant technical

standards, ^ 7)



even) for ionizing radiation sources, which arise

radionuclides, the reports on the results of tests showing that

declared properties meet the radiation protection requirements in terms of

purpose and use of resources,



j) for consumer products, which contain radioactive substances, and to which

were intentionally added in their production of radioactive substances,

assurance of basic radiation protection requirements throughout the

for their use.



(2) the tests shall be carried out on the products, prototypes, or their

formulas. You can also perform tests on models or mock-ups made

to the maximum extent to mimic the properties important for

assessment of nuclear safety, radiation protection and the projected content

radionuclides.



(3) Documentation of the tests of the products can be replaced by a reference to the previous

satisfactory test results, products of the same or similar use, and

properties, documentation, tests or calculations of the spare documentation,

that have been made by authorized persons or by the designated Authority and, if

reliability or conservativeness computing methods and parameters used

are acceptable to the Authority for evaluation.



§ 5



The method of approval



(Section 23, paragraph 2, of the Act)



In the decision on the type approval of the Office shall state the



and the identification of the applicant, and) to the extent referred to in § 3 (3). 1 (a). and)



(b) identification of the manufacturer, and) to the extent referred to in § 3 (3). 1 (a). (b)),



(c)), and identify the product to the extent referred to in § 3 (3). 1 (a). (c)),



d) range and method of conformity assessment pursuant to section 6,



e) conditions under which the product is issued; for packaging

file special forms of radioactive substances and radioactive substances with a small

rozptýlitelností their identification,



(f)) for ionizing radiation sources of its classification, the frequency and the minimum

the range of acceptance tests, tests of long-term stability and operating

stability,



(g) the period of validity of decision) type approval.



§ 6



Verification and proof of conformity, their scope and the way



(To section 23 (4) and (5) of the Act)



(1) the manufacturer, the importer or the person responsible for placing on the market of the product shall ensure that the

verification of conformity of the product with the approved type



and) for each type of packaging subject to approval in accordance with §

2 (2). 1, for special forms of radioactive substances and radioactive

substances with a small rozptýlitelností in the range, which is determined by the terms of the

the decision about the type approval,



(b)) for each of the contained radionuklidového emitters and tightness test

other tests in the scope of the certificate contained sources specified

a special legal regulation, 3), as appropriate, within the range specified in the

the decision about the type approval,



(c)) for each open tests in the range of radionuklidového heater

the accompanying sheet of open emitters laid down specific legal

Regulation, 3) where appropriate, to the extent provided for in the decision of the rating

approval,



(d)) with ionizing radiation sources other than radioactive substances:



1. the procedures provided for in special legislation, ^ 9)



2. in the case of other sources of ionizing radiation at each product or on

a statistically selected sample, if it is provided by the authority in the decision to

its type-approval.



(2) the compliance of the products is illustrated by the manufacturer, the importer or the person responsible for placing the product

on the market:



and for closed radionuclide emitters) certificate



(b) in the case of open radionuclide emitters) passport,



(c)) for packaging, special forms of radioactive substances,

radioactive substances with a small rozptýlitelností, sources of ionizing

radiation other than radionuclide emitters and other written products

Declaration of conformity of products in the Czech language that contains further

referred to:



1. identification of the manufacturers or importers, that Declaration of conformity

issues, and to the extent referred to in § 3 (3). 1 (a). and)



2. identification details of the product, at least in the scope of § 3 (3). 1 (a).

(c)),



3. a declaration that the product is for the purpose of safe and appropriate,



4. the method of verification of conformity, and a list of the legislation and

technical standards used in the attestation of conformity, ^ 9)



5. name, address and identification number of the person who participated in

on conformity assessment,



6. the date of issue of the Declaration of conformity, the name and title of the person responsible.



(3) the Manufacturer, the importer or the person responsible for placing on the market the product, issue a new

the Declaration of conformity of the product, if there is a change in the facts, which may

affect the characteristics of the product in terms of nuclear safety or

radiation protection, and the product has to be even after this change, continue to be placed on the

the market.



(4) products which have been issued with a written declaration of conformity shall

the manufacturer or the person responsible for placing on the market of the product mark of conformity referred to in

special legal regulation, ^ 9) in addition to the sealed radionuclide

heaters, special forms of radioactive substances and radioactive substances with

a small rozptýlitelností, which replaces the closed radionuclide

radiators certificates closed radionuklidového emitters and radioactive

special forms of substances and radioactive substances with little rozptýlitelností

their type approval.



(5) the sources of ionizing radiation, which has been verified by matching

special legal regulation, ^ 9) provides for the manufacturer, the importer or the person

listing the product on the market, the classification of the product and the minimum range of

the acceptance tests, tests of long-term stability and operating

constancy. ^ 3)



PART THE SECOND



THE TRANSPORT OF NUCLEAR MATERIALS AND RADIOACTIVE SUBSTANCES



section 7 of the



Authorization to transport



[To section 9, paragraph 1 (b), m) of the Act]



Permit Office is to be



and for the transport of nuclear materials), with the exception of depleted uranium isotope

235U, if shielding, packaging



(b)) for the transport of radioactive substances to specific forms of activity is higher than the

3,103 values A1 and radioactive substances other than special forms of

the activity higher than 3,103 values A2 or radioactive substances on the

the activity higher than 1000 a TBq, whichever of these values is

the lower,



(c)) for the transport of nuclear materials or radioactive substances in packaging

files of type B (M), which are not designed for a temperature range from

minus 40 ° C to plus 70 ° C or are constructed so that the

to allow controlled intermittent venting;



(d)) to be transported under special conditions, when you cannot meet all of the

the requirements of section 9, and when the following requirements are replaced by specific

the conditions, which ensure that the level of nuclear safety, radiation

protection and physical protection during transport is the same or higher,
(e)) for the transport of special-purpose vessel is laid down by

radiation protection,



(f)) for the transport of nuclear materials or radioactive substances, which

the values of A1 and A2 were determined by calculation.



§ 8



The extent and the way of performing the approval documentation for the authorization to

transport



[To section 13, paragraph 3 (b), (d)) of the Act]



(1) Emergency regulations for transport and transport of nuclear materials and

radioactive substances shall prepare the shipper pursuant to specific legal

Code; ^ 10) this is without prejudice to the obligation of the shipper to have available

the transport documents provided for in specific legislation. ^ 11)



(2) the inclusion of the transport of nuclear materials to the appropriate category

in terms of physical protection shall be carried out according to a special legal

prescription. ^ 12) way to ensure physical protection shall be laid down in the specific

legislation. ^ 12) ^ 13)



(3) If, in the context of international transport of certain part of the transport

transported through the territory of the Czech Republic, necessitates the scope and implementation of the

the documentation referred to in paragraphs 1 and 2 only for that part of the shipment.



§ 9



Transport security, and transport carrier



[To section 20, paragraph 1 (b)), and (d)) of the Act]



(1) for the transport of nuclear materials and radioactive substances according to § 7

shipping agent



and shall notify the Office of departure) 7 days in advance, if not by

special legal regulation ^ 14) unless otherwise specified,



(b)) in the documentation, shall that all cooperation with third

persons in emergency situations. If the emergency order assumes

cooperation with the fire rescue Corps more counties, it shall ensure that

through the Ministry of the Interior-General Directorate of

Fire brigade of the Czech Republic,



(c)) shall, in the documentation, that all documentation in advance to determine the

the participants in the transport were shown to be familiar with the safety regulations,



(d) in the case of radiation accident) or suspected its establishment without delay

the Office shall inform the appropriate operational centre, the police of the Czech Republic,

the relevant operating and information centre fire brigade

and the territorial administrative authority; in both cases, the carrier will send the Office

within 30 days from the occurrence of the event its evaluation in cooperation with the

the carrier,



(e) ensure the physical security of transport) according to a special legal

regulations, ^ 12) ^ 13)



(f)) the relevant requirements specified in annex No. 4, and the requirements of the

specific legislation. ^ 12)



(2) cancelled



PART THE THIRD



THE INTERNATIONAL TRANSPORT OF RADIOACTIVE WASTE



§ 10



The scope and ways of implementation of the international transport of radioactive waste,

documentation for the authorisation and supervision of such transport



[To section 9, paragraph 1 (b), p) and to the point (P) of the annex to the law]



(1) a permit under section 9 (2). 1 (a). p) of the Act, the validity of which can

The Office, the time limit is required for international shipments of radioactive

waste, whose activity and mass activity exceeds the level set by the

a special legal regulation, ^ 2) and for the following types of shipments:



and the Czech Republic) of the Member State of the European Union,



(b)) from a Member State of the European Union to the Czech Republic,



(c)) from the Czech Republic to a State which is not a member of the European Union, including the

transit by the Member States of the European Union,



(d)) from a State which is not a member of the European Union, the Czech Republic, including

transit by the Member States of the European Union,



e) between States, which is not a member of the European Union, with transit through the

the Member States of the European Union, while the Czech Republic is the first Member

State of the European Union, on whose territory the waste enters.



(2) the completed form, specimens of which are given in sections 1, 3 and

4 of annex 6, must be accompanied by the supporting documents, that are transported

together with the radioactive waste.



(3) for permission to carry out the multiple shipments, you can ask one of the applications,

If



and) radioactive waste to which it relates essentially has the same

physical, chemical and radioactive characteristics, and



(b) the transport is carried out) only between the same and the same

the beneficiary and concerns are always the same competent authorities. Holder

radioactive waste is a natural or legal person, that is, before

legally responsible for the implementation of the transport of waste, and intends to carry it

the recipient,



c) transport relating to the Czech Republic, a country which is not a member of the

The European Union is carried out through the same border crossings, if

the consent is not given to other road transport.



(4) in the international transport of radioactive waste referred to in paragraph 1

(a). and)



and the holder of the radioactive waste) shall submit to the Office an application on a form

a specimen of which is set out in section 1 of annex 6, and fill in and confirm the

the form of which a specimen is given in section 4 of annex 6,



(b))



1. Requests the opinion of the competent authorities in the country of destination and of the country or

countries of transit, the form of which a specimen is given in section 2

Annex No 6,



2. the decision on the application for authorisation of the international transport

radioactive waste form, a specimen of which is given in section 3

Annex No 6,



3. an authorization to transport shall inform the competent authorities of the country of destination and the countries of the

transit and applies to form, a specimen of which is given in section 3

Annex No 6,



4. send a copy of the form, a specimen of which is set out in section 5 of annex 6,

that it receives from the competent authority of the country of destination, the holder of the

the radioactive waste.



(5) When the international transport of radioactive waste referred to in paragraph 1

(a). (b))



and the consignee of the radioactive waste to) 15 days after the receipt of the waste, it shall send the

The Office of the completed and certified form of which a specimen is given in section 5

Annex No 6,



(b)) after the receipt of a form, a specimen of which is given in section 5 of annex

No. 6, will send a copy to the competent authorities of the Member States of the European

the Union, which is concerned.



(6) in the international transport of radioactive waste referred to in paragraph 1

(a). (c))



and the holder of the radioactive waste)



1. The Office shall submit the request on a form of which a specimen is given in section 1

Annex No 6,



2. shall ensure that the recipient immediately after the receipt of radioactive waste

posted by the completed and certified form of which a specimen is given in section 5

Annex No. 6, or the Declaration of the same content and stated the customs

the Office, through which the shipment was made,



3. fill in and confirm the form of which a specimen is given in section 4 of annex

No. 6,



4. The Office shall send, within 14 days from delivery of the radioactive waste recipients

form, specimens of which are given in sections 4 and 5 of annex 6. In

If the recipient does not fill in a form, a specimen of which is given in section 5 of the

Annex 6, it fills in the holder of the radioactive waste shall

Declaration by the beneficiary under paragraph 6 (a). and section 2)



(b))



1. requests an opinion from the competent authorities of the Member States of the European

the Union, which is concerned, the form of which a specimen is

listed in section 2 of the annex No 6, and in the case of transport with

the authorities of other countries concerned by the transport operation involves,



2. the decision on the application for authorisation of the international transport

radioactive waste form, a specimen of which is given in section 3

Annex No 6,



3. an authorization to transport shall inform the competent authorities of the countries concerned by the

transportation concerns, and applies to a form, a specimen of which is given in section

3 Annex 6,



4. upon receipt of the forms, of which a specimen is given in sections 4 and 5

Annex No 6, shall send a copy thereof to the competent authorities of the Member States

The European Union, which is concerned.



(7) in the international transport of radioactive waste referred to in paragraph 1

(a). (d))



and the consignee of the radioactive waste)



1. The Office shall submit the request on a form of which a specimen is given in section 1

Annex No 6,



2. ensure that the holder of the radioactive waste to fill out and confirm the

the form of which a specimen is given in section 4 of annex 6,



3. The Office shall send, within 14 days after the receipt of radioactive waste questionnaire and

certified form, specimens of which are given in sections 4 and 5

Annex No 6,



(b))



1. requests an opinion from the competent authorities of the Member States of the European

the Union, which is concerned, the form of which a specimen is

listed in section 2 of the annex No 6, and in the case of transport with

the authorities of other countries concerned by the transport operation involves,



2. the decision on the application for authorisation of the international transport

radioactive waste form, a specimen of which is given in section 3

Annex No 6,



3. an authorization to transport shall inform the competent authorities of the countries concerned by the

transportation concerns, and applies to a form, a specimen of which is given in section

3 Annex 6,



4. upon receipt of the forms, specimens of which are given in sections 4 and 5

Annex No 6, shall send a copy thereof to the competent authorities of the Member States

The European Union, which is concerned.



(8) in the international transport of radioactive waste referred to in paragraph 1

(a). (e))



and the person who will be) responsible for the implementation of the transport on the territory of the Czech

Republic, shall submit to the Office an application on the form of which a specimen is given in

section 1 of the annex No 6,



(b) the holder of the authorization)



1. ensure that the holder of the radioactive waste to fill out and confirm the

the form of which a specimen is given in section 4 of annex 6,
2. shall ensure that the recipient immediately after the receipt of radioactive waste

posted by the completed and certified form of which a specimen is given in section 5

Annex No. 6, or the Declaration of the same content and stated the customs

the Office, through which the shipment was made,



3. The Office shall send, within 14 days from delivery of the radioactive waste recipients

form, whose designs are listed in sections 4 and 5 of annex 6. In

If the recipient does not fill in a form, a specimen of which is given in section 5

Annex 6, it fills in the holder of the radioactive waste shall

Declaration by the beneficiary under paragraph 8 (a). (b)), section 2



(c))



1. requests an opinion from the competent authorities of the Member States of the European

the Union, which is concerned, the form of which a specimen is

listed in section 2 of the annex No 6, and in the case of transport with

the authorities of other countries concerned by the transport operation involves,



2. the decision on the application for authorisation of the international transport

radioactive waste form, a specimen of which is given in section 3

Annex No 6,



3. an authorization to transport shall inform the competent authorities of the countries concerned by the

transportation concerns, and applies to a form, a specimen of which is given in section

3 Annex 6,



4. upon receipt of the forms, specimens of which are given in sections 4 and 5

Annex No 6, shall send a copy thereof to the competent authorities of the Member States

The European Union, which is concerned.



(9) If the authority is the authority that decides on the application for authorisation to

international transport, but transport of the Czech Republic is concerned, it shall notify the

not later than two months after receipt of the request to the competent authority of its

consent or of the conditions of transport on our territory, where appropriate, the reason for

not giving consent. This makes use of a form, a specimen of which is given in the

section 2 of the annex No 6. For consideration of the application, the Office may request it's longer

period not exceeding one month. If the Office until the expiry of the

time limits deemed that it gave its approval to the transport.



§ 11



Common and transitional provisions



(1) Packaging the files listed in section 2 (2). 1 (a). and) and produced before the

effect of this Decree may be used until 31 December 2004. December 2003. After

This date may be used only if their technical implementation

complies with the limitations of the activity and material restrictions laid down in annex No.

3 and in addition to the requirements referred to in paragraph 86. Part I of annex 1,

If they are intended for the carriage of nuclear materials.



(2) Radioactive Substances of a specific form of type-approved before the effective

may be carried until 31 December 2006. December 2003. After this date may only be

as the only radioactive substances, other than special form.



(3) radioactive substances with a little rozptýlitelností type-approved before

effect may be carried until 31 December 2006. December 2003. After this date,

may only be transported as radioactive substances other than with a small

rozptýlitelností.



(4) the Sources of ionizing radiation of the type-approved before the effectiveness of this

the order, whose parameters and operating characteristics meet the requirements

tests of long-term stability under special legislation ^ 3) and

which has not expired as provided for by the manufacturer, the period of application, in terms of

radiation protection considered to be satisfactory. Sources of ionizing radiation, in

which has not been determined, the expiry date may be used until 30. June

2007, unless under special legislation ^ 3) unless otherwise specified.



§ 12



Cancellation provisions



Shall be deleted:



1. Decree No. 142/1997 Coll., on the type approval of packaging

for transport, storage or storage of radionuclide emitters and

nuclear materials, type approval of ionizing radiation sources,

type approval of protective equipment for work with sources of ionizing

radiation and other devices to work with them (the type approval)



2. Decree No. 142/1997 Coll., on transport and the transport of specified nuclear

materials and specified radionuclide emitters.



section 13



The effectiveness of the



This Decree shall take effect on the date of its publication, with the exception of section 10, which

shall take effect on the date of the Treaty of accession of the Czech Republic to

The European Union enters into force. The provisions of section 9 (2). 2 shall apply until the date of

Treaty of accession of the Czech Republic to the European Union in

force.



Chair:



Ing. In r. Drábová.



Annex 1



The requirements and test procedures for type approval



PART I



REQUIREMENTS ON FISSILE MATERIALS, RADIOACTIVE SUBSTANCES, PACKAGING FILES, AND

RADIOACTIVE SHIPMENTS



REQUIREMENTS FOR RADIOACTIVE SUBSTANCES



The requirements for radioactive material with low weight activity



1. (226.) *) The substance with low weight activity (LSA) is a radioactive

the substance, which is by its nature limited mass activity or

radioactive substance, whose average weight was intentionally activity

limited. External shielding materials that a substance with low weight

surround activity to determine the average weight of the activity

involved.



The Group of LSA-I includes:



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

containing naturally occurring radionuclides which are intended to

processing for use of these radionuclides,



(ii) hard neozářený natural uranium or depleted uranium or natural

thorium or their solid or liquid compounds or mixtures



(iii) radioactive material for which the A2 value is unlimited, except

fissile material in quantities which are not exempted from the requirements of the

fissile materials referred to in paragraph 78. Part I of annex 1,



(iv) other radioactive material in which the activity is completely dispersed

and provided for the average activity per unit mass do not exceed 30 times what

the values referred to in paragraphs 1. up to 6. Annex No. 3, with the exception of fissionable

material in quantities which are not exempted from the requirements for radioactive

consignments containing fissile materials referred to in paragraph 78. Part I of the annex.

No 1.



The Group of LSA-II includes



(i) water with tritium concentration up to 0.8 a TBq/l;



(ii) other substances, in which the activity is completely dispersed and provided for

the average activity per unit mass of not more than the values of 10E-4 A2 on 1 g

solids and 10E-5 A2 values to 1 g liquid.



The Group of LSA-III includes solids with the exception of the pills, in which

at the same time:



(i) radioactive substance is completely dispersed in solid substance or in fixed

objects, or is essentially uniformly dispersed in a compact pojivé

substance as such. concrete, bitumen, ceramic, etc.



(ii) the radioactive substance is relatively insoluble, or it is bound in the

relatively nerozpustném substrate, so even in the case of loss of the packaging

file, the loss of radioactive substances from one container

extraction in water for seven days does not exceed 0.1 A2,



(iii) the average mass activity solids without a facility

the material does not exceed 2. 10E-3 A2/g.



The requirements for radioactive material with low weight activity group

LSA III



2. (601). LSA Group III radioactive substance must be a solid,

of such a nature that, after exposure to the full content of the packaging file test

referred to in paragraph 3. Part II. Annex No 1, does not exceed the activity in

water value 0.1 A2.



Requirements for special form radioactive material



3. (239.) Special forms of radioactive substance is either a fixed

nerozptýlitelná radioactive substance or a sealed pouch,

containing radioactive material.



4. (602). Special forms of radioactive substance must have at least one

dimension is greater than 5 mm.



5. (603.) Special forms of radioactive substance must be of such a nature

or must be made so that after testing carried out in accordance with paragraphs

4.-11. Part II. Annex No 1, satisfy the following requirements:



(and) doesn't break or nerozdrtí during the tests for impact, pressure and bending

in accordance with paragraphs 5., 6., 7., 9. (a) part II. Annex No 1,



(b) melt, or clears when the thermal tests

as specified in paragraph 8. or paragraph 9. (b) part II. Annex No.

1,



(c) water activity in the determination of the leaching ability referred to in paragraph 10. and

11. part II. Annex No 1 does not exceed 2 kBq; or in the case of sealed sources

speed escape a volumetric test volumetric leakage assessment,

specified in the publication, international organization for Standardization:

"Radiation protection-sealed radioactive sources-test methods

leaks, ISO 9987:1992 (E), ISO, Geneva, 1992 ", do not exceed the

limit fixed by the Office.



6. (604). If it is part of the special form radioactive material

Hermetic box must be made so that it can be open

only destruction.



The requirements for radioactive material with little rozptýlitelností



7. (225.) Radioactive substance with a little rozptýlitelností is a radioactive

the substance in solid, solid state is not powder

form, either by itself or in a closed housing, the substance must be

limited ability to disperse.



8. (605). Radioactive substance with a little rozptýlitelností must be such

nature to the total quantity of the radioactive substances in the consignment fulfils the

the following requirements:



(a) the value of the input of the dose equivalent at a distance of 3 m from the

unshielded radioactive substances must not exceed 10 mSv/h
(b) after the tests specified in paragraphs 36. and 37. Part II.

Annex No 1, not activity released in the form of gaseous or aerosol

particulate matter exceed, up to the equivalent of the average 100 wind

those 100 A2 value, for each test can be used with a special pattern,



(c) after the test referred to in paragraph 3. Part II. Annex No 1,

the activity in the water may not to exceed 100 A2. This test must be

taken into account the damage as a result of the tests referred to in paragraph (b).



General requirements for all packaging files and the radioactive shipments



9. (231.) Packaging the file the file is the packages necessary to complete

the conclusion of the radioactive contents. While the radioactive contents are fissile

material or radioactive substance with all contaminated or

activated solid, liquid substances and gases inside

the packaging file. The packaging file can consist of one or more

packaging materials, absorption, distance, shielding structure elements

auxiliary devices for the filling and emptying, venting and reduction

pressure, cooling devices, shock, impact and handling equipment

mounting, thermal insulating elements, and also for the maintenance of the equipment and

repair of the entire container. Packaging file can be a box, sud

or similar container or shipping container, tank or intermediate

container for bulk cargo.



10. (230.) Radioactive shipment is packing the file, including its

radioactive content as it is passed to the transport. The different types of

radioactive shipments which are subject, shall comply with the limits

activities and material restrictions laid down in annex No 3 and the corresponding

the requirements set out in annex 1. Types of radioactive consignments



(a) that the consignment;



(b) the industrial shipment of type 1 (type IP-1);



(c) the industrial shipment of type 2 (type IP-2);



(d) industrial consignment type 3 (type IP-3);



(e) the shipment of type (type A);



(f) the shipment of type B (U) (type B (U));



(g) the shipment of type B (M) (type B (M));



(h) the shipment of type C (type C).



Note



Radioactive shipment containing fissile material must comply with the other

the requirements referred to in paragraph 77. -82. Part I of Annex No. 1.



Radioactive shipment containing uranium hexafluoride shall meet the other

the requirements of paragraph 35. -38. Part I of Annex No. 1.



11. (606.) Radioactive shipment must be made so that it was

can be easily and safely transported with regard to its mass, volume and

shape. In addition, they must be made so that it was possible in the transport

resource in the course of properly secured.



12. (607). Structural type of radioactive consignments must ensure that

any clamping device for packaging a file function, if the

used in the manner prescribed by the manufacturer and that in case of failure of this

radioactive device shipment meets the other requirements laid down

This Decree. The design type shall comply with the relevant safety

factors for the case of the lifting of the radioactive cargo market.



13. (608). Clamping device and any other fasteners on the outer

surface radioactive consignments, which can be used to

lifting must be manufactured so as to keep her weight in accordance with the

the requirements referred to in paragraph 12. Part I of Annex No. 1, otherwise,

must be removed, or otherwise put out of function for the duration of the transport.



14. (609.) Packaging the file must be made without exiting parts

the external surface so that it can be easily decontaminated, if by

not limited to important safety requirement.



15. (610). The outer surface of the radioactive shipments must be made so that the

the sole and was outside the water, if it was not limited

important safety requirement.



16. (611) Any equipment being transported with radioactive shipment,

that is not a part of it, shall not reduce its safety.



17. (612). Radioactive shipment must be able to withstand the effects of the

acceleration, vibration or resonance of vibration that may occur

under the conditions foreseeable under normal conditions of transport, shall not be

reduced the effectiveness of the closing device of the various containers of radioactive

consignment or may not violate its integrity as a whole.

In particular, nuts, bolts and other locking devices shall be made

so, in order to prevent their accidental release or loss, and even

with repeated use.



18. (613). Packaging materials and any of its parts must

be to each other and to the radioactive contents of the consignment, physically and chemically

compatible. Physical and chemical compatibility must be maintained for

all materials, even after exposure.



19. (614). All the closures, which could leak radioactive content,

must be secured before the uncontrollable unauthorized use.



20. (615). Construction of the radioactive shipments must comply with the temperatures and

the pressures of the external environment, which may occur in normal conditions

transport.



21. (616) For fissile materials or radioactive substances that exhibit

other hazardous properties shall comply with these type of construction

hazardous properties, see paragraph 7 of the annex No. 4.



Additional requirements for radioactive shipments transported by air



22. (617.) The temperature of the accessible surfaces of the radioactive shipments

transported by air shall not exceed 50 ° C at an ambient temperature of 38

St C, account to the sunlight.



23. (618.) Radioactive shipments transported by air shall be made

so that in the event of exposure to temperatures from minus 40 ° C to 55 ° C

not impaired the integrity of the kontejnmentového (restraint)

the system. The designer designed and described the arrangement of the parts of the packaging

the file must prevent leakage of fissile material or radioactive substances

during transport.



24. (619.) Radioactive shipments containing fissile materials or

radioactive substances shall be provided with a restraint for air transport

a system that will prevent leakage when the external pressure to 5 kPa.



Requirements for exempt consignments



25. (620). Cut the consignment must be made so as to meet the

the requirements specified in paragraphs 9. -21. Part I of Annex No. 1, and

In addition, the requirements referred to in paragraph 22. -24. Part I of Annex No. 1, if

they are transported by air.



The requirements for industrial shipments



The requirements on the industrial shipment of type 1 (IP-1)



26. (621) Industrial consignment type 1 (IP-1) must be made so that the

comply with the requirements specified in paragraphs 9. -21. Part I.

Annex No 1, and in addition to the requirements referred to in paragraphs 22. -24. Part I.

Annex No 1, if they are transported by air.



The requirements on the industrial cargo type 2 (IP-2)



27. (622.) The industrial shipment of type 2 (IP-2), must be made so that the

comply with the requirements of the industrial shipment of type 1 (IP-1), specified by the

in paragraph 26. Part I of Annex No. 1 and, in addition, if examined by

paragraphs 22. and 23. Part II. Annex No 1, must prevent



(a) the loss or dissipation of the radioactive contents, and



(b) loss of shielding effectiveness, which would cause greater than a 20% increase

input of the dose equivalent, in any place of its external

surface.



The requirements for industrial consignment type 3 (IP-3)



28. (623). Industrial consignment type 3 (IP-3) shall be made to

comply with the requirements of the industrial shipment of type 1 (IP-1), specified by the

in paragraph 26. Part I of Annex No. 1 and in addition to the requirements specified in the

paragraphs 34. -47. Part II. Annex No 1.



Requirements for radioactive shipments classified as industrial shipments

Type 2 (IP-2) and type 3 (IP-3)



29. (624.) Radioactive shipments may be used as industrial

cargo type 2 (IP-2) and type 3 (IP-3), provided that:



(a) meet the requirements of the industrial shipment of type 1 (IP-1),

specified in paragraph 26. Part I of annex 1,



(b) are made in order to meet the standards prescribed in chapter

General recommendations on packing in the UN publication "recommendations on the transport of

dangerous goods, ninth revised edition, ST/SG/AC 10/1/Rev. 9,

UN, New York and Geneva, 1995 "or other standards, which are those

at least equivalent and



(c) carried out the tests required for packing group I and II

According to the chapter general recommendations for packing in the publication of the UNITED NATIONS

"Recommendations for the transport of dangerous goods, ninth revised edition,

ST/SG/AC 10/1/Rev. 9, UN, New York and Geneva, 1995 ", must prevent:



(i) loss or dissipation of the radioactive contents, and



(ii) loss of shielding effectiveness, which would cause greater than a 20% increase

input of the dose equivalent, in any place of its external

surface.



30. (625). As the industrial cargo type 2 (IP-2) and type 3 (IP-3)

be used in tank containers, provided that:



(a) meet the requirements of the industrial shipment of type 1 (IP-1),

specified in paragraph 26. Part I of annex 1,



(b) are made in order to meet the standards prescribed in chapter

General recommendations on packing in the UN publication "recommendations on the transport of

dangerous goods, ninth revised edition, ST/SG/AC 10/1/Rev. 9,

UN, New York and Geneva, 1995 ", or other equivalent standards and must
be able to resist a test pressure of 265 kPa, and



(c) are made so that any additional shielding which is provided with

will be able to withstand the static and dynamic tension arising from the

handling under normal conditions of transport and of preventing a loss of shielding

capabilities leading to greater than 20% increase in the input of a batch

equivalent to any point of the outer surface of the tank used

container.



31. (626). Tanks, other than tank containers can be used

as the industrial cargo type 2 (IP-2) and type 3 (IP-3) for transporting LSA I

and the LSA II in the form of gaseous or liquid, as prescribed in table 1

(IV) in annex No. 4, provided that they satisfy the equivalent

the standards, which are listed in paragraph 30. Part I of Annex No. 1.



32. (627) Shipping containers can be used as industrial

cargo type 2 (IP-2) and type 3 (IP-3), provided that:



(a) radioactive content will be limited to solids;



(b) the requirements on the industrial cargo type IP-1 specified in the

paragraph 26. Part I of Annex No. 1 and



(c) are made in order to meet the standards prescribed in the document

International Organization for Standardization: "series 1 containers

-Specification and testing-part 1: General cargo containers,

ISO1496:1, 1990 (E), ISO, Geneva, 1992 ", with the exception of the dimensions. Must be

made to made to the tests prescribed in that

the document and the corresponding acceleration normal transport conditions

prevent:



(i) loss or dispersal of the radioactive contents,



(ii) loss of shielding effectiveness, which would cause greater than a 20% increase

input of the dose equivalent at any point, the outer surface of the

the shipping container.



33. (224.) Medium size container for bulk cargo is

portable packaging file



(a) does not have the inner content of more than 3 m3,



(b) is designed for mechanical handling;



(c) is resistant to the loads resulting from the handling and transport as

It was verified the tests,



(d) is designed in accordance with the standards in chapter recommendations for

medium-sized containers on bulk (IBC) in your publication

The UNITED NATIONS ' recommendations on the transport of dangerous goods, ninth revised

release, ST/SG/AC 10/1/Rev. 9, UN, New York and Geneva, 1995 ".



34. (628) Metal containers of medium size on a bulk carrier

may be used as industrial cargo type 2 (IP-2), and type 3

(IP-3), where:



(a) fill the requirements for industrial cargo type IP-1 specified in the

paragraph 26. Part I of annex 1,



(b) are made in order to meet the standards prescribed in chapter

Recommendations for a medium-sized containers for packing group I and

(II), in the UNITED NATIONS publication "recommendations on the transport of dangerous goods, ninth

Revised Edition, ST/SG/AC 10/1/Rev. 9, UN, New York and Geneva,

1995 "and carried out the tests specified in this document, with

the exception of stall tests the most detrimental manner,

prevents:



(i) loss or dispersal of the radioactive contents,



(ii) loss of shielding effectiveness, which would cause greater than a 20% increase

input of the dose equivalent, in any place of the outer surface of the

the shipping container.



Requirements for radioactive shipments containing uranium hexafluoride



35. (629) Except as permitted in paragraph 38. Part I of annex 1,

uranium hexafluoride shall be packaged and transported in accordance with the publication

International Organization for Standardization: "Packaging files for transport

hexafluoridu uranium ISO 7195:1993, E, ISO, Geneva, 1993 ", and with the requirements of

paragraphs 36. -37. Part I of Annex No. 1. Radioactive shipment must

at the same time comply with all requirements that apply to the radioactive

and the fissile properties of this substance.



36. (630). Each radioactive shipment of design to content 0.1 kg or

more hexafluoridu of uranium must be constructed so as to meet the following

requirements:



(a) without leakage test unacceptable load, according to the

the specifications contained in the publication of the International Organization for

Standardization: "Packaging for the transport of uranium hexafluoridu files ISO

7195:1993, E, ISO, Geneva, 1993 ", the static test specified in

paragraph 18. Part II. Annex No 1,



(b) without loss or dispersal of the uranium test hexafluoridu

specified in paragraph 22. Part II. Annex No 1,



(c) without tearing the restraint system to comply with the test specified in

paragraph 28. Part II. Annex No 1.



37. (631). Radioactive shipment content design on 0.1 kg or more

hexafluoridu uranium, must not be fitted with devices to reduce the pressure.



38. (632). Radioactive shipment content design on 0.1 kg or more

hexafluoridu of uranium, may be transported after the approval by the authority,

If:



(a) is designed according to the other requirements than are contained in the

the publication International Organization for Standardization: "Packaging files

for the transport of uranium hexafluoridu ISO 7195:1993, E, ISO, Geneva, 1993 ", and

paragraphs 36. -37. Part I of annex., but meets the applicable

extent of the requirements referred to in paragraphs 36. -37. Part I of annex 1,



(b) is designed so that no escape act test on unacceptable

load test pressure in MPa 2.76 referred to in paragraph 18. Part II.

Annex No 1, or,



(c) is projected on the contents of 9000 kg or more of uranium and hexafluoridu

doing so does not meet the requirements referred to in paragraph 36. (c) of part I of annex.

1.



Requirements for radioactive cargo type and



39. (633.) Radioactive shipment type and must be made so that the

comply with the requirements specified in paragraphs 9. -21. Part I of the annex.

No. 1, also in case of air transport, the requirements referred to in paragraphs 22. -

24. and paragraphs 40. -55. Part I of the annex No. 1.



40. (634) Any external dimension of radioactive consignments shall not be less

than 10 cm.



The smallest overall external dimension of radioactive consignments shall not be less than

10 cm.



41. (635) The cap on the outer surface of the container must be

secured in such a way that the seal or the seal could not be simply

broken; intact seal is evidence that the consignment has not been opened.



42. (636). Any fasteners radioactive shipments must be made

so, in order to force emerging in these příchytkách under normal conditions

transport and accident conditions in transport should not distort the ability to

radioactive shipments comply with established requirements.



43. (637). Structural type of radioactive consignments shall for each

component packaging comply with the exposure to temperatures from minus 40

St C to plus 70 ° C. Special attention must be paid to low

temperatures in the case of liquid contents and a potential depreciation of the

packaging materials in the given temperature range.



44. (638) The design and type of the material processing technology and production

packaging must be in accordance with the way of ensuring the quality

under special legislation) or international standards

acceptable to the authority.



45. (639). Design type must contain the sealing restraint

the system, which cannot be opened accidentally or as a result of pressure, which

may arise in the radioactive shipment.



46. (640). Special forms of radioactive substance can be considered

part of the restraint system.



47. (641) If the restraint system consists of a special unit of radioactive

consignments shall be securely closed mechanism independent of the

any other components of the radioactive cargo.



48. (642). Any part of a restraint system, the project must take into account,

radiolytic decomposition of liquids and other volatile substances and the formation of gas

chemical reactions and radiolýzou.



49. (643) Restraint system must keep the radioactive contents in a reduction

the external pressure to 60 kPa.



50. (644). All valves, with the exception of the insurance, shall be equipped with

the CAP, which will prevent any leakage.



51. (645.) Shielding, which closes part of radioactive shipments

specified as part of the restraint system must be constructed,

to prevent the accidental leakage of this part of the shielded space.

If the radiation shielding of the special drive, this drive must be

safely sealed shut-off mechanism independent of any

other parts of the container file.



52. (646.) Radioactive shipment must be made so that the

carried out the tests specified in paragraph 19. -24. Part II.

Annex No 1, prevent:



(a) loss or dispersal of the radioactive contents,



(b) loss of shielding effectiveness, which would cause greater than a 20% increase

input of the dose equivalent, in any place of the outer surface of the

radioactive shipments.



53. (647.) Structural type of radioactive consignments intended for liquid

fissile materials or radioactive substances must be his design

to respect changes in the volume of content and the free space in the packaging file in

Depending on the temperature changes, the dynamic phenomena and dynamics of performance.



54. (648) Radioactive shipment of type A, designed for liquids must

In addition:



(a) to comply with the conditions referred to in paragraph 52. Part I of Annex No. 1 and

After performing the tests specified in paragraph 25. Part II.

Annex No 1 must:
(i) contain plenty of absorbčního material, which absorbed at least

dual volume of liquid radioactive content and this absorption

the material must be suitably located, that has been in contact with the liquid in the

If it leaks, or



(ii) have installed restraint system composed of primary inner and

the secondary external parts that are made so as to ensure that the

the detention of the liquid content within the secondary outer part, even if

the primary internal part is leaky.



55. (649) Radioactive shipment type, designed for gases shall

prevent the loss or dissipation of the radioactive contents, for the test

carried out in accordance with paragraph 25. Part II. Annex No 1. Radioactive

shipment type and designed for tritium, or for the rare gases, this

comply with the requirement may not.



Requirements for radioactive consignments of type B (U)



56. (650.) Radioactive shipment of type B must be made so that the

comply with the requirements specified in paragraphs 9. -21. Part I of the annex.

No. 1, also in case of air transport, the requirements referred to in paragraphs 22. -

24. and paragraphs 40. -55. Part I of the annex No 1, with the exception of the specification in the

paragraph 52. (a) in part I of Annex No. 1 and in addition to the requirements of paragraphs 57. -

70. section I of Annex No. 1.



57. (651). Radioactive shipment must be made so that the heat

produced by radioactive shipments inside its content when the external

the conditions specified in paragraphs 59. and 60. Part I of Annex No. 1

and under normal conditions of carriage, as specified in paragraph 19. -

24. part II. Annex No 1, negatively affect the radioactive shipment

in such a way that it would not fulfill the requirements for restraint and

shielding if left unattended will be one week. Special

attention must be paid to the effects of heat, which may:



(a) to change the arrangement, the geometrical form or physical state

radioactive content, or if the fissile material or

radioactive substance sealed in packaging or a container (such as coverage

fuel) cause deformation of the container or packaging or directly

the radioactive contents or these melt, or



(b) reduce the efficiency of the packaging through differential

thermal expansion or cracking or melting down of shielding material, or



(c) in combination with humidity accelerate corrosion.



58. (652) With the exception of the request referred to in paragraph 22. Part I of annex.

1 the radioactive consignments intended for carriage must be

radioactive shipment made so that when the external conditions

specified in paragraphs 59 and 60. Part I of Annex No. 1 to the maximum

the temperature on any part of an accessible surface radioactive shipments

does not exceed 50 ° C, with the exception of radioactive consignments for transport

the terms of the exclusive use.



59. (653) Outside (ambient) temperature means a 38 ° C.



60. (654.) Conditions of solar irradiance and its values intended for use

are described and defined in table 1. (XI.).



Table 1. (XI) the value of the exposure of the Sun

+------------------------------------------+-----------------------+

| The shape and location of the surfaces | The exposure from the Sun for |

| 12 hours per day (W/m2) |

+------------------------------------------+-----------------------+

| Flat surfaces transported horizontally | |

|-Base-| No |

|--other surfaces | 800 |

+------------------------------------------+-----------------------+

| Flat surfaces not transported horizontally | |

| -all surfaces | 200a) |

+------------------------------------------+-----------------------+

| Curved surfaces | 400 |

+------------------------------------------+-----------------------+



and, Alternatively, may be to) the calculation of the sine function is used together with the

adopted by the absorption coefficient, and the possible effects can be neglected

reflections from the surfaces of adjacent objects.



61. (655). Radioactive shipment, part of which is thermal protection,

designed to meet the requirements referred to in paragraph 28. Part II. Annex

No. 1, must be designed so that this protection was effective, even after

the tests specified in paragraph 19. -24. and

27. (a) or (b) and 27 (c) of part II. Annex No 1. No such

protection of the outer surface of the radioactive cargo must not be excluded from the

the activities of the perforation, cutting through, smýknutím, abrasion or rough

treatment.



62. (656.) Radioactive shipment of type B must be made so that the

meet:



and the tests described in paragraphs) 19. -24. Part II. Annex No 1 and

loss of radioactive contents to no more than 10E-6 A1 per hour and



(b)) tests as described in paragraphs 26, 27 and 30. (b), 28. and 29. Part II.

Annex No 1 and tests:



(i) referred to in paragraph 27. (c) part II. Annex No 1, if

the weight of the radioactive cargo is less than 500 kg, and the total density

established on the basis of the external dimensions shall not exceed 1000 kg/m3 and the value of the

the activity of the radioactive contents is not more than 1000 A2, but not in the case of

special forms of radioactive substances, or



(ii) referred to in paragraph 27. (a) part II. Annex No 1 for all

other radioactive cargo,



(c) the following requirements:



(i) maintain sufficient shielding to ensure that the batch input

equivalent in distance of 1 m from the surface of the container is less than

10 mSv/h at a maximum radioactive contents, for which the radioactive

the consignment is designed,



(ii) limit the total loss of radioactive contents to no more than a week

10 A2 for krypton-85 and not more than A2 for all other radionuclides.



Note



If it is a mixture of different radionuclides, one must use the provisions in the

paragraphs 4. -6. Annex 3 with the exception of krypton-85, when it is possible to

use the effective value of the A2 (i) equal to 10 A2. For case (a) referred to

above, must also be taken into account in the value of external contamination of the

paragraph 8. Annex No. 4.



63. (657) Designed for the transport of radioactive shipment

the radioactive contents with activity greater than 10E5 A2 must be made

so that when the extended test of dipping into the waters referred to in paragraph 30.

Part II. Annex No 1 to avoid tearing of the restraint system.



64. (658) Compliance with the permitted limits of escape activity must not be dependent

even on the filters, nor on the mechanical cooling system.



65. (659) Radioactive shipment must not contain in restraint

locking pressure system, which would be under the conditions of the tests referred to in

paragraphs 19. -24. and 26. -29. Part II. Annex No 1 to allow for escape

radionuclides into the environment.



66. (660). Radioactive shipment must be made so that even in the case of

maximum normal operating pressure in carrying out the tests referred to

in paragraph 19. -24. and 26. -29. Part II. Annex No 1 has not reached the

tensions in the restraint of the values that have influenced it enough so that it would

did not meet the requirements of not him asked.



67. (661). Radioactive shipment must not have a maximum normal operating

pressure greater than 700 kPa.



68. (662) With the exception of the request referred to in paragraph 22. Part I of annex.

1 the radioactive shipments carried by air, the maximum temperature

on any part of an easily accessible surface radioactive consignments when

normal conditions of transport, without exposure to the Sun when the external

the conditions specified in paragraph 59. Part I of annex 1,

shall not exceed 85 ° C maximum temperature exceeds. If a 50 ° C,

radioactive shipment is transported under the conditions of an exclusive use

specified in paragraph 58. Part I of Annex No. 1. For the protection of

transport workers can count on barriers or walls, while

These barriers need not be tested.



69. (663) Radioactive shipment containing radioactive substance, with a small

rozptýlitelností must be designed so that any device

attached to a radioactive substance with a small rozptýlitelností, which are not

part of it, or any of the components of the packaging file do not affect the

negative properties. radioactive substances with little rozptýlitelností.



70. (664.) Radioactive shipment must be made for the interval surrounding

temperatures from minus 40 ° C to plus 38 ° C.



Requirements for radioactive consignments of type B (M)



71. (665) Radioactive shipment of type B (M) shall comply with the requirements of the

radioactive shipment of type B (U) referred to in paragraph 56. Part I of the annex.

No 1, with the exception of the requirements for radioactive shipments intended for the transport of

inside of that State, or only between certain States, unless the competent

the authority of the State concerned or the authorities of those States agree with changing requirements

compared to those that are listed in paragraphs 43, 59. -60. and 63. -70.

Part I of Annex No. 1. Requirements for radioactive consignments of type B (U)

referred to in paragraphs 63. -70. Part I of annex 1 are to be met,

If it is technically feasible.



72. (666.) Periodic ventilation of radioactive consignments of type B (M)

Maybe, if the relevant competent authorities enabled.



Requirements for the radioactive shipment type C



73. (667) Radioactive shipment of type C must be made so that the

comply with the requirements specified in paragraphs 9. -21., paragraphs 40

-53. with the exception of the specifications in paragraph 52. (a) the requirements of paragraphs and
57.-70. and in addition to the requirements of paragraphs 74. -76. Part I of Annex No. 1.



74. (668) Radioactive shipment of type C after thermal test carried out in

environment with a defined thermal conductivity 0.33 W/(m K) and a temperature of 38

° C in the steady state, your design must meet the

the evaluation criteria prescribed for tests in paragraphs 62. (b) and 66.

Part I of Annex No. 1. Initial conditions must be based on the evaluation of the

provided, that any thermal insulation of the radioactive cargo remains

intact at the maximum normal operating pressure and ambient temperature of 38

St. (C).



75. (669) Radioactive shipment of type C must be made so that when the

maximum normal operating pressure of the Act:



(a) the tests specified in paragraph 19. -24. Part II. Annex No.

1, limiting the loss of radioactive contents of less than 10-6 A2 per

an hour,



(b) the tests specified in paragraph 34. Part II. Annex

No. 1, where:



(i) its shielding must ensure the maintaining of the input of the dose equivalent in the

the distance of 1 m from the surface of the radioactive shipments so as not to exceed 10

mSv/h, when the maximum radioactive contents, for which it is designed,



(ii) restrict the accumulated loss of radioactive must content for the period

one week to less than 10 A2 for krypton-85 and A2 for all other

radionuclides.



Note



If it is a mixture of different radionuclides, one must use the provisions in the

paragraphs 4. -6. Annex 3 with the exception of krypton-85, when it is possible to

use the effective value of the A2 (i) equal to 10 A2. For case (a) referred to

above, must also be taken into account in the value of external contamination of the

paragraph 8. Annex No. 4.



76. (670.) Radioactive shipment of type C must be made so that the

perform advanced testing by immersion in water as specified in paragraph

30. part II. Annex No 1 to avoid breakage of the restraint system.



Requirements for radioactive shipments containing fissile material



77. (671). Fissile materials are uranium-233, uranium-235,

plutonium-239, plutonium-241, and material containing one or more of the

These radionuclides, with the exception of unirradiated natural uranium and

depleted uranium or natural uranium and depleted uranium, which were

exposed only in thermal reactors, must be transported to:



(a) maintain the status podkritický during normal conditions of transport, even for

the conditions of the accident, to keep the podkritického State must be considered

in particular, the following factors:



(i) the water coming into the radioactive shipments or escaping from it,



(ii) the loss of efficiency of built-in neutron or absorbátorů

Moderators



(iii) change the geometric arrangement of the contents either within the radioactive

consignment or as a result of the loss of part or all of the content of radioactive

the consignment,



(iv) reduce the distance spacing between radioactive consignments or

inside the radioactive cargo,



(v) radioactive consignments of ponořující into the water, or slumping into the

snow and



(vi) temperature changes;



Note



In general it can be stated that the fissile materials contain within itself and special fissile

materials pursuant to section 2 (a). j) point 1. BB) of the Atomic Act and in addition,

plutonium-241.



Fissile materials referred to in paragraph 77. of this annex, unlike

special fissile materials according to the Atomic Act, do not include the additional

isotopes of uranium, which are contained in uranium enriched in the isotopes uranium-233

or uranium-235.



(b) that the requirements have been met:



(i) paragraph 40. Part I of Annex No. 1 for fissile materials contained in

radioactive shipments,



(ii) concerning radioactive fissile material properties,

prescribed in this Decree and anywhere



(iii) specified in paragraphs 79. -88. Part I of Annex No. 1, with

the exception in paragraph 78. Part I of Annex No. 1.



Exceptions from the requirements for radioactive shipments containing fissile material



78. (672) fissile material meeting one of the conditions referred to in (a)-

(d) this paragraph is exempt from the requirement to be transported in

radioactive shipment fulfilling requirements of paragraphs 79. -88. Part I.

Annex No 1 as well as other requirements that apply to fissile

the materials. In the context of a single shipment may be claimed only one

exception.



(a) the shipment must not contain beryllium nor deuterium in quantities

exceeding 0.1% of the mass of fissile material. The weight limit on the

the supply is determined by the equation below:

The mass of uranium-235 (g) + weight of the other fissile material (g) < = 1,

------------------------ -----------------------------------------

X Y



where X and Y are the mass limits defined in table 2. (XII.)

provided that:



(i) each individual radioactive shipment contains a maximum of 15 g

fissile material as bulk material, this weight limit

applied to the shipment on one means of transport, or



(ii) fissile materials are homogeneous aqueous solutions or mixtures thereof,

where the ratio of fissile nucleons to hydrogen is less than 5% by weight,

or



(iii) contains a maximum of 5 g of fissile material in any

desetilitrovém volume



(b) uranium enriched to a maximum of 1. % uranium-235, and with a total

the contents of the plutonium and uranium-233 or below 1. % uranium-235 for the

provided that the fissile material is distributed quite homogeneously throughout the

volume. In addition, if uranium-235 in the form of metal, oxide or carbide,

shall not be arranged in the shape of bars,



(c) liquid solutions of uranyl nitrate with uranium enriched to a maximum of

2 materials. % uranium-235, with total plutonium and uranium-233 may not

exceed 0.002% of the mass of uranium, and the minimum ratio of the number of atoms of nitrogen

to the number of atoms of uranium (N/U) must be 2,



(d) radioactive plutonium shipment containing a total of individually

the weight of more than 1 kg, not more than 20% by weight of plutonium

may be composed of isotopes Pu-239, Pu-241, or any combination of these

radionuclides.



Table 2. (XII) the weight limits for the delivery for the removal of the requirements on

radioactive shipments containing fissile material

+---------------------+-------------------------------+------------------------------+

| Fissile material | Weight of fissile material | Weight of fissile material |

| | (g) mixed with substances having | (g) mixed with substances having |

| the average hydrogen density | | average hydrogen density |

| numbers less than or equal | density is higher than the density of the atoms ' | ' |

| the hydrogen atoms in the water ' | | hydrogen atoms in the water |

+---------------------+-------------------------------+------------------------------+

| Uranium-235 (X) | 400 | 290 |

| Other fissile | | |

| materials (s) | 250 | 180 |

+---------------------+-------------------------------+------------------------------+



The specification of the contents for the assessment of radioactive consignments

fissile materials



79. (673) If they are not known to the chemical or physical form, isotopic

composition, mass or concentration, moderation ratio or density, or

geometrical configuration, you must perform the assessment referred to in paragraphs 83.

-88. Part I of Annex No. 1 with the default assumption that each parameter

whose value is not known has the value which leads to the maximum

neutron multiplication corresponding to the known conditions and parameters in these

Guest.



80. (674) For irradiated nuclear fuel must be guest paragraphs 83. -

88. section I of annex 1 is based on the proven izotopickém composition with

order to achieve:



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



(b) a conservative estimate of the neutron multiplication for the assessment of radioactive

the consignment. After the exposure, but prior to shipment, the measurements must be carried out to

confirmation of the conservative estimate of isotope composition.



Requirements on geometrical arrangement and temperature



81. (675) Packaging the file after testing carried out as specified in the

paragraphs 19. -24. Part II. Annex No 1, must not allow insert

the cube of 10 cm.



82. (676) Radioactive shipment must be made for temperature interval

from minus 40 ° C to plus 38th. (C) if the authority does not provide for a decision on the

the type approval otherwise.



Evaluation of individual isolated radioactive shipments



83. (677) In the evaluation of isolated radioactive consignments must default

assumption be that water can penetrate to all free spaces

radioactive shipments, including those that are located inside of the restraint

system, and also to escape from them. However, if the design includes

Special resources to prevent such water penetration into the specific

free spaces, or the escape of water from these areas, and even in the

due to operator errors, then it is possible to assume, that in the referred

the water does not penetrate the spaces and of them escaping out the specific means.

they are:



(a) multiple, highly effective barrier against water, and each of them

should remain waterproof, even in the case of exposure to the radioactive shipments

the tests referred to in paragraph 88. (b) in part I of Annex No. 1. For special

resources can be mark of quality control in the production and maintenance and repair

packaging and reliability of the test results the conclusion of each
radioactive shipments before each shipment,



(b) for radioactive shipments containing only the uranium hexafluoride:



(i) the test referred to in paragraph 88. (b) in part I of Annex No. 1 when it is not

no physical contact between the valve and any other parts of the packaging

file than the original connection point and where, moreover, after performing the tests

prescribed in paragraph 28. Part II. Annex No 1 remain valves

tight,



(ii) quality control in the manufacture and maintenance of and repairs to the packaging

and the results of the tests to demonstrate closure of each radioactive consignments before

each transport.



84. (678). In the evaluation of isolated radioactive consignments must be

expected and found that the reflection caused at least

20 cm layer of water or to a higher reflection, which can be subsequently

due to the surrounding material in the immediate packaging,

near konfinementového (restrictive) system. Restrictive

the system is the spatial arrangement of fissile materials in the packaging file

and the arrangement of the parts of the packaging, so that the provision

podkritického the State of compliance with the conditions of nuclear safety. This

the arrangement, described the designer must be approved by the authority. If

demonstrated that the restrictive system stays inside the container after

the tests prescribed in paragraph 88. (b) in part I of Annex No. 1, may

be in paragraph 85. (c) in part I of Annex No. 1 for the reflection of neutrons

caused by at least 20 cm layer of water near the radioactive

the consignment.



85. (679) Radioactive shipment must remain podkritická for the assumptions

specified in paragraphs 83. -84. Part I of annex 1,

causing the maximum neutron multiplication, and under the conditions,

corresponding to:



(a) the normal transport conditions (without incident)



(b) the tests specified in paragraph 87. (b) in part I of annex 1,



(c) the tests set forth in paragraph 88. (b) in part I of Annex No. 1.



86. (680). For radioactive shipments transported by air:



(a) radioactive shipment must be podkritická under conditions consistent with

the test referred to in paragraph 34. Part II. Annex No 1, provided

the reflection caused by at least 20 cm layer of water, but without the intrusion of water

inside and



(b) shall not be taken of the special measures referred to in paragraph 83. part of the

I. Annex No 1, with the exception of the State when, after tests carried out

specified in paragraph 34. and after that in paragraph 33. Part II. Annex

No 1, avoids the entry of water inside the free spaces and water leaks from the

them.



Evaluation file radioactive shipments under normal conditions

transport



87. (681) the number "N", which is used to evaluate the status of the podkritického

radioactive shipments, file is derived, so that for a set of five

"N" radioactive shipments, are in a State of podkritickém for

the following arrangement, causing the maximum neutron multiplication:



(and) there is nothing between the radioactive shipments and file

radioactive shipments is after all sides exposed to the reflection at least

20 cm layer of water and



(b) the radioactive shipments were tested, or is presumed and

assessed their status after the tests specified in paragraph 19. -

24. part II. Annex No 1.



Evaluation file radioactive consignments under conditions of the accident at the

transport



88. (682) Number "N" shall be derived, such that two times "N-file"

radioactive shipments, are in a State of podkritickém for

the following arrangement, causing the maximum neutron multiplication:



(a) between the radioactive consignments there are hydrogen moderation and file

radioactive shipments is after all sides exposed to the reflection at least

20 cm layer of water and



(b) the radioactive shipments were tested, or must be reckoned with, and

assessed their status after the tests described in paragraph 19. -24.

Part II. Annex No 1 and then after making the most detrimental to the

testing of the following:



(i) the tests specified in paragraph 27. (b) or 27. (c) part II.

Annex No 1, or both for the radioactive shipment weighing less

or equal to 500 kg and the overall density is less than or equal to 1000 kg/m3

at the discretion of the external dimensions, or tests referred to in paragraph 27. (a) for the

all other radioactive shipments, followed by a test according to the

paragraph 28. and finished the tests referred to in paragraphs 31. -33. Part II.

Annex No 1, or



(ii) the test referred to in paragraph 29. Part II. Annex No 1 and



(c) whenever any part of the fissile material escapes from the restraint

the system, after the test specified in paragraph 88. (b) part I of the annex.

No. 1, must be considered and evaluated, that fissile material had escaped from each

radioactive shipments in the file and is in the space layout and

the Conference, which lead to the maximum neutron multiplication and addition occurs

the reflection in the vicinity of this substance caused by a layer of at least 20 cm of water.



PART II



TEST PROCEDURES



Verification of conformity



1. (701) Demonstration of compliance with the requirements set out in part I of Annex No. 1

must be carried out by any method described below, or a combination of

the following methods:



(a) the test samples representing the radioactive substance with low

the mass activity of LSA Group III, or radioactive substance specific

forms, rozptýlitelnou or little radioactive material or with prototypes or

samples of the packaging, where the contents of the sample or the packaging for the file

the test must simulate as closely as possible the expected range

the radioactive contents. Samples or packaging the files to be

tested shall be prepared as for carriage will be forwarded.



(b) the reference to the previous successful passes compliance pursuant to paragraphs a), (c)),

and (d)) enough of a similar nature.



(c) tests with models of appropriate scale of having such properties, which

they are significant because of the items when the engineering practice

demonstrated that the results of such tests are appropriate for the purposes of

design type. When a scale model is used, it must be taken into

considerations the need for adjusting certain test parameters, as

for example, the diameter of the rods or the comprehensive breakdown of the load.



(d) the calculation or substantiated argument when they are computing procedures and

parameters generally considered reliable or conservative.



2. (702). For the evaluation of the tests must be used or

the designated assessment methods, to demonstrate that the requirements of part II. Annex No.

1 were filled in accordance with the standards prescribed in the acceptance

I. Annex No 1.



Tests for a substance with low mass activity of LSA Group III



3. (703). A sample that represents the complete contents of the solid radioactive

the shipment (not less) must be on seven days submerged in water (to determine the

leaching ability) at room temperature. The volume of water used for the test

must be such that, at the end of the seven-day test period guarantees,

that the free volume neabsorbované and unreacted water will at least

to achieve 10% of the volume of a sample of solid substances. The water must have

the initial pH of 6-8 and a maximum conductivity of measure 10E-3S/m at 20 ° C.

Total activity of free volume of water must be measured after the end of

7-day test.



Tests for radioactive material, special form



General requirements



4. (704). Samples that contain or simulate radioactive substance

special forms must be submitted to stall test, test,

the bending test, and the heat test specified in paragraphs 5. -9. Part II.

Annex No 1. For each of these tests can be used in a different pattern.

After each test must be done in the determination of the leaching ability or

test the speed of the sample volume of leakage by using methods that

may be less sensitive than the methods specified in paragraph 10. part of the

II. Annex No 1 for nerozptýlitelnou solid or in accordance with paragraph

11. part II. Annex No 1 for a substance that is encapsulated.



Test methods



5. (705) stall test sample must fall on the pad (target) from a height

9 m. Washer must conform to the definition in paragraph 17. Part II. Annex

No 1.



6. (706). This allows the test sample must be placed on a plate of lead,

podepřeném smooth solid surface and have him come across flat front

aside from a mild steel bar so as to cause the shock of the corresponding

as a result of the impact mass 1.4 kg falling free fall of 1 m. lower part

the rods must have a diameter of 25 mm with edges rounded to a radius of 3.0 +/-0.3

mm. lead hardness 3.5-4.5 according to Vickersovy the scale and of a thickness

a maximum of 25 mm must overlap the area greater than the surface of the sample. For

each impact shall be applied to the new lead surface. The rod must be on a sample

in place of the assumed the greatest damage.



7. (707). The bend test must be carried out only for long and thin

resources that have a minimum length of 10 cm and at the same time the ratio of length to

the minimum width shall be at least 10. The sample must be firmly attached to

one half sticking out over the edge of the bracket. The orientation of the sample

must be such that its maximum damage when its

the free end hit the front surface of the steel bars. Steel rod must be on

a sample of the bump so that caused the shock of the corresponding result of impact

1.4 kg mass falling free fall of 1 m. lower part of the rod must have
25 mm diameter with edges rounded to a radius of 3.0 +/-0.3 mm.



8. (708). When the test sample must be heated in air to

the temperature of 800 ° C, this temperature must be maintained for 10 minutes after the

must be allowed to cool down.



9. (709) Samples that contain or simulate the fissile material or

the radioactive substance, concluded in case they may not be

reviewed:



(a) the tests prescribed in paragraphs 5. and 6. Part II. Annex No 1,

provided, that the mass of the special form radioactive material is less than

200 g and they are alternatively subjected to the class IV test,

prescribed in the publication, international organization for Standardization:

"Sealed radioactive sources-classification, ISO 2919:1980 (E), ISO,

Geneva, 1980 ".



(b) the test prescribed in paragraph 8. Part II. Annex No 1, for the

provided that, Alternatively, they are exposed to temperature class VI test,

prescribed in the publication, international organization for Standardization:

"Sealed radioactive sources-classification, ISO 2919:1980 (E), ISO,

Geneva, 1980 ".



The methods of the determination of the leaching ability and speed of a volumetric leakage



10. (710). For samples containing or simulating nerozptýlitelnou

a solid substance shall be the determination of the leaching ability is carried out as follows:



(a) the sample must be on seven days submerged in water (to determine the

leaching ability) at room temperature. The volume of water used for the test

must be such that, at the end of the seven-day test period guarantees,

that the free volume neabsorbované and unreacted water will at least

to achieve 10% of the volume of a sample of solid substances. The water must have

the initial pH of 6-8 and a maximum conductivity of 1 mS/m at 20 ° C.

the activity of the free volume of water must be measured after the 7-day

the test;



(b) the water sample must then be heated to a temperature of 50 ± 5 ° C and the

the temperature must be maintained for a period of 4 hours;



(c) then water activity must be laid down;



(d) nato, the sample must be left in the quiet air for seven days

at a minimum temperature of 30 ° C and a relative humidity of 90% minimum;



(e) subsequently, the sample must be immersed in water of the same specification as

in point (a) above and the water must then be heated to a temperature of 50 +/-5th.

C, this temperature must be maintained for a period of 4 hours;



(f) Finally, the activity of the water must be established.



11. (711) For samples containing or simulating the fissile material or

the radioactive substance in a closed case, they must be carried out

either the determination of the leaching ability or speed of a volumetric leakage,

in the following way:



(a) tube, the test must consist of the following steps:



(i) the sample must be immersed in water at room temperature. The water must

have an initial pH of 6-8 and a maximum conductivity of 1 mS/m at 20 ° C;



(ii) the water sample must then be heated to a temperature of 50 ± 5 ° C and

This temperature must be maintained for a period of 4 hours;



(iii) then water activity must be laid down;



(iv) nato sample must be left in the quiet air for seven days

at a minimum temperature of 30 ° C and a relative humidity of 90% minimum;



(v) the procedure referred to in items (i), (ii) and (iii) must be repeated.



(b) the alternative determination of the volumetric leakage rate must include

any of the tests prescribed in the publication of the international organization

for Standardization: "radiation protection-sealed radioactive sources-

test methods for leakage, ISO 9987:1992 (E), ISO, Geneva, 1992 "

are acceptable to the authority.



Tests for radioactive material with little rozptýlitelností



12. (712) A sample containing or simulating radioactive material with a small

rozptýlitelností must be subjected to the enhanced thermal test

specified in paragraph 36. and the impact test specified in

paragraph 37. Part II. Annex No 1. For each of the tests can be

used a different sample. After each test, the sample shall be subjected to the

digestion test specified in paragraph 3. Part II. Annex No 1.

After each test it shall be determined whether they are infused with the applicable

the requirements referred to in paragraph 8. Part I of Annex No. 1.



Tests for radioactive shipments



Preparation of the sample for testing



13. (713). All samples must be checked before testing, with a view to

identify and record faults or damage, including:



(a) derogations from the design type



(b) the manufacturing defects,



(c) corrosion, or other damage,



(d) deformation.



14. (714). Must be clearly specified in the restraint of radioactive

the consignment.



15. (715). The outer dimensions of the sample must be clearly identified so that

It was possible to make a simple and clear reference to each part of the sample.



Testing the integrity of the restraint system, shielding and valuation

podkritičnosti



16. (716.) After you have made the appropriate test or tests

specified in paragraphs 18. -37. Part II. Annex 1, shall be:



(a) identified and recorded defects or damage



(b) determine whether the restraint system integrity is maintained and shielding in

extent required by section I of Annex No. 1 of the test for radioactive

consignment and



(c) found in radioactive consignments containing fissile materials, whether

are fulfilled and the conditions applied in the valuation required in

paragraphs 77. -88. Part I of Annex No. 1 for one or more of the

radioactive shipments.



The target for the stall zkoušk



17. (717). The target for the drop tests specified in paragraphs 5., 22.,

25. (a), 27, 35. and 37. Part II. Annex No 1 must have a flat,

the horizontal surface of such a nature, that any increase in its resistance to

displacement or deformation upon impact of the sample subsequently increase damage

sample.



Tests for radioactive shipments projected for sulphur content

uranium



18. (718). Samples that contain, or simulate radioactive shipments

the design on the content of 0.1 kg or more of uranium must be hexafluoridu

tested hydraulically to the inner pressure of 1.38 MPa at least, but if

the test pressure is less than 2.76 MPa, the design type shall be subject to

type-approval by the competent authorities of the country of use. For the set

periodic testing of packaging files may be used in any

equivalent non-destructive testing, approved by the competent authorities of the countries

the use of.



Tests demonstrating ability to withstand normal conditions of transport



19. (719.) This is a test by spraying water, free fall, pressure

load and penetration. Samples of radioactive consignments shall be subject to

all tests, the first test shall be carried out by spraying with water. For

provided that they are filled with the requirements of paragraph 20. Part II. Annex

No 1, can be used for all tests one sample.



20. (720) time interval between the end of the test by spraying with water and

the following test shall be such that the water to the maximum extent seep

without značnějšího the drying of the exterior surface of the sample. If spraying

applied at the same time of the four sides, this break must be taken as

the two-hour, unless it can be demonstrated that the more conservative is the interval

another. Must not, however, be made no break, if it is used by the gradual

spraying water in each of the four directions.



21. (721) In the test by spraying the water sample must be exposed

sprinkling, that simulates rain about withholding the intensity of the corresponding

the value of 5 cm per hour for at least one hour form.



22. (722) During the test, the sample must be in free fall, tumbling at the target, so that the

due to the safety characteristics of the test suffered a maximum

damage, when it:



(a) the height of fall, measured from the lowest part of the specimen to the upper surface of the

the target shall be not less than the distance specified for the

weight table 3. (XIII) the target must match the definition given in the

paragraph 17. Part II. Annex No 1;



(b) for radioactive shipments rectangular shapes from cardboard or fiber from the

wood, not exceeding 50 kg weight, must be a special sample tested

free fall from a height of 0.3 m on every corner;



(c) for radioactive shipments cylindrical shape of the Board, filamentous

not exceeding a mass of 100 kg, a separate specimen shall be tested free

falling from a height of 0,

3 m on each quarter of the edges of the two bases in the war.



Table 3. (XIII) the height of free fall when testing of radioactive

consignments for normal conditions of transport

+-----------------------------------------+----------------------+

| The weight of the packaging file | Free fall height (m) |

the content's |to (kg) | |

+-----------------------------------------+----------------------+

less than 5 000 | | 1.2 |

+-----------------------------------------+----------------------+

| 5 000 more or equal to and less than 10 0000 | 0.9 |

+-----------------------------------------+----------------------+

more or equal | 10 000 and less than 15 0000 | 0.6 |

+-----------------------------------------+----------------------+

more than 15 000 | | 0.3 |

+-----------------------------------------+----------------------+



23. (723) If during the test the pressure of the shape of the packaging effectively

does not compress, the sample must be exposed for 24 hours

the pressure of the load must be evenly distributed to the two

the opposite side of the sample, one of which must be the base upon which
radioactive shipment normally consists of greater value than it is:



(a) five times the weight of the actual radioactive shipments or



(b) the product of the area projected vertically cross-section of radioactive shipments and

13 kPa pressure.



24. (724). In the test hole must be placed on neúhybný

a flat horizontal surface, but:



(a) the rod diameter 32 mm with polokulovým and weighing 6 kg must

gone in the direction of the vertical axis at the center of the weakest part of the sample so that the

When sufficiently deep penetration to hit on the restraint system. Rod

the test must not be substantially distorted.



(b) the height of fall of the rod as measured from the bottom-most end of the intended

part of the impact on the upper edge of the sample must be 1 m.



Additional tests for radioactive cargo type and designed for

liquids and gases



25. (725) The sample must be tested for each of the tests referred to in this

paragraph, however, if it can be demonstrated that one of the tests for a given

a sample of the more challenging than the second, in this case, the sample must be tested

a more challenging test:



(and) the free fall test, the sample must target to fall to an

his greatest damage due to the restraint system. The height of the

free fall, measured from the lowest part of the specimen to the upper surface of the target shall

be 9 m Target must match the definition given in paragraph 17. Part II.

Annex No 1;



(b) the penetration test, the sample is tested on the breakdown referred to in paragraph 24.

Part II. Annex No 1, but the height of the bars must be 1.7 m over 1 m

as specified in paragraph 24. (b) part II. Annex No 1.



Tests demonstrating ability to withstand accident conditions in transport



26. (726) The sample must be tested for the total effects of the tests referred to

in paragraphs 27. and 28. Part II. Annex No 1 in the order given. Subsequently,

After these tests must be a pattern or a special sample tested

dipping into the waters referred to in paragraph 29. and if it is applicable under the

paragraph 30. Part II. Annex No 1.



27. (727). The mechanical test consists of three different drop

the tests. Each sample is examined in accordance with the requirements of paragraphs 56. or 82.

Part I of Annex No. 1. The sequence of tests shall be such that after their

mechanical tests of the sample was damaged in the subsequent heat test

What is the largest, while:



(a) when the stall test and must fall on the target sample, in order to

his greatest damage, the height of fall, as measured from the lowest part of the

the sample to the upper surface of the target shall be 9 m. Target must match the

the definition given in paragraph 17. Part II. Annex No 1;



(b) when the stall test II. the sample must fall, so that was what

the largest impact damage to the rod mounted perpendicular to the target. The height of the fall

measured by the impact on the projected part of the sample to the top surface of the rod

must be 1 m Rod shall be of solid mild steel of circular cross-section

15.0 cm diameter + 0.5 cm and 20 cm long, in the event that a longer rod

does not cause more damage. In this case, the rod must be used

such a length that has caused the greatest damage. The upper end of the rods

must be flat and horizontal with rounded edges with a radius of not more

than 6 mm. Target, to which is attached the rod must conform to the definition of

referred to in paragraph 17. Part II. Annex No 1;



(c) in the test sample is located on the III targets subjected to dynamic

crushing fall of bodies weighing 500 kg from a height of 9 m, so that there was a

his greatest damage. The falling body must be solid, medium

Tough steel plate with dimensions of 1 m x 1 m and must fall in a horizontal

direction. The fall height shall be measured from the bottom of the plates to the top

the edge of the sample. Target, on which the pattern is must conform to the definition of

referred to in paragraph 17. Part II. Annex No 1.



28. (728) Before the thermal test sample must be in thermal equilibrium

at an ambient temperature of 38 ° C, under the conditions of the exposure of the Sun according to the table

1. (XI.), and at the same time when exposed to the maximum development of the internal heat

the radioactive content of the radioactive cargo. Alternatively, you may

have any of the listed parameters before and during the test by another

value, provided that they are taken into account in the valuation of the subsequent

the response of the radioactive cargo. Heat the test sample must not be

artificially cooled and any combustion of the sample materials must be left

the natural course, must consist of:



(a) exposure of the sample for a period of 30 minutes such a heat environment

which at least corresponds to the heat flow corresponds to the equivalent of a mixture of fire

hydrocarbon fuel and air in a sufficiently stable surrounding

the conditions for the achievement of the average emissions factor of at least 0.9 in

the average temperature of a flame of at least 800 ° C, fully surrounding sample

having a coefficient of surface absorption of 0.8 or one whose value

It will be proven when exposed to fire, radioactive shipment have,



(b) the consequent exposure of the sample to ambient temperature of 38 ° C, with the influence of the

the exposure of the Sun according to table 1. (XI.), and at the same time, with a maximum generation

the internal heat of the radioactive content of radioactive consignments on

a sufficiently long period to ensure that the temperature anywhere in the

sample decreased and were starting one.

Alternatively, you may have after the interruption of external heat supply any of the

given the parameters of different value, provided that they are taken into

considerations when pricing the subsequent response of the radioactive cargo.



29. (729) Test by dipping into the water sample must be immersed

at least 15 m below the surface for at least 8 hours to his

the greatest damage. The conditions of the test determines the value of the external

at least 150 kPa overpressure.



Extended test of dipping into the water for the radioactive shipment type B (U),

Type B (M) containing more than 10E5 A2 and type C for radioactive shipments



30. (730) When the extended test dipping into the water sample must be under

the surface of at least 200 m for at least 1 hour. Test conditions

determines the value of the external gauge pressure of 2 MPa minimum.



Test by dipping into the water for the radioactive shipment containing fissile

materials



31. (731). Radioactive cargo, for which the evaluation has been carried out

for intrusion and leakage of water in the range, which leads to the highest reactivity

for the purposes of the assessment referred to in paragraphs 83. -88. Part I of annex 1,

are excluded from this test.



32. (732). Before the sample is tested by immersion in water, must be

tested in accordance with paragraph 27. (b) or 27. (and) or 27. (c) part II.

Annex No 1, as required in paragraph 88. Part I of Annex No. 1

and specified in paragraph 28. Part II. Annex No 1.



33. (733) The sample must be submerged under the water level at least 0.9 m

for at least 8 hours, in the position in which the maximum leakage is expected.



Tests for radioactive shipment type C



34. (734). The samples shall be subjected to the effects of respectively of each of the

the following tests:



(a) the tests specified in paragraphs 27. (a) 27. (c), 35. and 36.

Part II. Annex No 1 and



(b) the test specified in paragraph 37. Part II. Annex No 1.



Note



For the sequence of the tests referred to in (a) and (b) is permitted to use the Special

samples.



35. (735). This allows the test sample shall be subjected to the destructive

the effect of the probe from the medium-hard steel. The orientation of the probe to the surface of the

the sample shall be such that after the test procedures specified in the

paragraph 34. (a) part II. Annex No 1 has caused the maximum damage

sample.



(a) a sample representing the radioactive shipment weighing less than

250 kg, shall be placed at the target and dropped a probe weighing 250

kg, falling from above 3 m above the intended point of impact. Probe for this

the test has a cylindrical rod of a diameter of 20 cm, with the end of (that will run up against

on the sample) in the shape of a truncated cone, with the following dimensions: 30 cm

height 2.5 cm diameter and the ending part. The target to which the sample is

faster must correspond to the definition given in paragraph 17. Part II.

Annex No 1.



(b) for radioactive shipments weighing more than 250 kg must be

located on the probe and sample target falls on the probe. The fall height, measured from the

part of the impact to the outer surface of the probe shall be 3 m for this test.

the probe must have the same shape and dimensions as specified in (a) above,

except that, if a greater length and mass of the probe could lead to

the greater the damage to the sample. The target to which the rod is mounted must

correspond to the definition given in paragraph 17. Part II. Annex No 1.



36. (736.) Advanced thermal test conditions must be the same as the

the conditions specified in paragraph 28. Part II. Annex No 1, with the

except that the exposure to heat must take 60 minutes.



37. (737) When the impact test, the sample shall be subjected to the impact on the target

at a speed of not less than 90 m/s, and it is oriented so that suffered

the maximum damage. The target must match the definition given in paragraph

17. part II. Annex No 1.



------------------------------------------------------------------



*) Note



Positional numbers printed in bold in parentheses according to paragraph numbers,

where appropriate, tables and pictures correspond to the numbering of the recommendations
The International Atomic Energy Agency, "the IAEA Safety Standards

Series, Regulations for the Safe Transport of Radioactive Material,

1996 Edition (Revised), Requirements, No. TS-R-1 (ST-1, Revised),

The International Atomic Energy Agency, Vienna, 2000 ". For this attachment

apply the interpretation of the concepts referred to in the abovementioned document from paragraph 201 to

paragraph 248.



**) Decree 214/1997 Coll., on quality assurance activities

related to the use of nuclear energy and the activities leading to the

exposure and determining the criteria for the classification and distribution of selected

equipment in the security classes.



Annex 2



Requirements for packaging files of type D and S



1. Packaging the file type (D) and with the



(a) it must be proven to be durable enough due to the

projected the way of handling



(b) must be made of materials whose life proven

corresponds to the projected useful life of the container. Materials with

shorter life can only be used for the components of the packaging file

in the course of the operation of the warehouse or storage easily replaced.



2. the content of the packaging file type D and S must be sufficiently dried out and

surrounded by a defined medium. About the criteria and the parameters of the drying

the media decides on a proposal from the Office of the applicant's type approval.



3. Packaging the file type must be designed so that:



(a) meets the requirements of paragraph 1. 56.-70. Part I of Annex No. 1 and at the same time

additional requirements specified and listed in annex No. 2.



(b) ensures the possibility of checking the packaging file during the

the operation of the warehouse;



(c) retain sufficient shielding during normal operation and project

accidents. Shielding packaging must guarantee that, on the surface

packaging will be the power equivalent to less than 10 mSv/h

and that's when the maximum permissible activity of the projected content

radionuclides;



(d) the heat generated inside the packaging file by its contents

radionuclides have not affected under normal conditions and for the external temperature 38

St. (C) the packaging file so adversely, that did not meet the requirements for

the tightness and shielding in the case that the packaging and contents of the file will not be

monitored for a period of one week;



(e) eliminate the influence arising from the heat, the heat must not:



1. change the layout, the geometrical form or physical state of the content

radionuclides or, if they are enclosed in a special casing radionuclides,

cause deformation or melting down of this sleeve or radionuclides,



2. reduce the effectiveness of the shielding container file as a result of his

uneven thermal expansion or cracking or melting down

shielding material



3. in combination with moisture, accelerate corrosion



4. be the cause of the interruption of the residual heat removal and removal of residual

the heat must be guaranteed, even in conditions of the project.



Annex 3



The limits of the activities and material restrictions



The basic values of radionuclides



1. (401). *) Table 1. (I) for individual radionuclides lists

the following core values:



(a) A1 and A2 in a TBq, where A1 is the value of activity of a radioactive substance

specific forms, as listed in table 1 (I) of the annex No. 3 or derived

According to annex No 3 and used to determine the activity limits for the purposes of

the requirements of the annexes to the No 1 to No 4 and A2 is the value of the activity of radioactive

substances other than special form radioactive material, referred to in table 1

(I) Annex 3 or derived in accordance with Annex No 3 and used to

the determination of the limits of the activity for the purposes of the requirements of the annexes to the No 1 to No 4;



(b) the limits of the activity to remove the substance in Bq/g; and



(c) limit activities to cut supplies in the Bq.



Determination of the Basic radionuclide values



2. (402). For individual radionuclides which are not listed in the table

1. (I) of the annex No 3 requires the determination of the fundamental values set out in

paragraph 1. Annex 3 the approval of the Authority or, for international

transport, the approval of the competent authorities of the countries concerned in the transport operation involves.

Where is the chemical form of each radionuclide is known, is allowed to

use the value in A2 is related to its solubility class as

recommended by the International Commission for radiation protection, if it is in

normal conditions of carriage, or in an accident is considered a chemical form

radionuclides. Alternatively, they can be used without the approval of the Authority

the value of the radionuclides listed in table 2 (II).



3. (403). When determining the value of A1 or A2 for a radionuclide that is not

given in table 1. (I) in annex No. 3, is a number of rozpadová, if you are

radionuclides contained in it in circumstances in which they occur in nature

and if none of the radioactive product of conversion does not have a half-life longer

than 10 days or longer than the half-life of the radionuclide in the series, the default

considered as a single radionuclide, and the value of the activities of the A1 or A2,

to be used must be the corresponding default values

radionuklidům the series. In the case of family disintegration, where any

the radioactive product of conversion has a half-life of more than 10 days, or

longer than the half-life of the radionuclide must be the default default radionuclide

along with the products of radioactive transformations considered a mixture of different

radionuclides.



4. (404). For mixtures of radionuclides, where the basic values of the individual

radionuclides are given in table 1 in accordance with paragraph 1. Annex No. 3,

applies to:



XM = 1//Sumaf (i) (i),

(I)



where:



(f) (i) is the proportion of activity or activity

the appropriate radionuclide in the mixture,

(I) x is the value of A1 or A2 or the limit of weight

activities for the extracted substance or limit activities for

check the delivery for the radionuclide i;

XM is the limit value derived for the mixture of values A1, or

A2, or from marginal activity for a cut

a substance or activity limits for extracted package.



5 (405). If the identity of each radionuclide is known but not if known

values for the activity of some of them, can be sorted to the radionuclides

groups and the lowest value of the activities in each group may be used in the

Calculations according to the formulae referred to in paragraph 4. and 15. Annex No. 3.

Groups may be based on the total Alpha activity and the total beta/gamma

activity, if known; to calculate according to the formulas listed in the

paragraphs 4. and 15. Annex No. 3 uses the lowest values for both

alpha emitters for beta/gamma emitters.



Table 1. (I) the basic values of radionuclides

-------------------------------------------------------------------------------------

radionuclide (atomic number) A1 A2 Limits Limits

the weight of the mass

activities activities

for removal to remove the

substance

-------------------------------------------------------------------------------------

[A TBq] [A TBq] [Bq/g] [Bq/g]

-------------------------------------------------------------------------------------

Actinium (89)

-------------------------------------------------------------------------------------

The AC-225, (and) an 8 x 10-1 6 x 10-3 1x101 1x104

-------------------------------------------------------------------------------------

AC-227 (a) 9x10-1 9x10-5 1 x 10-1 1x103

-------------------------------------------------------------------------------------

AC-228 6 x 10-1 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

Silver (47)

-------------------------------------------------------------------------------------

AG-105 2 x 100 2 x 100 1x102 1x106

-------------------------------------------------------------------------------------

AG-108 m (a) 7 x 10-1 7 x 10-1 1x101 (b) 1x106 (b)

-------------------------------------------------------------------------------------

AG-110 m (a) 4 x 10-1 4 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

AG-111 2x106 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

Aluminum (13)

-------------------------------------------------------------------------------------

Al-26 1 x 10-1 1 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Americium (95)

-------------------------------------------------------------------------------------

Am-241 1x101 1 x 10-3 1 x 100 1x104

-------------------------------------------------------------------------------------

Am-242 m (a) 1x101 1 x 10-3 1 x 100 (b) 1x104 (b)

-------------------------------------------------------------------------------------

Am-243 (a) 5x100 1 x 10-3 1 x 100 (b) 1x103 (b)

-------------------------------------------------------------------------------------

Argon (18)

-------------------------------------------------------------------------------------

Ar-37 4x101 4x101 1x106 1x108

-------------------------------------------------------------------------------------

AR-39 4x101 2x101 1x107 1x104

-------------------------------------------------------------------------------------

AR-3 x 10-3 x 10 41 1-1 1x102 1x109

-------------------------------------------------------------------------------------

Arsenic (33)
-------------------------------------------------------------------------------------

As-3 x 10-3 x 10 72 1-1 1x101 1x105

-------------------------------------------------------------------------------------

As-73 4x101 4x101 1x103 1x107

-------------------------------------------------------------------------------------

As-74 1x106 9x10-1 1x101 1x106

-------------------------------------------------------------------------------------

As-76 3 x 10-1 3 x 10-1 1x102 1x105

-------------------------------------------------------------------------------------

As-77 7 x 10 2x101-1 1x103 1x106

-------------------------------------------------------------------------------------

Astatine (85)

-------------------------------------------------------------------------------------

At-211 (a) 2x101 5x10-1 1x103 1x107

------------------------------------------------------------------------------- ------

Gold (79)

-------------------------------------------------------------------------------------

Au-193 7x100 1x102 1x107 2 x 100

-------------------------------------------------------------------------------------

Au-194 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

Au-195 1x101 6 x 100 1x102 1x107

-------------------------------------------------------------------------------------

Au-198-1 1 x 100 6 x 10 1x102 1x106

-------------------------------------------------------------------------------------

Au-199 1x101 6 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

Barium (56)

-------------------------------------------------------------------------------------

BA-131 (a) 2 x 100 2 x 100 1x102 1x106

-------------------------------------------------------------------------------------

BA-133 3x100 3x100 1x102 1x106

-------------------------------------------------------------------------------------

BA-133m-1 2x101 6 x 10 1x102 1x106

-------------------------------------------------------------------------------------

BA-140 (a) 5x10-1 3 x 10-1 1x101 (b) 1x105 (b)

-------------------------------------------------------------------------------------

Beryllium (4)

-------------------------------------------------------------------------------------

Be-7 2x101 2x101 1x103 1x107

-------------------------------------------------------------------------------------

The be-10 4x101 6 x 10-1 1x104 1x106

-------------------------------------------------------------------------------------

Vizmut (83)

-------------------------------------------------------------------------------------

BI-205 7 x 10-1 7 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

BI-3 x 10-3 x 10 206 1-1 1x101 1x105

-------------------------------------------------------------------------------------

BI-207 7 x 10-1 7 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

BI-210-1 1 x 100 6 x 10 1x103 1x106

-------------------------------------------------------------------------------------

BI-210m (a) 6 x 10-1 10-2 1x101 1x105

-------------------------------------------------------------------------------------

BI-212 (a) 7 x 10-1 6 x 10-1 1x101 (b) 1x105 (b)

-------------------------------------------------------------------------------------

Berkelium (97)

-------------------------------------------------------------------------------------

BK-247 8x100 1 x 100 x 10-4 1x104

-------------------------------------------------------------------------------------

BK-249 (a) 3 x 10 4x101-1 1x103 1x106

-------------------------------------------------------------------------------------

Bromine (35)

-------------------------------------------------------------------------------------

BR-76 4 x 10-1 4 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

BR-77 3x100 3x100 1x102 1x106

-------------------------------------------------------------------------------------

BR-82 4 x 10-1 4 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Carbon (6)

-------------------------------------------------------------------------------------

C-11-1 1 x 100 6 x 10 1x101 1x106

-------------------------------------------------------------------------------------

C-14 4x101 3x100 1x104 1x107

-------------------------------------------------------------------------------------

Calcium (20)

-------------------------------------------------------------------------------------

CA-41 1x105 Unlimited 1x107 Unlimited

-------------------------------------------------------------------------------------

CA-45 4x101 1 x 100 1x104 1x107

-------------------------------------------------------------------------------------

CA-47 (and) 3x100 3 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Cadmium (48)

-------------------------------------------------------------------------------------

CD-109 3x101 2 x 100 1x104 1x106

-------------------------------------------------------------------------------------

CD-113m 4x101 5x10-1 1x103 1x106

-------------------------------------------------------------------------------------

CD-115 (a) 4 x 10 3x100-1 1x102 1x106

-------------------------------------------------------------------------------------

CD-115m 5x10-1 5x10-1 1x103 1x106

-------------------------------------------------------------------------------------

CER (58)

-------------------------------------------------------------------------------------

CE-139 7x100 2 x 100 1x102 1x106

-------------------------------------------------------------------------------------

CE-141 6 x 10 2x101-1 1x102 1x107

-------------------------------------------------------------------------------------

CE-143-1 6 x 10 9x10-1 1x102 1x106

-------------------------------------------------------------------------------------

CE-144 (a) 2 x 10-1 10-1 1x102 (b) 1x105 (b)

-------------------------------------------------------------------------------------

Californium (98)

-------------------------------------------------------------------------------------

CF-248 6 x 10-3 4x101 1x101 1x104

-------------------------------------------------------------------------------------

CF-240 3x100 x 10-4 1x103 1 x 100

-------------------------------------------------------------------------------------

CF-250 2 x 10-3 2x101 1x101 1x104

-------------------------------------------------------------------------------------

CF-251 7x100 7 x 10-4 1x103 1 x 100

-------------------------------------------------------------------------------------

Cf-252-2 5x10 3 x 10-3 1x101 1x104

-------------------------------------------------------------------------------------

CF-253 (a) 4 x 10-2 1x102 4x101 1x105

-------------------------------------------------------------------------------------

CF-254 1 x 10-3 1 x 10-3 1 x 100 1x103

-------------------------------------------------------------------------------------

Chlorine (17)

-------------------------------------------------------------------------------------

CL-36 6 x 10 1x101-1 1x104 1x106

-------------------------------------------------------------------------------------

CL-38 2 x 10-1 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Curium (96)

-------------------------------------------------------------------------------------

Cm-240 4x101 10-2 1x102 1x105

-------------------------------------------------------------------------------------

2 x 100 cm-241 1 x 100 1x102 1x106

-------------------------------------------------------------------------------------

Cm-242 4x101 1 x 10-2 1x102 1x105

-------------------------------------------------------------------------------------

Cm-243 9x100 1 x 10-3 1 x 100 1x104

-------------------------------------------------------------------------------------

Cm-244 2x101 2 x 10-3 1x101 1x104

-------------------------------------------------------------------------------------

Cm-245 9x100 9x10-4 1x103 1 x 100

-------------------------------------------------------------------------------------

Cm-246 9x100 9x10-4 1x103 1 x 100

-------------------------------------------------------------------------------------

Cm-247 (a) 3x100 1 x 10-3 1 x 100 1x104

-------------------------------------------------------------------------------------

Cm-248-2 p 3 x 10-4 1x103 1 x 100

-------------------------------------------------------------------------------------

Cobalt (27)
-------------------------------------------------------------------------------------

Co-55 5x10-1 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

What is 3 x 10-1-56-1 1x101 1x105 3 x 10

-------------------------------------------------------------------------------------

Co-57 1x101 1x101 1x102 1x106

-------------------------------------------------------------------------------------

Co-58 1x101 1 x 100 1 x 100 1x106

-------------------------------------------------------------------------------------

What-4x101 4x101 1x104 1x107 58 m

-------------------------------------------------------------------------------------

Co-60 4 x 10-1 4 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Chrome (24)

-------------------------------------------------------------------------------------

CR-51 3x101 3x101 1x103 1x107

-------------------------------------------------------------------------------------

Cesium (55)

-------------------------------------------------------------------------------------

CS-129 one one 1x102 1x105

-------------------------------------------------------------------------------------

CS-131 3x101 3x101 1x103 1x106

-------------------------------------------------------------------------------------

CS-1 x 100 132 1 x 100 1x101 1x105

-------------------------------------------------------------------------------------

CS-134 7 x 10-1 7 x 10-1 1x101 1x104

-------------------------------------------------------------------------------------

CS-134 m 6 x 10 4x101-1 1x103 1x105

-------------------------------------------------------------------------------------

CS-135 4x101 1 x 100 1x104 1x107

-------------------------------------------------------------------------------------

CS-136 5x10-1 5x10-1 1x101 1x105

-------------------------------------------------------------------------------------

CS-137 (a) 2 x 100 6 x 10-1 1x101 (b) 1x104 (b)

-------------------------------------------------------------------------------------

Copper (29)

-------------------------------------------------------------------------------------

CU-64 6 x 100 1 x 100 1x102 1x106

-------------------------------------------------------------------------------------

CU-67 1x101 7 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

Dysprosium (66)

-------------------------------------------------------------------------------------

Dy-159 2x101 2x101 1x103 1x107

-------------------------------------------------------------------------------------

Dy-165 9x10-1 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

Dy-166 (a) 9x10-1 3 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

Erbium (68)

-------------------------------------------------------------------------------------

ER-169 4x101 1 x 100 1x104 1x107

-------------------------------------------------------------------------------------

ER-171 an 8 x 10-1 5x10-1 1x102 1x106

-------------------------------------------------------------------------------------

Europium (63)

-------------------------------------------------------------------------------------

EU-147 2 x 100 2 x 100 1x102 1x106

-------------------------------------------------------------------------------------

EU-148 5x10-1 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

EU-149 2x101 2x101 1x102 1x107

-------------------------------------------------------------------------------------

EU-150 (with a short half-life) 7 x 10 2 x 100-1 1x103 1x106

-------------------------------------------------------------------------------------

EU-150 (long-lived) 7 x 10-1 7 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

EU-152 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

EU-152 m 10-1 10-1 1x102 1x106

-------------------------------------------------------------------------------------

EU-154-1 6 x 10 9x10-1 1x101 1x106

-------------------------------------------------------------------------------------

EU-155 2x101 3x100 1x102 1x107

-------------------------------------------------------------------------------------

EU-156 7 x 10-1 7 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Measures (9)

-------------------------------------------------------------------------------------

F-18 1 x 100 6 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Iron (26)

-------------------------------------------------------------------------------------

Fe-52 (a) 3 x 10-1 3 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Fe-55 4x101 4x101 1x104 1x106

------------------------------------------------------------------------------- ------

Fe-59 9x10-1 9x10-1 1x101 1x106

-------------------------------------------------------------------------------------

Fe-60 (a) 4x101 2 x 10-1 1x102 1x105

-------------------------------------------------------------------------------------

Galium (31)

-------------------------------------------------------------------------------------

GA-67 7x100 3x100 1x102 1x106

-------------------------------------------------------------------------------------

GA-68 5x10-1 5x10-1 1x101 1x105

-------------------------------------------------------------------------------------

GA-72 4 x 10-1 4 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Gadolinium (64)

-------------------------------------------------------------------------------------

GD-146 (a) 5x10-1 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

GD-2 x 10-3 148 2x101 1x101 1x104

-------------------------------------------------------------------------------------

GD-153 1x101 9x100 1x102 1x107

-------------------------------------------------------------------------------------

GD-3x100 159 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

Germanium (32)

-------------------------------------------------------------------------------------

GE-68 (a) 5x10-1 5x10-1 1x101 1x105

-------------------------------------------------------------------------------------

GE-71 4x101 4x101 1x104 1x108

-------------------------------------------------------------------------------------

The GE-3 x 10-3 x 10 77 1-1 1x101 1x105

-------------------------------------------------------------------------------------

Hafnium (72)

-------------------------------------------------------------------------------------

HF-172 (a) 6 x 10-1 6 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

HF-3x100 3x100 1x102 1x106 175

-------------------------------------------------------------------------------------

HF-181 2 x 100 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

HF-182 Unlimited Unlimited 1x102 1x106

-------------------------------------------------------------------------------------

Mercury (80)

-------------------------------------------------------------------------------------

Hg-194 (a) 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

Hg-195m (a) 3x100 7 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

Hg-197 2x101 1x101 1x102 1x107

-------------------------------------------------------------------------------------

Hg-4 x 10 197m 1x101-1 1x102 1x106

-------------------------------------------------------------------------------------

Hg-203 5x100 1x102 1x105 1 x 100

-------------------------------------------------------------------------------------

Holmium (67)

-------------------------------------------------------------------------------------

Ho-166 4 x 10-1 4 x 10-1 1x103 1x105

-------------------------------------------------------------------------------------

166m-6 x 10-1 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

Iodine (53)

-------------------------------------------------------------------------------------

I-123 6 x 100 3x100 1x102 1x107
-------------------------------------------------------------------------------------

I-124 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

I-125 2x101 3x100 1x103 1x106

-------------------------------------------------------------------------------------

I-126 2 x 100 1 x 100 1x102 1x106

-------------------------------------------------------------------------------------

I-129 Unlimited Unlimited 1x102 1x105

-------------------------------------------------------------------------------------

I-131 3x100 7 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

I-132 4 x 10-1 4 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

I-133 7 x 10-1 6 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

I-134 3 x 10-1 3 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

I-135 (a) 6 x 10-1 6 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Indium (49)

-------------------------------------------------------------------------------------

In-111 3x100 3x100 1x102 1x106

-------------------------------------------------------------------------------------

In-113m one 1x102 1x106 2 x 100

-------------------------------------------------------------------------------------

In-114m (a) 1x101 5x10-1 1x102 1x106

-------------------------------------------------------------------------------------

In-115m 7x100 1x102 1x106 1 x 100

-------------------------------------------------------------------------------------

Iridium (77)

-------------------------------------------------------------------------------------

IR-189 (a) 1x101 1x101 1x102 1x107

-------------------------------------------------------------------------------------

IR-190 7 x 10-1 7 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

IR-192 1 x 100 (c) 6 x 10-1 1x101 1x104

-------------------------------------------------------------------------------------

IR-3 x 10-3 x 10 194 1-1 1x102 1x105

-------------------------------------------------------------------------------------

Potassium (19)

-------------------------------------------------------------------------------------

To-40 9x10-1 9x10-1 1x102 1x106

-------------------------------------------------------------------------------------

K-42 p-1 p-1 1x102 1x106

-------------------------------------------------------------------------------------

K-7 x 10-6 x 10 43 1-1 1x101 1x106

-------------------------------------------------------------------------------------

Krypton (36)

------------------------------------------------------------------------------- ------

KR-81 4x101 4x101 1x104 1x107

-------------------------------------------------------------------------------------

KR-85 1x101 1x101 1x105 1x104

-------------------------------------------------------------------------------------

KR-85 m 8x100 3x100 1x103 1x101 0

-------------------------------------------------------------------------------------

KR-87 2 x 10-1 10-1 1x102 1x109

-------------------------------------------------------------------------------------

Lanthanum (57)

-------------------------------------------------------------------------------------

La-137 3x101 6 x 100 1x103 1x107

-------------------------------------------------------------------------------------

La-140 4 x 10-1 4 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Lutetium (71)

-------------------------------------------------------------------------------------

Lu-172 6 x 10-1 6 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Lu-173 8x100 8x100 1x102 1x107

-------------------------------------------------------------------------------------

Lu-174 9x100 9x100 1x102 1x107

-------------------------------------------------------------------------------------

Lu-174 m 2x101 1x101 1x102 1x107

-------------------------------------------------------------------------------------

Lu-177 3x101 7 x 10-1 1x103 1x107

-------------------------------------------------------------------------------------

Magnesium (12)

-------------------------------------------------------------------------------------

Mg-28 (a) 3 x 10-1 3 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Manganese (25)

-------------------------------------------------------------------------------------

MN-52 3 x 10-1 3 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

MN-53 1x104 Unlimited 1x109 Unlimited

-------------------------------------------------------------------------------------

MN-54 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

MN-56-1 3 x 10 3 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Molybdenum (42

-------------------------------------------------------------------------------------

MO-93 4x101 2x101 1x103 1x108

-------------------------------------------------------------------------------------

MO-99 (a) 1 x 100 6 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

Nitrogen (7)

-------------------------------------------------------------------------------------

N-13 9x10-1 6 x 10-1 1x102 1x109

-------------------------------------------------------------------------------------

Sodium (11)

-------------------------------------------------------------------------------------

On-22 5x10-1 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

On the 2 x 10-1-24-10-1 1x101 1x105

-------------------------------------------------------------------------------------

Niobium (41)

-------------------------------------------------------------------------------------

NB-93 m 4x101 3x101 1x104 1x107

-------------------------------------------------------------------------------------

NB-94 7 x 10-1 7 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

NB-95 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

NB-97 9x10-1 6 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Neodymium (60)

-------------------------------------------------------------------------------------

ND-147 6 x 10 6 x 100-1 1x102 1x106

-------------------------------------------------------------------------------------

ND-149 6 x 10-1 5x10-1 1x102 1x106

-------------------------------------------------------------------------------------

Nickel (28)

-------------------------------------------------------------------------------------

NI-59 Unlimited Unlimited 1x104 1x108

-------------------------------------------------------------------------------------

NI-63 4x101 3x101 1x105 1x108

-------------------------------------------------------------------------------------

NI-65 4 x 10-1 4 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Neptunium (93)

-------------------------------------------------------------------------------------

NP-235 4x101 4x101 1x103 1x107

-------------------------------------------------------------------------------------

NP-236 (with a short half-life) of 2 x 100 1x103 2x101 1x107

-------------------------------------------------------------------------------------

NP-236 (long-lived) 9x100 2 x 10-2 1x102 1x105

-------------------------------------------------------------------------------------

NP-237 2x101 2 x 10-3 1 x 100 (b) 1x103 (b)

-------------------------------------------------------------------------------------

NP-239 7x100 4 x 10-1 1x102 1x107

-------------------------------------------------------------------------------------

Osmium (76)

-------------------------------------------------------------------------------------

OS-1 x 100 1 x 100 185 1x101 1x106

-------------------------------------------------------------------------------------

OS-191 1x101 2 x 100 1x102 1x107

-------------------------------------------------------------------------------------

OS-191m 4x101 3x101 1x103 1x107

-------------------------------------------------------------------------------------
OS-193 2 x 100 6 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

OS-194 (a) 3 x 10-1 3 x 10-1 1x102 1x105

-------------------------------------------------------------------------------------

Phosphorus (15)

-------------------------------------------------------------------------------------

P-32 5x10-1 5x10-1 1x103 1x105

-------------------------------------------------------------------------------------

P-33 4x101 1 x 100 1x105 1x108

-------------------------------------------------------------------------------------

Protaktinium (91)

-------------------------------------------------------------------------------------

PA-230 (a) 2 x 100 7 x 10-2 1x101 1x106

-------------------------------------------------------------------------------------

PA-231 one 4 x 10-4 1x103 1 x 100

-------------------------------------------------------------------------------------

PA-233 5x100 7 x 10-1 1x102 1x107

-------------------------------------------------------------------------------------

Lead (82)

-------------------------------------------------------------------------------------

PB-201 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

PB-4x101 2x101 1x103 1x106 202

-------------------------------------------------------------------------------------

PB-203 3x100 1x102 one 1x106

-------------------------------------------------------------------------------------

PB-205 Unlimited Unlimited 1x104 1x107

-------------------------------------------------------------------------------------

Pb-210 (a) 1 x 100 5x10-2 1x101 (b) 1x104 (b)

-------------------------------------------------------------------------------------

PB-212 (a) 7 x 10-1 10-1 1x101 (b) 1x105 (b)

-------------------------------------------------------------------------------------

Palladium (46)

-------------------------------------------------------------------------------------

PD-103 (a) 4x101 4x101 1x103 1x108

-------------------------------------------------------------------------------------

PD-107 1x105 Unlimited 1x108 Unlimited

-------------------------------------------------------------------------------------

PD-109 5x10 2 x 100-1 1x103 1x106

-------------------------------------------------------------------------------------

Promethium (61)

-------------------------------------------------------------------------------------

PM-143 3x100 3x100 1x102 1x106

-------------------------------------------------------------------------------------

PM-144 7 x 10-1 7 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

PM-145 3x101 1x101 1x103 1x107

-------------------------------------------------------------------------------------

PM-147 4x101 2 x 100 1x104 1x107

-------------------------------------------------------------------------------------

PM-148 m (a) an 8 x 10-1 7 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

PM-149 of 2 x 100 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

Polonium (84)

-------------------------------------------------------------------------------------

After 210 p-4x101-2 1x101 1x104

-------------------------------------------------------------------------------------

Praseodymium (59)

-------------------------------------------------------------------------------------

PR-142 4 x 10-1 4 x 10-1 1x102 1x105

-------------------------------------------------------------------------------------

PR-143 6 x 10 3x100-1 1x104 1x106

-------------------------------------------------------------------------------------

Platinum (78)

-------------------------------------------------------------------------------------

PT-188 (a) 1 x 100 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

PT-191 3x100 one 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 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

PT-197m 1x101 6 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

Plutonium (94)

-------------------------------------------------------------------------------------

Pu-236 3x101 3 x 10-3 1x101 1x104

-------------------------------------------------------------------------------------

Pu-237 2x101 2x101 1x103 1x107

-------------------------------------------------------------------------------------

Pu-238 1x101 1 x 10-3 1 x 100 1x104

-------------------------------------------------------------------------------------

Pu-239 1x101 1 x 10-3 1 x 100 1x104

-------------------------------------------------------------------------------------

Pu-240 1x101 1 x 10-3 1 x 100 1x103

-------------------------------------------------------------------------------------

Pu-241 (a) 6 x 10-2 4x101 1x102 1x105

-------------------------------------------------------------------------------------

Pu-242 1x101 1 x 10-3 1 x 100 1x104

-------------------------------------------------------------------------------------

Pu-244 (a) 4 x 10-1 1 x 10-3 1 x 100 1x104

-------------------------------------------------------------------------------------

Radium (88)

-------------------------------------------------------------------------------------

RA-223 (a) 4 x 10-1 7 x 10-3 1x20E2 (b) 1x105 (b)

-------------------------------------------------------------------------------------

RA-224 (a) 4 x 10-1 10-2 1x101 (b) 1x105 (b)

-------------------------------------------------------------------------------------

RA-225 (a) 2 x 10-1 4 x 10-3 1x102 1x105

-------------------------------------------------------------------------------------

RA-226 (a) 2 x 10-1 3 x 10-3 1x101 (b) 1x104 (b)

-------------------------------------------------------------------------------------

RA-228 (a) 6 x 10-1 10-2 1x101 (b) 1x105 (b)

-------------------------------------------------------------------------------------

Rubidium (37)

-------------------------------------------------------------------------------------

RB-81 2 x 100 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

RB-83 (a) 2 x 100 2 x 100 1x102 1x106

-------------------------------------------------------------------------------------

RB-84 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

RB-86 5x10-1 5x10-1 1x102 1x105

-------------------------------------------------------------------------------------

RB-87 1x104 Unlimited 1x107 Unlimited

-------------------------------------------------------------------------------------

RB (natural) Unlimited Unlimited 1x104 1x107

-------------------------------------------------------------------------------------

Rhenium (75)

-------------------------------------------------------------------------------------

Re-184 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

Re-184m 3x100 1x102 1x106 1 x 100

-------------------------------------------------------------------------------------

Re-186 2 x 100 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

Re-187 Unlimited Unlimited 1x106 1x109

-------------------------------------------------------------------------------------

Re-188 4 x 10-1 4 x 10-1 1x102 1x105

-------------------------------------------------------------------------------------

Re-189 (a) 6 x 10 3x100-1 1x102 1x106

-------------------------------------------------------------------------------------

Re (natural) Unlimited Unlimited 1x106 1x109

-------------------------------------------------------------------------------------

Rhodium (45)

-------------------------------------------------------------------------------------

RH-99 of 2 x 100 2 x 100 1x101 1x106

-------------------------------------------------------------------------------------

RH-101 3x100 1x102 1x107 one

-------------------------------------------------------------------------------------
RH-102 5x10-1 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

RH-102 m 2 x 100 2 x 100 1x102 1x106

-------------------------------------------------------------------------------------

RH-103 m graphics 4x101 4x101 1x104 1x108

-------------------------------------------------------------------------------------

RH-105 1x101 an 8 x 10-1 1x102 1x107

-------------------------------------------------------------------------------------

Radon (86)

-------------------------------------------------------------------------------------

RN-222 (a) 3 x 10-1 4 x 10-3 1x101 (b) 1x108 (b)

-------------------------------------------------------------------------------------

Ruthenium (44)

-------------------------------------------------------------------------------------

Ru-97 5x100 5x100 1x102 1x107

-------------------------------------------------------------------------------------

Ru-103 (a) 2 x 100 2 x 100 1x102 1x106

-------------------------------------------------------------------------------------

Ru-105-1 1 x 100 6 x 10 1x101 1x106

-------------------------------------------------------------------------------------

Ru-106 (a) 2 x 10-1 10-1 1x102 (b) 1x105 (b)

-------------------------------------------------------------------------------------

Sulphur (16)

-------------------------------------------------------------------------------------

S-35 4x101 3x100 1x105 1x108

-------------------------------------------------------------------------------------

Antimony (51)

-------------------------------------------------------------------------------------

SB-122 4 x 10-1 4 x 10-1 1x102 1x104

-------------------------------------------------------------------------------------

SB-124 6 x 10-1 6 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

SB-125 2 x 100 1 x 100 1x102 1x106

-------------------------------------------------------------------------------------

SB-126 4 x 10-1 4 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Scandium (21)

-------------------------------------------------------------------------------------

SC-44 5x10-1 5x10-1 1x101 1x105

-------------------------------------------------------------------------------------

SC-46 5x10-1 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

SC-47 1x101 7 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

SC-48 3 x 10-1 3 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Selenium (34)

-------------------------------------------------------------------------------------

-75 3x100 3x100 1x102 1x106

-------------------------------------------------------------------------------------

-79 4x101 2 x 100 1x104 1x107

-------------------------------------------------------------------------------------

Silicon (14)

-------------------------------------------------------------------------------------

-31 's 6 x 10-1 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

-32 's 4x101 5x10-1 1x103 1x106

-------------------------------------------------------------------------------------

Samarium (62)

-------------------------------------------------------------------------------------

SM-145 1x101 1x101 1x102 1x107

-------------------------------------------------------------------------------------

SM-147 1x101 Unlimited 1x104 Unlimited

-------------------------------------------------------------------------------------

SM-151 4x101 1x101 1x104 1x108

-------------------------------------------------------------------------------------

SM-153 9x100 1 6 x 10-1x102 1x106

-------------------------------------------------------------------------------------

The Tin (50)

-------------------------------------------------------------------------------------

SN-113 (a) one of 2 x 100 1x103 1x107

-------------------------------------------------------------------------------------

SN 117 m 4 x 10-7x100-1 1x102 1x106

-------------------------------------------------------------------------------------

SN-119 4x101 3x101 1x103 1x107

-------------------------------------------------------------------------------------

SN-121m (a) 4x101 9x10-1 1x103 1x107

-------------------------------------------------------------------------------------

SN-123 an 8 x 10-1 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

SN-125 4 x 10-1 4 x 10-1 1x102 1x105

-------------------------------------------------------------------------------------

SN-126 (a) 6 x 10-1 4 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Strontium (38)

-------------------------------------------------------------------------------------

SR-82 (a) 2 x 10-1 10-1 1x101 1x105

-------------------------------------------------------------------------------------

SR-85 2 x 100 2 x 100 1x102 1x106

-------------------------------------------------------------------------------------

SR-85 m 5x100 5x100 1x102 1x107

-------------------------------------------------------------------------------------

SR-a 3x100 3x100 1x102 1x106

-------------------------------------------------------------------------------------

SR-89 6 x 10-1 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

SR-90 (a) 3 x 10-1 3 x 10-1 1x102 (b) 1x104 (b)

-------------------------------------------------------------------------------------

SR-91 (a) 3 x 10-1 3 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

SR-92 (a) 1 x 100 3 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Tricium (1)

-------------------------------------------------------------------------------------

T (H-3) 4x101 4x101 1x106 1x109

-------------------------------------------------------------------------------------

Tantalum (73)

-------------------------------------------------------------------------------------

Ta-178 (long-lived) 1 x 100 x 10-1 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 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

TB-160-1 1 x 100 6 x 10 1x101 1x106

-------------------------------------------------------------------------------------

Technetium (43)

-------------------------------------------------------------------------------------

TC-95m (a) 2 x 100 2 x 100 1x101 1x106

-------------------------------------------------------------------------------------

TC-96 4 x 10-1 4 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

TC-96 metres (a) 4 x 10-1 4 x 10-1 1x103 1x107

-------------------------------------------------------------------------------------

TC-97 1x103 Unlimited 1x108 Unlimited

-------------------------------------------------------------------------------------

TC-97m 4x101 1x103 1x107 1 x 100

-------------------------------------------------------------------------------------

TC-98 10-1 7 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

The TC-99 4x101 9x10-1 1x104 1x107

-------------------------------------------------------------------------------------

TC-99m 1x101 one 1x102 1x107

-------------------------------------------------------------------------------------

Tellurium (52)

-------------------------------------------------------------------------------------

Te-121 2 x 100 2 x 100 1x101 1x106

-------------------------------------------------------------------------------------

Te-121m 5x100 3x100 1x102 1x105

-------------------------------------------------------------------------------------

Te-123m 8x100 1x102 1x107 1 x 100

-------------------------------------------------------------------------------------

Te-125 2x101 9x10-1 1x103 1x107
-------------------------------------------------------------------------------------

Te-127 7 x 10 2x101-1 1x103 1x106

-------------------------------------------------------------------------------------

Te-127m (a) 2x101 5x10-1 1x103 1x107

-------------------------------------------------------------------------------------

Te-129 6 x 10 7 x 10-1-1 1x102 1x106

-------------------------------------------------------------------------------------

Te-129m (and) an 8 x 10-1 4 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

Te-131m (a) 7 x 10-1 5x10-1 1x101 1x106

-------------------------------------------------------------------------------------

Te-132 (a) 5x10-1 4 x 10-1 1x102 1x107

-------------------------------------------------------------------------------------

Thorium (90)

-------------------------------------------------------------------------------------

Th-227 1x101 5x10-3 1x101 1x104

-------------------------------------------------------------------------------------

Th-228 (a) 5x10-1 1 x 10-3 1 x 100 (b) 1x104 (b)

-------------------------------------------------------------------------------------

Th-229-4 1 x 100 5x100 5x10 (b) 1x103 (b)

-------------------------------------------------------------------------------------

Th-230 1x101 1 x 10-3 1 x 100 1x104

-------------------------------------------------------------------------------------

Th-231 4x101 2 x 10-2 1x103 1x107

-------------------------------------------------------------------------------------

Th-232 Unlimited Unlimited 1x101 1x104

-------------------------------------------------------------------------------------

Th-234 (a) 3 x 10-1 3 x 10-1 1x103 (b) 1x105 (b)

-------------------------------------------------------------------------------------

Th (natural) Unlimited Unlimited 1 x 100 (b) 1x103 (b)

-------------------------------------------------------------------------------------

Titan (22)

-------------------------------------------------------------------------------------

TI-44 (a) 5x10-1 4 x 10-1 1x101 1x105

-------------------------------------------------------------------------------------

Thallium (81)

-------------------------------------------------------------------------------------

TL-200 9x10-1 9x10-1 1x101 1x106

-------------------------------------------------------------------------------------

TL-201 1x101 one 1x102 1x106

-------------------------------------------------------------------------------------

TL-202 2 x 100 2 x 100 1x102 1x106

-------------------------------------------------------------------------------------

TL-204 7 x 10 1x101-1 1x104 1x104

------------------------------------------------------------------------------- ------

Thulium (69)

-------------------------------------------------------------------------------------

TM-167 7x100 an 8 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

TM-170 6 x 10 3x100-1 1x103 1x106

-------------------------------------------------------------------------------------

TM-171 4x101 4x101 1x104 1x108

-------------------------------------------------------------------------------------

Uranium (92)

-------------------------------------------------------------------------------------

U-230 (fast retention) (a), (d) 1 x 10 4x101-1 1x101 (b) 1x105 (b)

-------------------------------------------------------------------------------------

U-230 (medium-fast retention)

(a), (e) 4x101 4 x 10-3 1x101 1x104

-------------------------------------------------------------------------------------

U-230 (slow retention) (a), (f) 3x101 3 x 10-3 1x101 1x104

-------------------------------------------------------------------------------------

U-232 (fast retention) (d) 1 x 100 4x101 1 x 10-2 (b) 1x103 (b)

-------------------------------------------------------------------------------------

U-232 (medium-fast retention) (e) 7 x 10-3 1x101 4x101 1x104

-------------------------------------------------------------------------------------

U-232 (slow retention) (f) 1 x 10-3 1x101 1x101 1x104

-------------------------------------------------------------------------------------

U-233 (fast retention) (d) 4x101 9x10-2 1x101 1x104

-------------------------------------------------------------------------------------

U-233 (medium-fast retention) (e) 2 x 10-2 1x102 4x101 1x105

-------------------------------------------------------------------------------------

U-233 (slow retention) (f) 4x101 6 x 10-3 1x101 1x105

-------------------------------------------------------------------------------------

U-234 (medium-fast retention) (e) 4x101 9x10-2 1x101 1x104

-------------------------------------------------------------------------------------

U-234 (medium-fast retention) (e) 2 x 10-2 1x102 4x101 1x105

-------------------------------------------------------------------------------------

U-235 (all types of retention)

(a), (d), (e), (f) Unlimited Unlimited 1x101 (b) 1x104 (b)

-------------------------------------------------------------------------------------

U-236 (fast retention) (d) Unlimited Unlimited 1x101 1x104

-------------------------------------------------------------------------------------

U-236 (medium-fast retention) (e) 2 x 10-2 1x102 4x101 1x105

-------------------------------------------------------------------------------------

U-236 (slow retention) (f) 4x101 6 x 10-3 1x101 1x104

-------------------------------------------------------------------------------------

U-238 (all types of retention)

(d), (e), (f) Unlimited Unlimited 1x101 (b) 1x104 (b)

-------------------------------------------------------------------------------------

The (natural) Unlimited Unlimited 1 x 100 (b) 1x103 (b)

-------------------------------------------------------------------------------------

U (enriched to 20% or less)

(g) Unlimited Unlimited 1 x 100 1x103

-------------------------------------------------------------------------------------

For (impoverished) Unlimited Unlimited 1 x 100 1x103

-------------------------------------------------------------------------------------

Vanadium (23)

-------------------------------------------------------------------------------------

In the 4 x 10-1-48-1 4 x 10 1x101 1x105

-------------------------------------------------------------------------------------

In-49 4x101 4x101 1x104 1x107

-------------------------------------------------------------------------------------

Tungsten (74)

-------------------------------------------------------------------------------------

W-178 (a) 9x100 5x100 1x101 1x106

-------------------------------------------------------------------------------------

W-181 3x101 3x101 1x103 1x107

-------------------------------------------------------------------------------------

W-185 x 10 4x101-1 1x104 1x107

-------------------------------------------------------------------------------------

W-187 2 x 100 6 x 10-1 1x102 1x106

-------------------------------------------------------------------------------------

W-188 (a) 4 x 10-1 3 x 10-1 1x102 1x105

-------------------------------------------------------------------------------------

Xenon (54)

-------------------------------------------------------------------------------------

XE-122 (a) 4 x 10-1 4 x 10-1 1x102 1x109

-------------------------------------------------------------------------------------

XE-7 x 10-2 x 100 1 123 1x102 1x109

-------------------------------------------------------------------------------------

XE-127 one of 2 x 100 1x103 1x105

-------------------------------------------------------------------------------------

XE-131m 4x101 4x101 1x104 1x104

-------------------------------------------------------------------------------------

XE-133 2x101 1x101 1x103 1x104

-------------------------------------------------------------------------------------

XE-135 2 x 100 3x100 1x103 1x101 0

-------------------------------------------------------------------------------------

Yttrium (39)

-------------------------------------------------------------------------------------

Y-87 (a) 1 x 100 1 x 100 1x101 1x106

-------------------------------------------------------------------------------------

Y-88 4 x 10-1 4 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

Y-90 3 x 10-1 3 x 10-1 1x103 1x105

-------------------------------------------------------------------------------------

Y-91 6 x 10-1 6 x 10-1 1x103 1x106

-------------------------------------------------------------------------------------

Y-2 x 100 2 x 100 1x102 91m 1x106

-------------------------------------------------------------------------------------

Y-92 2 x 10-1 10-1 1x102 1x105

-------------------------------------------------------------------------------------

Y-3 x 10-3 x 10 93 1-1 1x102 1x105
-------------------------------------------------------------------------------------

Yterbium (70)

-------------------------------------------------------------------------------------

Yb-169 one 1 x 100 1x102 1x107

-------------------------------------------------------------------------------------

Yb-175 3x101 9x10-1 1x103 1x107

-------------------------------------------------------------------------------------

Zinc (30)

-------------------------------------------------------------------------------------

Zn-65 of 2 x 100 2 x 100 1x101 1x106

-------------------------------------------------------------------------------------

Zn-69 6 x 10 3x100-1 1x104 1x106

-------------------------------------------------------------------------------------

Zn-trees (a) 6 x 10 3x100-1 1x102 1x106

-------------------------------------------------------------------------------------

Zirconium (40)

-------------------------------------------------------------------------------------

ZR-88 3x100 3x100 1x102 1x106

-------------------------------------------------------------------------------------

ZR-93 Unlimited Unlimited 1x103 (b) 1x107 (b)

-------------------------------------------------------------------------------------

ZR-95 (a) 2 x 100 x 10-1 1x101 1x106

-------------------------------------------------------------------------------------

ZR-97 (a) 4 x 10-1 4 x 10-1 1x101 (b) 1x105 (b)

-------------------------------------------------------------------------------------



(a) the value of the activities of the A1 or A2 or both values include contributions

the radioactive half-life of the conversion products of less than 10 days



(b) radionuclides and radioactive products of their corresponding conversion

a permanent equilibrium are listed below:

SR-90, Y-90

Zr93 Nb-93 m

ZR-Nb-97 97

Ru-106 Rh-106

CS-137 Ba-137m

CE-134 La-134

CE-144 Pr-144

BA-140 La-140

BI-212 Bi-210, Po-210

PB-212, Bi-212, Tl-208 (0.36), Po-212 (64)

RN-220 Po-216

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 (64)

RA-226 Rn-222, Po-218, Pb-214, Bi-214, Po-214,

Pb-210, Bi-210, Po-210

RA-228 Ac-228

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

Th-228 Ra-224, Rn-220, Po-216, Pb212, Bi-212,

Tl208 (0.36), Po-212 (64)

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

After-213, Pb-209

Th natural Ra-228, Ac-228, Th-228, Ra-224, Rn-220,

After-216, Pb-212, Bi-212, Tl-208

(0.36), Po-212 (64)

Th-234 Pa-234m

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

U-232 Th-228, Ra-224, Rn-220, Po-216, Pb-212,

BI-212, Tl-208 (0.36), Po-212 (64)

U-235 Th-231

U-238 Th-234, Pa-234m

In 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

U-240 Np-240 m

NP-237 Pa-233

Am-242 m Am-242

Am-243 Np-239



(c) the quantities can be determined by measuring the speed of conversion or measurement

input of the dose equivalent at a specified distance from the radionuklidového

emitters.



(d) the following values are valid only for the following uranium compounds:

UF6, U2F2, UO2 (NO3) 2.



(e) the following values are valid only for the following uranium compounds:

UO3, UF4, UCl4 and šestimocné compounds of uranium.



(f) the following values are valid for the other uranium compounds, not specified elsewhere in the

points (d) and (e)).)



(g) the following values are valid only for the neozářený uranium.



6. (406) For individual radionuclides or mixtures thereof, for which the

the necessary information is not known, it must be applied to the values listed in the table

2 (II) of the annex No 3.



Table 2. (II.) the basic values of radionuclides for unknown radionuclides

and mixtures

-------------------------------------------------------------------------------------

Radionuclides A1 A2 Limits Limits

weight activities

activities for removal

for cutting supplies

the substance

-------------------------------------------------------------------------------------

[A TBq] [A TBq] [Bq/g] [Bq]

-------------------------------------------------------------------------------------

It is known only by the presence of

radionuclides emitting

beta or gamma radiation 0.1 0.02 1x101 1x104

-------------------------------------------------------------------------------------

It is known only by the presence of

radionuclides emitting

Alpha 9x10 0.2-5 1 x 10-1 1x103

-------------------------------------------------------------------------------------

No data available 0.001 9x10-5 1 x 10-1 1x103

-------------------------------------------------------------------------------------



The limits of the radioactive content of radioactive shipments



7. (407.) The quantity of fissionable material or radioactive substances in

radioactive shipment shall not exceed the applicable limits referred to in

paragraphs 8. -20. Annex No. 3.



Exempt consignment



8. (408.) Cut the consignment for fissile material or radioactive substance

other than the items are made from natural uranium, depleted uranium,

or natural thorium must not contain more than the following activities:



(a) where there is a fissile material or radioactive substance incorporated or

included as part of the unit or another product, such as a clock

or electronic apparatus, the limits specified in columns 2.

and (3). table 3. (III) Annex 3 for each individual item and

each radioactive shipment (in this order);



(b) where the fissile material or radioactive substance is as follows

incorporated or is not included as part of the device or other

the product applies limits for radioactive shipment specified in the column

4. table 3. (III) Annex No. 3.



9. (409). Cut the consignment for products made from natural uranium,

depleted uranium or natural thorium, may contain any

the quantity of such substances, provided that the outer surface of the uranium or

Thorium is enclosed in an inactive sheath made of metal or any other

the hard material.



10. (410). For the carriage of mail, the total activity of each cut

shipments shall not exceed one-tenth of the appropriate limit specified in table

3 of annex 3.



Industrial shipments, type 1, type 2 and type 3



11. (411) The radioactive contents in a single consignment of radioactive substances, LSA

According to annex No 1 paragraph 1) or SCO specified in annex 3, paragraph

12) must be limited so that the input dose equivalent is specified

in paragraph 21. Annex No. 4 must not be exceeded, and the activity in one

radioactive shipment must be limited so that the activity limits for the

means of transport specified in paragraph 25. Annex No. 4 were

are exceeded.



12. (241.) SCO-surface contaminated object the hard subject matter,

that itself is not radioactive, on whose surface is dispersed, however, fissile

material or radioactive substance. Surface contaminated objects

sorted into one of two groups:



(a) SCO: a hard subject, on which at the same time



(i) the nefixovaná contamination on the accessible surface area of an average of 300

cm2 (or on the entire surface, if less than 300 cm2) does not exceed 4 Bq/cm2

(for beta and gamma emitters and low toxicity alpha emitters, or 0.4 Bq/cm2

for all other alpha emitters and



(ii) the fixed contamination on the accessible surface area of an average of 300

cm2 (or on the entire surface, if less than 300 cm2) does not exceed 4.104

Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters, or

4.103 Bq/cm2 for all other alpha emitters and



(iii) the sum of unfrozen and frozen contamination on the inaccessible surface

more than 300 cm2 (or the area if less than 300 cm2)

4.104 does Bq/cm2 for beta and gamma emitters and alpha emitters with low

toxicity, or 4.10 E3 Bq/cm2 for all other alpha emitters;



(b) SCO (II): a solid object on which either the fixed surface exceeds the

or nefixovaná contamination limits applicable under (a) for SCO and and

on which at the same time



(i) the nefixovaná contamination on the accessible surface area of greater than 300

cm2 (or on the entire surface, if less than 300 cm2) does not exceed 400

Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters, or 40

Bq/cm2 for all other alpha emitters and



(ii) the fixed contamination on the accessible surface area greater than 300

cm2 (or on the entire surface, if less than 300 cm2) does not exceed 8.10 E5

Bq/cm2 for beta and gamma emitters and low toxicity alpha emitters or 8.104

Bq/cm2 for all other alpha emitters and



(iii) the sum of unfrozen and frozen contamination on the inaccessible surface

with an area of more than 300 cm2 (or the area if less than 300 cm2)

8.105 does Bq/cm2 for beta and gamma emitters and alpha emitters with low

toxicity or 8.104 Bq/cm2 for all other alpha emitters.



Table 3. (III) the limits of the activities for the cut of the consignment

-------------------------------------------------------------------------------------

The physical state of the content of the instrument or product of a substance-
(State)-----------------------------------------limits

The limits for the items, and the limits for radioactive)

radioactive cargo zásilkya)

-------------------------------------------------------------------------------------

Fixed

-------------------------------------------------------------------------------------

A special form of 10-2 A1 A1 A1 10-3

-------------------------------------------------------------------------------------

other forms 10-2 10-3 A2 A2 A2

-------------------------------------------------------------------------------------

Liquid 10-3 A2 10 A2-1 to 10-4 A2

-------------------------------------------------------------------------------------

Gaseous

-------------------------------------------------------------------------------------

tritium 2 x 10-2 A2 2 x 10-1 10-2 A2 A2

-------------------------------------------------------------------------------------

a special form of 10-3 A1 10-2 A1 10-3 A1

-------------------------------------------------------------------------------------

other forms 10-3 A2 10 A2-3 10-3 A2

-------------------------------------------------------------------------------------



for mixtures of radionuclides), see paragraph 4. -6. Annex No. 3.



13. (412) One radioactive shipment of non-combustible solid LSA II or

LSA III, if transported by air, shall not contain an activity greater

than 3000 A2.



Radioactive cargo type and



14. (413.) The type of the consignment, and shall not contain activities greater than:



(a) the value of A1; for special form radioactive material, or



(b) the value of A2; for all other radioactive material



15. (414.) For mixtures of radionuclides whose identities and respective activities

are known, the following condition shall apply to the radioactive contents of the consignment

type:



(i) sumaB/A1 (i) + sumaC (j)/A2 (j) < = 1,

i j



where:



(B) (i) is the activity of radionuclide i as radioactive

special forms of the substance,

A1 (i) the value of A1 for radionuclide i,

(C) to (j) is the activity of radionuclide j other than

special forms of radioactive substance and A2 (j)

the value of A2 for a radionuclide j.



Radioactive cargo type B (U) and B (M)



16. (415.) Consignments of type B (U) and (B) (M) shall not contain:



(a) higher activities than those that were intended for the design type,



(b) other radionuclides than that were intended for the design type,

or



(c) radioactive contents in a form or physical or chemical state

other than that it was designed for the type of design and content are

a decision on the type of approval.



17. (416.) Consignments of type B (U) and (B) to (M), transported by air must comply with the

the requirements of paragraph 16. Annex No 3 and shall not contain more than

the following activities:



(a) for a few rozptýlitelné radioactive substances-both are designed for

the type of construction,



(b) for special form radioactive material-3000 A1 or 100 000 A2,

Depending on which of these values is lower,



(c) for all other fissile materials and radioactive substances-3000

A2,



Radioactive cargo type C



18. (417.) Consignment type C must not contain:



(a) higher activities than those that were intended for the design type,



(b) other radionuclides than that were intended for the design type,

or



(c) radioactive contents in a form or physical or chemical state

other than that it was designed for the type of design and content are

a decision on the type of approval.



Radioactive shipments containing fissile material



19. (418). Radioactive shipments containing fissile material shall not

include:



(a) the mass of fissile material different from that which was intended for

the type of construction,



(b) any radionuclides or fissile materials different from those which

they were intended for the design type, or



(c) radioactive contents in a form or physical or chemical state, or

in a special arrangement other than that they were intended for the

design type as specified in the decisions about their approval,

If such a decision requires.



Radioactive shipments containing uranium hexafluoride



20. (419) The weight of the hexafluoridu uranium radioactive shipment shall not

exceed a value that would cause the free space in the package

(packaging) would be less than 5% of the volume specified in the

the maximum temperature for the device, which will be radioactive

the consignment is used. Uranium hexafluoride must be solid and

the internal pressure in the radioactive shipment shall be at the time of transfer to the

transport lower than atmospheric pressure.



------------------------------------------------------------------



*) Note



Positional numbers printed in bold in parentheses according to paragraph numbers,

where appropriate, tables and pictures correspond to the numbering of the recommendations

The International Atomic Energy Agency, "the IAEA Safety Standards

Series, Regulations for the Safe Transport of Radioactive Material,

1996 Edition (Revised), Requirements, No. TS-R-1 (ST-1, Revised),

The International Atomic Energy Agency, Vienna, 2000 ". For this attachment

apply the interpretation of the concepts referred to in the abovementioned document from paragraph 201 to

paragraph 248.



Annex 4



The security requirements for the transport of



Requirements before the first shipment



1. (501). *) Before the first shipment of radioactive consignments must be met

the following requirements:



(a) if the pressure exceeds the projected 35 kPa of the restraint system, shall

ensure that the restraint system of each radioactive shipments match

approved to the requirements of the project due to the ability of this system

keep the integrity when exposed to such pressure,



(b) for each of the radioactive shipment of type B (U), (B) to (M) and (C), and for each

radioactive shipment containing fissile material shall be provided to

the effectiveness of the shielding and the restraint system, and if it is needed,

properties of heat transfer and efficiency of the restrictive system, were within the

the emission limit values applicable to the approved design type or

described,



(c) any radioactive shipment, which contains fissile material and to

that have been assigned added neutron poisons as part thereof, must be

subjected to tests to detect the presence and distribution of these

Neutron poisons, to comply with the provisions of paragraph 77. (I).

Annex No 1.



The requirements before each shipment



2. (502). Before each shipment of radioactive consignments must be met

the following requirements:



(a) for all radioactive shipments must comply with all

requirements, appropriate to the type of radioactive cargo,



(b) the lifting handles, do not meet the conditions referred to in paragraph 12. point

I. Annex No 1, must be removed or otherwise made

nepouživatelnými for the lifting of radioactive consignments in accordance with

paragraph 13. the point I of annex 1,



(c) for each of the radioactive shipment of type B (U), (B) to (M) and (C), and for each

radioactive shipment containing fissile material must be met

all the conditions laid down in the decision about the type approval,



(d) any radioactive shipment of type B (U), (B) to (M) and (C) and each radioactive

the consignment containing fissile material shall not be transported before the

reaches the equilibrium conditions are sufficiently close to the conditions of the corresponding

the requirements for temperature and pressure for the transport, if this is not an exception from the

These requirements included in the type approval.



(e) for each of the radioactive shipment of type B (U), (B) to (M) and (C), and for each

radioactive shipment containing fissile material must be control or

appropriate tests examined, that all closures, valves or other

the openings of the restraint system, which could leak radioactive contents are

enclosed in an appropriate manner and, where appropriate, provided with a seal as the test

proof of compliance with the requirements of paragraph 62. and 75. the point I of annex 1,



(f) for each special form radioactive substance must meet all

the conditions laid down in the decision on the type of approval and all

the relevant requirements,



(g) for radioactive shipments containing fissile material must be

ensure the implementation of the measure described in paragraph 80. (b) of section I of the annex.

No 1 and tests each radioactive consignments closedness in accordance with paragraph

83. section I of Annex No. 1, if applicable,



(h) any radioactive substance with a little rozptýlitelností must comply with the

all the conditions laid down in the decision on the type of approval and all

the corresponding requirements.



The transport of other goods



3. (503). Radioactive shipment shall not, outside of documents and objects

needed for the handling of fissile material or radioactive substance,

that are part of the consignment, contain nothing else. These terms and conditions

shall not preclude the transport of substances with low weight and surface activity

contaminated objects with other items. Transport of substances with low

the mass activity or surface contaminated objects together with the

other kinds of stuff is allowed, provided that cannot be

interaction between them and the packaging or its file

radioactive contents that would reduce the safety of the radioactive

the consignment.



4. (504.) Tanks and containers of medium size on the bulk stuff
(IBC), which are used for the carriage of radioactive material shall not be

used for transit storage or transport of other goods, if

have not been decontaminated, so that the nefixovaná surface contamination for

gamma emitters, beta emitters and low toxicity alpha emitters with not more

than 0.4 Bq/cm2 for all other alpha emitters and not more than 0.04 Bq/cm2.

Contamination with low toxicity alpha emitters is the contamination of the natural

uranium, depleted uranium, natural uranium-235, thoriem, or

uranium-238, thoriem-232, thoriem, and thoriem-228-230 contained in ores

and chemical concentrates or alpha emitters with a half-life of less than

ten days. Contamination that can be removed from the surface, under normal

the conditions during transport is nefixovaná, any other is the contamination of the

fixated.



5. (505.) The transport of other goods with delivery carriage under the conditions

exclusive use, which is the use of the means of transport or a large

shipping container with a single carrier, in consequence of which are

all loading and unloading, starting, in the course of shipment and the final,

carried out in accordance with his instructions, is permitted, provided that the transport of

This is organized solely by the carrier and is not disabled on the basis of the

other terms and conditions. While the shipment is radioactive shipment, consignment, or

a cargo of radioactive substances being passed by the carrier for carriage (hereinafter referred to as

delivery).



6. (506.) The shipment must be accompanied during transportation and storage of transit

separated from other dangerous goods in accordance with the relevant provisions

for the transport of dangerous goods in each country, through which or into which the

fissile material or radioactive substance transported, where appropriate, with

regulations of the carrier, as well as with the requirements.



The security of the transport of radioactive shipments with other dangerous

the characteristics of the content



7. (507). When packing, labelling, placing tags, storage and

the transport must be taken into account in addition to the radioactive and fissile

properties and other dangerous properties of the radioactive cargo, as

explosivity, flammability, chemical toxicity of impulsiveness and korosivnost with

to ensure compliance with the relevant regulations for the transport of dangerous

Affairs of each country, through which or into which the fissionable material or

radioactive substance transported, where appropriate, with the provisions of the carrier, as well as

with the requirements.



Check and requirements in terms of contamination and leakage of radioactive

consignments



8. (508). Nefixovaná on the outer surface of the radioactive contamination

the consignment must be maintained at the lowest achievable level and in practice

in normal conditions of transport, shall not exceed the following limits:



(a) 4.0 Bq/cm2 for beta and gamma emitters and for alpha emitters with low

toxicity and



(b) 0.4 Bq/cm2 for all other alpha emitters.



Note



The above limit levels are considered as zprůměrnění the results of the

abrasion areas 300 cm2 on any part of the surface.



9. (509.) Except as provided in paragraph 14. Annex No 4 shall not

exceed the level of contamination of the unfrozen on external and internal

surfaces of the outer packaging, shipping containers, storage tanks and containers

middle size to bulk things limits laid down in paragraph 8.

Annex No. 4.



10. (510). If it is clear that the radioactive shipment is damaged or that

leaking or if it is suspected that radioactive shipment was damaged

or was it leaks, it must be restricted and a qualified person

as soon as possible to evaluate the input dose equivalent and the range of

contamination of such consignments. The evaluation must be carried out due to the

radioactive shipment, means of transport, places of loading and unloading

including adjacent and, if necessary, to all other

the materials, which were in the vehicle. In the case of

If necessary, further measures must be taken to protect the health, property and

of the environment in accordance with the conditions laid down in the applicable laws

legislation in order to eliminate or reduce as far as possible the consequences of the leak

(the leak) or damage.



11. (511). Radioactive shipments for which the escape of the radioactive contents

exceeds the limits permitted for normal conditions of transport, shall not be considered

shut down the surveillance at the appropriate place, but may not be transported further,

If you have not been repaired or otherwise put into a proper State and

decontaminated.



12. (512). Means of transport and equipment used for the usual

transport of radioactive substances must be regularly checked for

the determination of the levels of contamination. The frequency of such inspections must comply with the

the likelihood of contamination and the quantity transported radioactive

substances.



13. (513.) Except as provided in paragraph 14. Annex No. 4 must be

all means of transport, equipment, or parts thereof, which

during the transport of radioactive substances contaminated above the limits

laid down in paragraph 8. Annex No 4 or exhibit the power of batch

the equivalent of more than 5 mikroSv/h, decontaminated as soon as possible

by the qualified person; must not be used again, if nefixovaná

contamination in excess of the limits laid down in paragraph 8. Annex No. 4 and if

It is not power equivalent, resulting from the fixed contamination

on the surface, after decontamination is less than 5 mikroSv/h.



14. (514). The outer packaging, shipping containers, tanks, containers

medium size on the bulk of the case or means of transport

for the transport of radioactive substances transported under the conditions of an exclusive

use, are excluded from the terms of paragraphs 9. and 13. Annex No. 4, but

only in regard to its internal surfaces and only for as long as you

This exclusive use remain.



Control and the requirements for the transport of the exempted shipments



15. (515.) Cut the consignment shall be subject to further requirements



(a) in paragraphs 7., 8., 11., 16., 34. -36., 49. (c), 54. and

the relevant requirements of paragraph 17. -20. Annex No 4,



(b) in paragraph 25. the point I of Annex No. 1 to cut the consignment,



(c) in paragraph 40. the point I of Annex No. 1, if it is to cut the consignment

containing fissile material and at the same time that meet one of the requirements

paragraph 78. the point I of annex 1,



(d) in paragraphs 79. and 80. Annex No. 4, in the case of carriage by post.



16. (516). Input equivalent anywhere on the outer

the surface of the cut shipments shall not exceed 5 mikroSv/h.



17. (517) fissile materials or radioactive substances, which are

enclosed in the device or included in the product or form a part of these

objects and their activity at the same time does not exceed the limits laid down for the

the item and for the radioactive shipment in 2 columns. and (3). table 3

(III) Annex No. 3 may be carried as cut consignment

current compliance with the following conditions:



(a) input dose equivalent at a distance of 10 cm from any

place the outer surface of the part of the apparatus or product is not greater than

0.1 mSv/h,



(b) each instrument or any product (except the hours or the device

bearing the markings made on the basis of glowing colors

radioluminiscence) bears the words "Radioactive"



(d) fissile material or radioactive substance is completely closed inactive

compound (a device whose sole purpose is to contain

radioactive material cannot be considered as instrument or product in the above

that meaning).



18. (518) fissile materials or radioactive substances other than forms

described in paragraph 17. Annex No. 4 may be carried as

cut the consignment, if the activity does not exceed the limits laid down in column 4.

table 3 (III) of annex 3 and for the current meet the following

assumptions:



(a) radioactive shipment will keep its radioactive contents under the conditions

common transport



(b) the radioactive shipment is on the inner surface of the packaging bears the inscription

"Radioactive", so the opening is visible warning on

the presence of fissionable material or radioactive substances.



19. (519.) The product, which are the only fissile materials or

radioactive substances neozářený, neozářený natural uranium depleted uranium

or non-irradiated natural thorium may be transported as cut

the consignment, provided that the external surfaces of the uranium or thorium content have

inactive sheath made of metal or other hard materials.



Checking and additional requirements for transport of empty packaging



20. (520). Empty packaging the file that contained the fissile material or

radioactive substances can be transported as a common consignment

current compliance with the following conditions:



(a) the packaging file is in accordance with the requirements of and safely closed,



(b) the outer surface of each of its components of the uranium or thorium is enclosed

an inactive sheath made of metal or other hard materials,



(c) the level of contamination of the unfrozen on his inner surface does not exceed

one hundred times the limits laid down in paragraph 8. Annex No 4,



(d) all the stickers that can be placed on it in accordance with the

paragraph 41. Annex No 4 are obscured, degraded or removed.



Control and the requirements for the transport of radioactive substances of low

the mass activity (LSA) and surface contaminated objects (SCO)

Industrial packages or unpackaged
21. (521) The quantity of substances, LSA or SCO in a single industrial consignment type 1

(IP-1), type 2 (IP-2), type 3 (IP-3) or subject, or, where appropriate, file

subjects must be limited to the external power input dose equivalent

at a distance of 3 m from the unshielded substance or object or file

items does not exceed 10 mSv/h.



22. (522) The substance of the LSA and the SCO that are fissile materials or fissile

the materials contain, must comply with the relevant conditions of paragraphs 68. and

69. the annex No. 4 and paragraph 77. the point I of Annex No. 1.



23. (523) The substance of the LSA and SCO in groups LSA-I and SCO-I may be

transported unpackaged under the following conditions:



and all unpacked substances) other than ores that contain radionuclides,

occurring exclusively in nature, must be transported, so that for

the conditions of the normal transport of the radioactive contents from the transport cannot

resource leak, and can cause loss of shielding.



(b) each means of transport) must be used only for the transport of a

conditions of an exclusive use, unless it were transported only

the subjects of the SCO-I on which the contamination on the accessible level is not and

inaccessible surfaces greater than 10 times the limit referred to in paragraph

4. Annex 4,



c) inaccessible surfaces for the SCO Group-I must be higher

the level of contamination of the unfrozen, until it corresponds to the values laid down in

paragraph 12. (a) (i) of point I of annex 3, otherwise, it must be

measures to ensure that fissile materials or

radioactive substances cannot escape to a means of transport.



24. (524) The substance of the LSA and SCO must be packed in accordance with the requirements of

table 1. (IV) of the annex No 4, if not in paragraph 23. Annex No 4

otherwise specified.



25. (525) The total activity of the substances, LSA and SCO in a single ship

space or waterproof section of the ship for the river cruise or in another

means of transport in radioactive consignments type IP-1, IP-2, IP-3

or unpackaged, shall not exceed the limits laid down in table 2. (In.)

Annex No. 4.



Table 1. (IV) the requirements for industrial shipments for LSA and SCO

------------------------------------------------------------------

Type of industrial shipments

Radioactive contents-------------------------------------------

Carriage under the conditions of the other transport

the exclusive use of the

------------------------------------------------------------------

LSA-I Pevnýa) type IP-1, Type IP-1

Liquid Type IP-1, Type IP-2

------------------------------------------------------------------

LSA-II hard Type IP-2, Type IP-2

Liquid Type IP-2, Type IP-3

------------------------------------------------------------------

LSA-III Type IP-2, Type IP-3

------------------------------------------------------------------

SCO-Ia Type IP-1, Type IP-1

------------------------------------------------------------------

SCO-II type IP-2, Type IP-2

------------------------------------------------------------------



and) under the conditions described in paragraph 23. Annex No. 4 may be

LSA-I and SCO-I transported unpackaged.



Table 2. (V) the limits of the activity for the substance of the LSA or SCO in industrial

packages or unpackaged

--------------------------------------------------------------------------------------

The type of substances Bound activity Limit activities

for the means of transport for shipping space

other than a ship or vodotěsnýúsek

for the river cruise boat for říčníplavbu

--------------------------------------------------------------------------------------

LSA-I Unlimited Unlimited

--------------------------------------------------------------------------------------

LSA-II and LSA-III Unlimited 100 A2

solid non-combustible substances

--------------------------------------------------------------------------------------

LSA-II and LSA-III 100 A2 10 A2

hard flammable substances and all

liquid substances and gases

--------------------------------------------------------------------------------------

SCO 100 A2 10 A2

--------------------------------------------------------------------------------------



Table 3. (VI) cost of the multiplication Factors for large dimensions



------------------------------------------------------------------

The dimensions of the nákladua) the multiplication factor

------------------------------------------------------------------

up to 1 m2 1

------------------------------------------------------------------

from more than 1 m2 to 5 m2 2

------------------------------------------------------------------

from more than 5 m2 up to 20 m2 3

------------------------------------------------------------------

from more than 10 to 20 m2

------------------------------------------------------------------



and Established as the largest area of) possible cross-section of cargo



Determination of transport index



26. (526.) The transport index (TI) for radioactive shipment, packaging,

shipping container unpacked substances or unpackaged LSA-I and SCO-is the number

derived on the basis of the following procedure:



(a) found the highest wattage dose equivalent in mSv/h

the distance of 1 m from the external surfaces of the radioactive cargo, the outer

packaging, or shipping container, or unpackaged LSA-I or substances

SCO-I, shall be multiplied 100 and the resulting number is the transport index



(b) for uranium and thorium ores and their concentrates are for the highest

příkony dose equivalent at a distance of 1 m from the external surfaces

set these values



(i) 0.4 mSv/hpro uranium and thorium ores and their concentrates, physics



(ii) 0.3 mSv/hpro chemical concentrates of thorium;



(iii) 0.02 mSv/hpro chemical concentrates of uranium, in addition to the hexafluoridu

uranium,



(c) for tanks, containers and unpackaged LSA-I substances and SCO-I

the value obtained in accordance with point (a) is multiplied by the corresponding factor from

table 3. (VI) Annex No 4,



(c) values obtained in accordance with points (a) and (b) shall be rounded up to the

one decimal place (e.g. from 1.13 will be 1,2), except the value of 0.05

or lower, which may be considered as zero.



27. (527) The transport index for the outer packaging, shipping container or

the means of transport shall be determined as either the sum of the transport

indices of radioactive shipments, or by direct measurement of the batch input

equivalent. The exception are the loose outer packaging, which shall be

the transport index determined only as the sum of the transport indexes all

radioactive shipments contained in them.



Determination of transport index for the conservation of podkritického State



28. (528) The transport index for the conservation of podkritického State

(CSI) for radioactive shipments containing fissile material shall be obtained

by dividing the number 50 of the smaller of the two values of "N", implied in paragraphs 87.

and 88. Part I of Annex No 1 (IE. CSI = 50/N). The value of the transport

the index of the conservation status of the podkritického can be zero for

provided that an unlimited number of radioactive consignments is podkritický

(i.e., the "N" are virtually equal to infinity in both cases).



29. (529) The transport index for the conservation of podkritického State

for each shipment must be determined as the sum of all individual CSI

radioactive shipments in shipment contained.



The limits for the transportation index, the index of transport in terms of conservation

podkritického the status and power of the radioactive dose equivalent

mail and packaging



30. (530). The transport index of individual radioactive shipments or

the outer packaging shall not, with the exception of supplies transported under the conditions

exclusive use shall not exceed 10, and the transport index in terms of

the conservation status of the individual podkritického of radioactive shipments or

the outer packaging shall not exceed 50.



31. (531) Power dose equivalent, with the exception of radioactive

consignments and external packaging carried under the conditions of an exclusive use

by rail or road, in accordance with the conditions laid down in paragraph

72. (a) the annex No. 4, or the radioactive shipments and packaging

carried under the conditions of an exclusive use and under the specific conditions

vessel or by air in accordance with the conditions laid down in paragraphs

74.78, respectively. Annex No 4, not power equivalent to the

elsewhere in the outer surface of the radioactive shipments or external

package exceed 2 mSv/h.



32. (532) Maximum power equivalent to any location

the outer surface of the radioactive consignments transported under the conditions

exclusive use shall not exceed 10 mSv/h.



Table 4. (VII) the category of radioactive consignments and packaging

--------------------------------------------------------------------------------------

The Conditions Category

----------------------------------------------------------------------

The transport index (TI) maximum power equivalent

anywhere on the outer surface of the

--------------------------------------------------------------------------------------

0a) no more than 0.005 mSv/h I-white

--------------------------------------------------------------------------------------
more than 0, more than 0.05 mSv/h but not more

but not more than 1a) than 0.5 mSv/h II-yellow

--------------------------------------------------------------------------------------

more than 1, more than 0.5 mSv/h but not more

but not more than 10 mSv/h 2 III-yellow

--------------------------------------------------------------------------------------

more than 10 of more than 2 mSv/h but not more

than 10 mSv/h III-žlutáb)

--------------------------------------------------------------------------------------



and) if not measured transport index greater than 0.05, the transmission can be

the index referred to in paragraph 26. (c) of the annex No 4 is considered equal to 0.



(b)) must be transported under the conditions of an exclusive use.



Category of radioactive consignments and packaging



33. (533) Radioactive shipments and the outer packaging must be included in the

one of the categories I-white, II-YELLOW or III-YELLOW in accordance with the conditions,

set out in table 4. (VII) of annex 4 and the following

terms and conditions:



(a) in determining the appropriate category for the radioactive shipment and outer

the packaging must be respected at the same time the transport index and the batch input

equivalent on the surface. If the transport index satisfies the condition for one

category, but power consumption equivalent to surface the value

corresponds to a different category, the radioactive shipment or external

cover to the higher of the two categories. In this context, category I-white

It considers the lowest category,



(b) the transport index shall be determined in accordance with the procedure laid down in paragraphs

26 and 27. Annex No 4,



(c) If a power equivalent to a surface greater than 2 mSv/h,

the consignment must be radioactive or outer package is transported under the conditions

exclusive use and in accordance with the relevant conditions of paragraphs 72. (a), 74.

or 78. Annex No 4,



(e) radioactive shipment transported under special conditions,

be assigned to category III-yellow,



(f) the outer packaging, containing the radioactive shipment, carriage for

the special conditions, shall be assigned to category III-YELLOW.



Table 5. (VIII) the selection from the list of numbers of the United Nations,

proper shipping names and descriptions, additional risks.

-------------------------------------------------------------------------------------

The correct number, and Additional shipping)

The United Nations and a description of the risk

-------------------------------------------------------------------------------------

2910 radioactive substance,

cut the consignment-limited quantity

-------------------------------------------------------------------------------------

2911 radioactive substance,

cut the consignment-device or (b)) products

-------------------------------------------------------------------------------------

2909 radioactive substance,

cut the consignment-products from natural uranium

or depleted uranium or thorium

-------------------------------------------------------------------------------------

2908 radioactive substance,

cut the consignment-empty packaging

-------------------------------------------------------------------------------------

2912 radioactive substance, low mass activity

(LSA-I), other than fissile material or cut

fissile material

-------------------------------------------------------------------------------------

3321 radioactive substance, low mass activity

(LSA-II), other than fissile material or cut

fissile material

-------------------------------------------------------------------------------------

3322 radioactive substance, low mass activity

(LSA-III), other than fissile material or cut

fissile material

-------------------------------------------------------------------------------------

2913 radioactive substance,

surface contaminated objects (SCO-I or SCO-II)

other than fissile material or cut fissionable material

-------------------------------------------------------------------------------------

2915 radioactive substance, radioactive shipment type and

other than the specific form of the radioactive substance, other

than fissile material or cut fissionable material

-------------------------------------------------------------------------------------

3332 radioactive substance, radioactive shipment of type A,

special forms of radioactive substance

other than fissile material or cut fissionable material

-------------------------------------------------------------------------------------

2916 radioactive substance, radioactive shipment of type B (U)

other than fissile material or cut fissionable material

-------------------------------------------------------------------------------------

2917 radioactive substance, radioactive shipment of type B (M)

other than fissile material or cut fissionable material

-------------------------------------------------------------------------------------

3323 radioactive substance, radioactive shipment of type (C)

other than fissile material or cut fissionable material

-------------------------------------------------------------------------------------

2919 radioactive substance, transport under special conditions

other than fissile material or cut fissionable material

-------------------------------------------------------------------------------------

2978 uranium hexafluoride, a radioactive substance Corrosive substance

other than fissile material or cut fissionable material (class 8)

-------------------------------------------------------------------------------------

3324 radioactive substance, low mass activity (LSA-II),

fissile material

-------------------------------------------------------------------------------------

3325 radioactive substance, low mass activity (LSA-III),

fissile material

-------------------------------------------------------------------------------------

3326 radioactive substance, surface contaminated objects

(SCO-I or SCO-II), fissile material

-------------------------------------------------------------------------------------

3327 radioactive substance, radioactive shipment of type A,

fissile material

other than special form radioactive substance

-------------------------------------------------------------------------------------

3333 radioactive substance, radioactive shipment of type A,

special forms of radioactive substance,

fissile material

-------------------------------------------------------------------------------------

3328 radioactive substance, radioactive shipment of type B (U),

fissile material

-------------------------------------------------------------------------------------

3329 radioactive substance, radioactive shipment of type B (M)

fissile material

-------------------------------------------------------------------------------------

3330 radioactive substance, radioactive shipment of type (C),

fissile material

-------------------------------------------------------------------------------------

3331 radioactive substance,

transport under special conditions

fissile material

-------------------------------------------------------------------------------------

2977 uranium hexafluoride, a radioactive substance, Corrosive substance

fissionable material (class 8)

-------------------------------------------------------------------------------------



the correct name of transport) can be found in the section "the correct shipping

the name and description "and is limited to the portion of the submitted in all capital letters. In the case of

UN and UN 2909 2911 must enjoy only the corresponding correct shipping

the correct name of the alternative transport names that are separated by

the words "or".



(b)) Cut fissile materials are those fissile materials which meet the

the provisions of paragraph 78. the point I of Annex No. 1.



Marking, labelling and signs



Labelling



34. (534.) Each radioactive shipment must be clearly legible and

durably marked on the outside surface of the designation, where appropriate, the carrier

the recipient, or both.



35. (535) Each radioactive shipment, with the exception of the exempted shipments

must be clearly legible and durably marked on the outside surface of the

a number of the United Nations (UN number), from which hang

the letters "UN" and the proper shipping name. If you cut the consignment,

they have not been admitted to the international mail transport must be marked only

the UN number, before which hang the letters "UN". For radioactive

consignments accepted for international mail transport, the provisions

paragraph 80. Annex No. 4.



36. (536.) Each radioactive shipment of gross weight greater than 50

kg shall be clearly legible and durably marked on the outside surface of the

the indication of the actual gross weight.



37. (537.) Each radioactive shipment, which corresponds to the design

type:



(a) industrial consignment type 1, 2 or 3 shall be clear, legible and

durably marked on the outside surface of the competent of the inscriptions "type IP-1",

"Type IP-2" or "type IP-3"



(b) the shipment of type and must be clearly legible and durably marked on the

the outer surface of the words "and TYPE",
(c) industrial cargo type 2, 3 or a radioactive cargo type and must

be clearly legible and durably marked on the outside surface of the

distinguishing sign for vehicles in international traffic (VRI code) of the country

the origin of the design-type and the manufacturer or other

identification of radioactive consignments laid down by the Office.



(Fig. a). 1. (1.) Basic třílistý symbol of dimensions derived from the

the central circle of RADIUS X. The minimum allowable size of X is 4 mm.



38. (538) Each radioactive shipment, which corresponds to the type-

the approved design type shall be clearly legible and durably

marked on the outer surface:



(a) the identification mark allocated to the Office,



(b) the serial number, uniquely identifying each package file

for the type-approved design type,



(c) the words "type B (U)" or "type B (M)" for the radioactive shipment type

B (U) or type B (M)



(d) the words "type C" for radioactive shipment type (C).



39. (539.) Radioactive consignments of type B (U), type B (M) or type C must be

on the outer surface of the place, which is resistant to fire and water, marked with

třílistým symbol, the model shows the figure. l (1.), stamping,

by extracting or otherwise, that is resistant to fire and water.



(Fig. a). 2. (2). Category I-white sticker. The background must be white stickers,

the color of the třílistého symbol and text must be black, and the color of the Strip

identifying the category must be red. [= radioactive, radioactive

CONTENTS = CONTENTS, ACTIVITY = ACTIVITY, minimum dimension = minimum

dimension. ]



40. (540). If the substance of the LSA-I or SCO-I contained in containers or

packed in packing materials transported under the conditions of an exclusive

use, in accordance with paragraph 23. Annex No 4, must be on the outer surface of the

These containers or packing the appropriate designation, either "RADIOACTIVE SUBSTANCE

LSA-I "or" RADIOACTIVE SCO-I "SUBSTANCE.



Labelling



41. (541.) All radioactive shipments, the outer packaging and shipping

the containers must be accompanied by the appropriate category labels according to the

the designs on the figure. 2 (2) (fig. a). 3 (3), or (fig. a). 4 (4) with the exception of the large

shipping containers and tanks, for which it is allowed to use

alternative measures pursuant to the requirements of paragraph 46 stickers. Annex

4. In addition, any radioactive shipment, packaging and shipping

container containing fissile material, with the exception of fissionable material

cut on the basis of the requirements of paragraph 78 of annex I, point 1, shall

be provided with a sticker in accordance with the model in Figure 1. 5. Stickers, which are

do not apply to the content must be removed or covered. For fissile

materials or radioactive substances with other dangerous properties

the provisions of paragraph 7. Annex No. 4.



(Fig. a). 3. (3). Category II-yellow sticker. The background of the top half of the sticker

must be yellow and the bottom half white, the colour of the symbol and text třílistého

must be black, and the color of the stripes indicating the category must be red.

[= radioactive, radioactive CONTENTS = CONTENTS, ACTIVITY = activity

the minimum dimension = minimum dimension, TRANSPORT = TRANSPORT INDEX

The INDEX. ]



42. (542) Labels according to the designs. 2 (2) (fig. a). 3 (3), or (fig. a). 4

(4.) must be installed on the outer surface of the two opposite parties

radioactive shipments, the outer packaging or on the external surface of all four

Parties of the shipping container or tank. If the obligation to apply the measures

labels according to the pattern in Figure 1. 5 (5), must be placed in these stickers

the immediate vicinity of the labels on the models. 2 (2) (fig. a). 3 (3),

or fig. 4. (4). The labels must not conceal the marking provided for in

paragraphs 34. up to 39. Annex No. 4.



Fill in the labels according to the radioactive content of the



43. (543.) Each sticker on the models. 2 (2) (fig. a). 3 (3), or

(fig. a). 4. (4). must be filled in the following data:



(a) the contents of the consignment



(i) outside substances LSA-I shall be filled in the name of the radionuclide on the label

According to table 1. (1) Annex 3 using the symbols listed in it. For

a mixture of radionuclides, the most restrictive nuclides shall be filled in, if it allows the

the space that is available in the row. The appropriate LSA or SCO Group

must be registered in the name of the radionuclide. To apply expressions

"LSA-II", "LSA-III", "SCO-I" and "SCO-II";



(ii) for LSA-I is "LSA-I" is sufficient, the name of the radionuclide

is not necessary.



(b) the maximum activity of the radioactive contents during transport expressed

in as becquerels relative (Bq) with the appropriate prefix'S hanging units. U

fissile materials may be given instead of the total weight of the activity in

grams (g) or in multiples,



(c) for the outer packaging and shipping containers have the records for "content" and

"activity" on the labels correspond to the relevant data required

paragraph 43. (a) and 43. (b) of the annex No 4, where the total content

the outer packaging and the shipping container shall be added together. This does not apply for

labels on packaging and shipping containers, when containers

contain a mixture of radioactive shipments with different radionuclides; for them

the record must be: "See transport documents";



(d) for category I-white is not writing the transport index is required.



Fill in the value of the transport index stickers of the conservation

podkritického status



44. (544) Each label conforming to the model in Figure 1. 5 must be filled in

the value of the transport index for the conservation of podkritického State,

as prescribed in the decision on the authorisation of the transport of a specific

conditions or in the decision on the type of approval issued by the Office.



45. (545) For the outer packaging and shipping containers must write the values

the transport index for the conservation of podkritického status on the label

correspond to the sum of the transport indexes of the conservation podkritického

the condition required by paragraph 44. Annex No. 4 all radioactive

parcels contained in the outer packaging or on the shipping container.



Stamping of marks



46. (546) Large shipping containers that contain radioactive

the shipment, with the exception of the exempted shipments, and tanks shall be provided with

marks according to the pattern in Figure 1. 6. (6). Signs must be mounted vertically

on the front, side and rear wall of a large shipping container

or cisterns. Tags that do not apply to the content must be

removed or covered. Instead of the current use of stickers and labels

Alternatively, allowed to use only the appropriate labels according to the patterns on the

(fig. a). 2. (2) fig. 2. 3. (3), fig. 4. (4) and Fig. 5. (5)

enlarged so that they have the minimum dimensions according to the pattern in Figure 1. 6. (6).



(Fig. a). 4. (4). Category III-yellow sticker. The background of the top half of the sticker

must be yellow and the bottom half white, the colour of the symbol and text třílistého

must be black, and the color of the stripes indicating the category must be red.

[= radioactive, radioactive CONTENTS = CONTENTS, ACTIVITY = activity

the minimum dimension = minimum dimension, TRANSPORT = TRANSPORT INDEX

The INDEX. ]



47. (547.) Delivery of bulk substances, LSA-I or SCO-I in the transport

the container or in the cistern or the delivery of the packaged radioactive substances

carried under the conditions of an exclusive use in a shipping container can be

mark the only number the UNITED NATIONS, the UN shipment number must be

indicate the black digits high at least 65 mm, and either:



(a) in the bottom half of the marks by the pattern in Figure 1. 6. (6), before which

to hang the letters "UN", on a white background, or



(c) on the basis of the model in Figure 1. 7. (7).



Note



If you use the alternative (b), must be attached to the main brand, according to

the model in Figure 1. 6. (6) additional symbol according to the pattern in Figure 1. 7 (7) on the

all four sides of the shipping container or tank.



(Fig. a). 5. (5). The label of the transport index for the conservation of

podkritického State. Background stickers must be white, the color of the text must be

the black. [FISSILE = FISSIONABLE MATERIAL, THE CRITICALITY SAFETY INDEX = TRANSPORT

THE INDEX OF THE CONSERVATION STATUS, MINIMUM DIMENSION PODKRITICKÉHO =

MINIMUM DIMENSION].



The liability of the carrier



48. (548.) In compliance with the requirements of paragraphs 20. (d) and 34. up to 47. Annex

No. 4 relating to the marking and labelling and marks matches

the shipping agent.



(Fig. a). 6. (6). Mark. With the exception of authorised pursuant to the provisions of paragraph 70.

Annex No. 4 must be the minimum dimensions of the brand under the displayed model;

If they are chosen by the other dimensions, relative proportions must be maintained.

The digit "7" shall not be less than 25 mm. height of the background of the top half

signs shall be yellow and of the lower half white, the colour of the symbol třílistého

and the text must be black. In the bottom half of the tags, you can either use

the term "radioactive" or his place to record the relevant UN number

for the shipment. [MINIMUM = MINIMUM, RADIOACTIVE, RADIOACTIVE = MINIMUM

DIMENSION = MINIMUM SIZE.]



The accompanying delivery requirements



49. (549.) The shipping agent must indicate in the transport documents,

accompanying each shipment, the corresponding data and comply with the listed

order:



(a) the proper shipping name in accordance with table 5. (VIII) the annex No. 4;



(b) the number of the class to the UNITED NATIONS, "7",



(c) the UN number assigned to the substance in accordance with table 5. (VIII) Annex No.

4, předsazenými with the letters "UN",



(d) the name or symbol of each radionuclide or, for mixtures of radionuclides
appropriate general description or a list of restrictive nucleons,



(e) a description of the physical and chemical state of the substance or indication that this is a

a special form radioactive material or radioactive substance with a little

rozptýlitelností. For a description of the chemical forms is not possible, the chemical

the formula,



(f) the maximum activity of the radioactive contents during transport expressed in

As becquerels relative (Bq) with the appropriate prefix'S hanging units,

fissile materials may be given instead of the total weight of the activity in

grams (g) or in multiples,



(g) the category of radioactive cargo, t. s. I-white, II-yellow, III-yellow;



(h) the transport index (categories II-yellow and III-yellow),



(i) for deliveries containing fissile materials, other than exempt under

paragraph 78 of annex I, point 1, the transport index of the conservation

podkritického State



(j) the identification mark for each decision of the type approval, or

permit Office, corresponding to their delivery,



(k) for the bulk shipment of radioactive consignments in the outer packaging, or

shipping container for detailed statement of the contents of each radioactive

shipments inside the outer packaging or shipping container, or

each outer packaging or shipping container in the consignment. If they have a

be interpreted each radioactive consignments from the outer packaging or

shipping container at certain places during transport must be

available to the relevant transport documents;



(l) if the shipment is transported under the conditions of an exclusive use, in addition

the words "carriage under the conditions of an exclusive use",



(m) for bulk substances, LSA-II, LSA-III, SCO-I and SCO-II

the total shipment activity as multiples of values.



(Fig. a). 7. (7). Make a separate UN number for the record. The background tag must

be the Orange and paint the edges of the marks and numbers of the UNITED NATIONS must be black. Symbol

"****" represents the point at which the number must be recorded

The UNITED NATIONS for radioactive material, as shown in table 5. (VIII) Annex

4. [MINIMUM DIMENSION = MINIMUM SIZE.]



The Declaration of the transporter



50. (550.) The carrier is obliged to include in the transport documents

the following text or equivalent statement: "I declare

that the contents of the shipment is fully described above, transport

name is included in the group, packed, marked and equipped with the stickers and

and it is in every respect in a State suitable for transport (make up

type of transport) according to the requirements of the relevant international treaties and

national legislation. "



51. (551.) If the release of this statement in the context of the condition of transport

certain international agreements, the carrier may not issue such a statement

for that part of the transport, to which the international agreement applies.



52. (552) The Declaration must be dated and shall be signed by the

the transporter. Facsimile of the handwritten signature may be replaced only when the

the relevant laws and decrees of the legally permitted the legal validity of such

the signature.



53. (553) The Declaration must be included in the document that describes the delivery

podleodstavce 49. Annex No. 4.



Remove or cover stickers



54. (554) If it is sent packing empty file as the cut the consignment

in accordance with the provisions of paragraph 20. Annex No 4, may not be the original stickers

readable or visible.



Information for carriers



55. (555). The shipper shall include in the transport documents for instructions on

the measures, which must be carried out if a situation for their

the application of. The instructions shall be in the language or languages required

the carrier or the authorities concerned and must contain at least the following information:



(a) supplementary measures while loading, positioning for the carriage, transportation,

the handling and unloading of radioactive cargo, the outer packaging or

the shipping container, including specific conditions for heat dissipation (see

paragraph 65. Annex No. 4) or instruction, that such measures are not necessary,



(b) the limitations in terms of the type of transport or a means of transport and

all the necessary instructions on the route,



(c) the written instructions on the emergency measures to be taken to the appropriate

the shipment.



56. (556). The decision about the type of approval or authorisation of shipments may not

necessarily accompany the consignment. However, the carrier must ensure that their

availability for the carrier prior to loading and unloading.



The notification to the competent authorities of the



57. (557) Before the first shipment of any radioactive shipments

requiring the approval or authorisation of competent authorities must transporter

ensure that a copy of the type-approval have been submitted to the competent

the authorities of each Member State concerned by the transport operation involves. The competent authorities do not have the

the obligation to respond to a notification received and on their response

to wait.



58. (558) For each shipment listed in subparagraphs), b), c) or (d))

of this paragraph, the carrier must notify the competent authorities of each Member State,

which or into which the consignment is to be transported. This notice must

each competent authority to receive before transport, if possible

at least 7 days in advance.



(a) the radioactive cargo type C with fissile materials or

radioactive substances, whose activity is higher than 3,103 A1 or

3,103 A2, or 1000 a TBq, whichever value is lower,



(b) the radioactive cargo type B (U), fissile materials or

radioactive substances, whose activity is higher than 3,103 A1 or

3,103 A2, or 1000 a TBq, whichever value is lower,



(c) radioactive consignments of type B (M)



(d) transport under special conditions.



59. (559) Notification of delivery shall contain



(a) sufficient information to enable the identification of radioactive shipments

or radioactive shipments, including all the necessary numbers of decisions and

identification markings,



(b) the date of shipment, the expected date of arrival or

arrival and estimated route,



(c) the name of the fissile material or radioactive material or nuclide,



(d) a description of the physical condition and chemical forms of the radioactive material, or

the fact that this is a special form radioactive material or a radioactive

a substance with a little rozptýlitelností,



(e) the maximum activity of the radioactive contents during transport expressed in

As becquerels relative (Bq) with the appropriate prefix'S hanging units. U

fissile materials may be given instead of the total weight of the activity in

grams (g) or in multiples.



60. (560) The carrier does not have to send a separate notification if the

were the necessary information included in the request for authorization to transport.



Documentation and operating rules, which must have a carrier available



61. (561.) The carrier must have a copy of each decision

The Office and a copy of the instructions for the correct conclusion of the radioactive shipments and all

measures for the preparation of transport before the transport shall be carried out according to the

the terms of the decision.



Transport and storage in transit during transport



Separation during transport and storage in transit during transport



62. (562.) Radioactive shipment, or the outer packaging, or shipping container

containing fissile materials or radioactive substances must be within

transport and storage in transit during transport, separated from the



(a) places used by the staff and from the into the photographic film from

the reasons for the restriction of exposure to ionizing radiation,



(b) from other dangerous goods in accordance with paragraph 6 of the annex No.

5.



63. (563.) Radioactive shipments or outer packagings of category II-YELLOW

or III-YELLOW shall not be carried in compartments occupied

the passengers with the exception of places intended for personnel responsible for the accompaniment

such radioactive consignments or outer packaging.



Positioning the supply on the means of transport and storage during transit

transport



64. (564). Deliveries must be safely stored, i.e. when the carriage. so, in order to

they cannot move, flip, or fall.



65. (565) If the average surface heat flux of radioactive shipments

or the outer packaging does not exceed 15 W/m2 and if things in the

the immediate surroundings are packed in bags or bags may be

radioactive shipment or the outer packaging, transported without special

requirements relating to the placing for the transport, together with the other

the packed cargo, however, if the appropriate authorization or approval

the competent authority does not specify explicitly something else.



66. (566) Loading shipping containers and distribution

radioactive shipments, the outer packaging or shipping containers,

performs the following steps:



(a) except under the conditions of an exclusive use shipments must be the total

the number of radioactive consignments, packaging or transport

containers on a single means of transport limited in such a way,

to the total sum of the transport indices does not exceed the values specified in

table 6. (IX) the annex No. 4. For the supply of substances LSA-I does not exist

restrictions on the sum of the transport indexes



(b) for shipments transported under the conditions of an exclusive use does not exist

restrictions on the sum of the transport indexes on a single means of transport,



(c) under normal conditions of transport may not power equivalent

at any point, the external surface of the vehicle shall not exceed 2
mSv/h at a distance of 2 m from, the external surface of the vehicle

0.1 mSv/h,



(d) the total sum of the transport indexes of the conservation

podkritického State in the shipping container and on the means of transport

must not exceed the values listed in table 7. (X) the annex No. 4.



Table 6. (IX) the limits of the transport index (TI) for transport containers

and for the means of transport not transported under the conditions of an exclusive use

-------------------------------------------------------------------------------------

The type of the shipping container or means of transport Limits total

the transport index (TI)

in the transport

the container, or

on the means of transport

-------------------------------------------------------------------------------------

Shipping container-50

------------------------------------------------------------------------------- ------

Shipping container-large 50

-------------------------------------------------------------------------------------

The vehicle 50

-------------------------------------------------------------------------------------

The plane

for the transport of persons 50

for the transport costs 200

-------------------------------------------------------------------------------------

Vessel for inland waterways 50

-------------------------------------------------------------------------------------

Naval ship and)

(1) Shipping area, Department, or defined deck area

radioactive shipment, the outer packaging or small transport

container 50

a large shipping container 200

(2) the Overall naval ship

radioactive shipment, the outer packaging or small transport

the container 200

a large shipping container unlimited

-------------------------------------------------------------------------------------



Radioactive shipments) or outer packaging on vehicles, which

comply with the requirements of paragraph 72. Annex No 4, may be transported

vessels provided that they will not be interpreted from the vehicle all the time

transport on board the vessel.



67. (567) Each radioactive shipment or the outer packaging, having a transmission

index greater than 10, and each having shipment transport index in terms of

the conservation status of the podkritického greater than 50 must be transported only

under the terms of the exclusive use.



Separation of radioactive consignments of fissile materials during

transport and transit storage



68. (568) In transit storage during transport in any

storage area must be the number of radioactive consignments, external

packaging and shipping containers containing fissile materials limited

in such a way that the total sum of the transport indexes in terms of

conservation status does not exceed podkritického value of 50 in one group

such radioactive shipments, packaging and transport

containers. This limited group of radioactive consignments, external

packaging and shipping containers must be stored so that the

compliance with the distance of at least 6 m between them.



Table 7. (X) Limits of the transport indices of the conservation

podkritického State (CSI) for the transport of containers and transport

resources containing fissile material

-------------------------------------------------------------------------------------

The type of the shipping container or means of transport Limits total

the transport indexes of the

the conservation

podkritického status

(CSI) in the transport

the container, or

on the means of transport

------------------------

Other Přepravaza

transport conditions

exclusive

the use of the

-------------------------------------------------------------------------------------

Shipping container--small 50-

-------------------------------------------------------------------------------------

Shipping container-large 50 100

-------------------------------------------------------------------------------------

The vehicle 50 100

-------------------------------------------------------------------------------------

Aircraft:

for the transport of persons 50-

for the transport costs 50 100

-------------------------------------------------------------------------------------

Inland waterway vessel 50-

-------------------------------------------------------------------------------------

Naval ship and):

(1) Shipping area, Department, or defined deck area

-radioactive shipment, the outer packaging or small transport

container 50 100

-a large shipping container 50 100



(2) the Overall naval ship

-radioactive shipment, the outer packaging or small transport

container 200b) 200 c)

-a large shipping container (b) unlimited unlimited) (c))

-------------------------------------------------------------------------------------



Radioactive cargo, and) or outer packaging on vehicles, which

comply with the requirements of paragraph 72. Annex No 4, may be transported

vessels provided that they will not be interpreted from the vehicle all the time

transport on board the vessel. In this case the data from the boxes

with the heading "Transport under the conditions of an exclusive use".



(b) delivery and handling) save for the transport must be carried out

so that the total sum of the transport indexes of the conservation

podkritického State (CSI) does not exceed the value 50 or in one group and

the handling of any such group and save for transport must

be made so that these groups were separated by a distance of at least 6

m.



(c) the delivery and handling) save for the transport must be carried out

so that the total sum of the transport indexes of the conservation

podkritického State (CSI) does not exceed the value of 100 or in one group and

the handling of any such group and save for transport must

be made so that these groups were separated by a distance of at least 6

m space between groups may be occupied for the next cargo in accordance with the

paragraph 5. Annex No. 4.



69. (569) If the total sum of the transport indexes in terms of

the conservation status of the podkritického on the means of transport or in a transport

container exceeds 50, as permitted in the table 7. (X) the annex

No. 4, must be stored so as to comply with the distance of at least 6 m

between such a means of transport or transport container and

other groups of radioactive consignments, the outer packaging or

shipping containers containing fissile material or other

means of transporting fissile materials or radioactive

the substance.



Additional requirements relating to carriage by rail and road



70. (570) rail and road vehicles carrying radioactive

the consignment, the outer packaging or containers bearing labels

According to the model. 2. (2) fig. 2. 3. (3), fig. 4. (4). or fig. 5.

(5.) or carrying supplies for the exclusive use of the terms must be

mark conforming to the model in Figure 1. 6. (6):



(a) from the outside on both sides in the case of rail vehicles,



(b) from the outside on both sides and on the back of the head in the case of road

of the vehicle.



Note



For vehicles without sidewalls may be placed directly on the chassis tag

carrying the load, if there are visible; for large volume

tanks or transport containers are sufficient signs

directly on them. For vehicles that do not have sufficient space for the location of the

the larger brands, brands can be modeled on the dimensions of the figure. 6

reduced so that they have the dimension of 100 mm. All the parties marks the Nonpareil

relationship to the cargo of the vehicle must be removed.



71. (571) If the shipment on the vehicle is the non-packed substance LSA-I or

SCO-I or if a shipment transported under the conditions of an exclusive use

packaged fissile material or radioactive substance with a single number

The United Nations must be the number of the Organization

the United Nations, see table 5. (VIII) the annex No. 4, recorded

black digits not less than 65 mm high either:



(a) at the bottom of the tag according to the pattern in Figure 1. 6, or



(b) on the basis of the model in Figure 1. 7. (7).



Note



If the alternative is chosen ad (b)), the additional symbol must be

located close to the major brands on the outside of both sidewalls in the case

rail vehicle or on the outside of the two sidewalls and at the back of the head in the

the case of a road vehicle.



72. (572) In the case of deliveries, carried under the conditions of an exclusive

the use shall not exceed the equivalent wattage of a batch:



(a) 10 mSv/h at any point of the external surfaces of the radioactive shipments
or the outer packaging; may, however, shall not exceed 2 mSv/h, if the



(i) the vehicle is fitted with a sealing device that under normal conditions of transport

prevents unauthorized persons from access to the Interior of the vehicle and



(ii) such measures are carried out to consolidate the radioactive shipments

or packaging, that is their location inside the indoor space

of the vehicle under normal conditions of transport and



(iii) between the start and end of the shipment will be made no

loading or unloading;



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

roof and floor areas, or in an open vehicle, at any

the site, which is located on the vertical planes extended from the external

the edges of the vehicle, the load on the surface and the bottom of the external surface of the vehicle and



(c) 0.1 mSv/h at a distance of 2 m from the vertical planes, their parts are

the outer surfaces of the sidewalls of the vehicle or if the cargo on

an open vehicle, at a distance of 2 m from the vertical planes

take place outside of the vehicle.



73. (573) In the case of road vehicles is not to anyone except the driver and

mate allowed to stay in the vehicle flying radioactive

the consignment, the outer packaging or shipping containers marked with stickers

category II-YELLOW or III-YELLOW.



Additional requirements apply to the carriage by vessels



74. (574) Radioactive shipments, or the outer packaging having a power input

dose equivalent on the surface more than 2 mSv/h, in addition to those that

they are carried on the vehicle under the conditions of an exclusive use in accordance with the

table 6. (IX) the annex No. 4, Note (a), shall not be transported

the vessel, with the exception of those that are transported in special

terms and conditions.



75. (575). The transport of the supplies of the realized a special-purpose vessel

that project is on the basis of the solution or the conditions of the lease is intended to

transport of radioactive substances is excluded from the requirements referred to in

paragraph 66. Annex No. 4 If the following conditions are met simultaneously



(a) for the carriage of the radiation protection program, which is

approved by the competent authority of the State in which the vessel is registered and,

If it is required, by the competent authority at each port, in which

vessel anchors,



(b) the conditions for the location on the means of transport are fixed

for the entire route, and remember and supply, which can be loaded during

the path in the layover



(c) loading, treatment with the delivery and unloading take place under the supervision of the person

qualified in the field of the transport of radioactive substances.



Additional requirements relating to the carriage of



76. (576) Radioactive consignments of type B (M) and the supplies carried for

conditions of an exclusive use must not be transported by aircraft for the transport of

persons.



77. (577) Air must not be transported radioactive consignments of type B (M)

chilled air, the radioactive shipments that require external cooling

auxiliary cooling system, radioactive consignments subject to operational

checks during transport and radioactive consignments containing liquid

pyrophoric materials.



78. (578) Radioactive shipments, or the outer packaging of the reporting power

dose equivalent on the surface more than 2 mSv/h, must not be

transported by air, with the exception of those that are transported under

the special conditions.



Additional requirements relating to the international carriage by post



79. (579) The shipment, which meets the requirements of paragraph 15. Annex No. 4 and

While the activity of the radioactive contents shall not exceed one tenth of the

the limits prescribed in the table 3. (III) Annex No 3, may be taken

for the transport of mail in States where such transport is enabled; When

It must meet the additional requirements that may be applicable

post prescribed. In the Czech Republic is not the national transport

radioactive substances in the mail enabled.



80. (580.) The shipment, which meets the requirements of paragraph 15. Annex No. 4 and

While the activity of the radioactive contents shall not exceed one tenth of the

the limits prescribed in the table 3. (III) Annex No 3, may be taken

for the international carriage by post filing outside the territory of the Czech Republic; When

It must meet the following additional requirements prescribed

the individual regulations of the Universal Postal Union, must be



(a) made to the post office only carriers who are authorised by the competent authorities;



(b) made the quickest way, usually by air;



(c) on the surface of clearly and durably marked with the words "RADIOACTIVE SUBSTANCE-

The AMOUNT AUTHORIZED for the CARRIAGE of MAIL, these words must be crossed out

the cross, if returns an empty file packaging;



(d) on the surface marked with name and address of the carrier with a request that, when

the shipment was undeliverable returned;



(e) the name and address of the shipper and the description of the contents of the shipment are also given within the

the packaging file.



------------------------------------------------------------------



*) Note



Positional numbers printed in bold in parentheses according to paragraph numbers,

where appropriate, tables and pictures correspond to the numbering of the recommendations

The International Atomic Energy Agency, "the IAEA Safety Standards

Series, Regulations for the Safe Transport of Radioactive Material,

1996 Edition (Revised), Requirements, No. TS-R-1 (ST-1, Revised),

The International Atomic Energy Agency, Vienna, 2000 ". For this attachment

apply the interpretation of the concepts referred to in the abovementioned document from paragraph 201 to

paragraph 248.



Annex 5



Shipment of sealed sources between the Member States of the European Union



The standard document used in accordance with the Council Regulation Euratom No.

1493/93



Shipment of sealed sources between the member states of the european

Community



Standard document to be used pursuant this Council Regulation (Euratom)

No 1493/93



Note



Notice



-The recipient of the closed sections must fill the emitters 1 to 5 and send this

the document to the appropriate competent authority in their country.



The consignee of sealed sources must complete boxes 1 to 5 and send

This form to the competent authority is in his country.



-The competent authority of the consignee Member State must fill in box 6 and

return the document to the recipient.



The competent authority of the consignee Member State must fill in box

6 and return this form to the consignee.



-The consignee sends this document to the sender (the holder) in the country

the sender before carrying out a shipment of a closed Panel.



The consignee must then send this form to the holder in the forwarding

country prior to the shipment of the sealed sources.



-All parts of this document must be completed and the appropriate boxes

zakřížkovány.



All sections of this form must be completed and boxes ticked, where

appropriate.

1. This DECLARATION CONCERNS:

1. THIS DECLARATION CONCERNS:



ONE OF THE TRANSPORT

ONE SHIPMENT



(This document is valid until the shipment is made, if the

unless otherwise specified in section 6)

(This form is valid until the shipment is completed unless

otherwise stated in box 6)



expected date of shipment (if available):......................

expected date of shipment (if available):



MULTIPLE SHIPMENTS

SEVERAL SHIPMENTS



(This document is valid for three years unless otherwise specified in the section

6)

(This form is valid for three years unless otherwise stated in box

6)



2. PLACE of DESTINATION EMITTERS (RADIATORS)

2. the DESTINATION OF THE SOURCE (S)



Jméno příjemce: ..................................................

Name of consignee:



Contact person:.................................................

Person to contact:



Adresa: ..........................................................

Address:



Tel.: ................................... Fax: ...................



3. The HOLDER of the EMITTERS (RADIATORS) in the country of the SENDER

3. the HOLDER OF THE SOURCE (S) IN THE FORWARDING COUNTRY



The name of the sender (the holder):....................................

Name of holder:



Contact person:.................................................

Person to contact:



Adresa: ..........................................................

Address:



Tel.: ................................... Fax: ...................



4. DESCRIPTION of the EMITTERS (RADIATORS) that are the SUBJECT of the shipment (s)

4. DESCRIPTION OF THE SOURCE (S) INVOLVED IN THE SHIPMENT (S)



(a) Radionuclide (radionuclides):..................................

(a) Radionuclide (s):



(b) the maximum activity of individual emitters (MBq):................

(b) the Maximum activity of individual source (MBq):



(c) Počet zářičů: ................................................

(c) the Number of sources:



(d) if it is a closed radiator (if sealed sources) part of the machine

or apparatus or device, then provide a short description of this

machines or apparatus or device:

(d) If this (these) sealed source (s) is (are) mounted in (a)

machinery/device/equipment, short description of the

machinery/device/equipment:



..............................................................



..............................................................



..............................................................



..............................................................



..............................................................



..............................................................



(e) Please indicate (if this is possible and if it is required by the competent

authorities):

(e) Indicate (if available and requested by the competent
authorities):



-national or international technical standard, which closed radiator

suits (sealed sources meet) and the number of the relevant

certificate:

national or international technical standard with which the

sealed source (s) (s) complies and certificate number:



................................................................



................................................................



-the date of validity of the certificate:...................................

date of expiry of certification:



-name of the manufacturer and catalogue reference:

the name of the manufacturer and catalogue reference:



................................................................



................................................................



5. STATUTORY DECLARATION or a RESPONSIBLE REPRESENTATIVE of the

5. DECLARATION OF THE AUTHORIZED OR RESPONSIBLE PERSON



-I, the consignee, hereby certify that the information provided by me in this

of the document are correct.

I, the consignee, hereby certify that the information provided

in this form is correct.



-I, the consignee, hereby certify that I am licensed, authorized or other

authorization to accept the sources listed (sources listed) in this

dokumente.

I, the consignee, hereby certify that I am licensed, authorized

or otherwise permitted to receive the source (s) described in

This form.



-Number of licences, permissions or other authorization and the expiry date of the

validity:

The license, authorization or other permission number (if

"applicable") and validity date thereof:



................................................................



................................................................



-I, the consignee, hereby certify that I meet all national

legislative requirements, relating to the safe storage,

the use or storage of sources (emitters) laid down in this

the document.

I, the consignee, hereby certify that I comply with all the

It is the national requirements, such as those relating to the

safe storage, use or disposal of the source (s) described in this

form.



Jméno: .........................................................

Name:



Podpis: ........................................................

Signature:



Datum: ........................................................

Date:



6. the COMPETENT AUTHORITY of the COUNTRY of the RECIPIENT, that the REGISTERED

THIS STATEMENT

6. CONFIRMATION BY THE COMPETENT AUTHORITY OF THE CONSIGNEE

THE COUNTRY THAT IT HAS TAKEN NOTE OF THIS DECLARATION



Stamp:

Stamp:



The name of the competent authority:

The name of the authority:



.................................................................



.................................................................



.................................................................



.................................................................



Address:

Address:



.................................................................



.................................................................



.................................................................



.................................................................



Telefon: ............................. Fax: ......................



Tel.: Fax:



Datum: ..........................................................

Date:



This declaration is valid until (if provided):......................

This declaration is valid until (if applicable):



See also section 1, page 1, with instructions on the determination of the period of validity of

of this document.

Please see box 1, page 1, for guidance on the length of time this

the form is valid.



Annex 6



STANDARD DOCUMENT FOR THE SUPERVISION OF SHIPMENTS OF RADIOACTIVE WASTE AND

OF SPENT FUEL AND ITS CONTROL



General notes:



Section A1-A6 to be completed for shipments of radioactive waste and of the B-1 to

B-6 is completed for the transport of spent fuel (including spent fuel

intended for final disposal, which is therefore classified as a

waste).



Part A-1 or B-1 (application for permission to transport): the applicant,

that is according to the type of transport:



-the holder in the case of transport between Member States (MM type) or export

from the community to a third country (ME);



-the beneficiary in the case of imports into the community from a third country (IM);



-the person responsible for the shipment in the Member State to which radioactive

waste or spent fuel is to enter the Community in the case of transit

Community (type TT).



Part A-2 or B-2 (acknowledgement of receipt): fill in the concerned

the competent authorities, which according to the type of transport, the competent authorities



-the country of origin in the case of transport type MM or ME;



-country of destination in the case of transport by type of IM;



-the country where the consignment first enters the community, in the case of transport

the type TT and all the competent authorities of any Member State of transit.



Part A-3 or B-3 (rejection or approval): fill in all the

the competent authorities.



Part A-4a or-4b/B-4a/B-4b (authorisation or refusal to transport):

the competent authority responsible for the issue of permits, which is referred to in

the type of transport, the competent authority



-the country of origin in the case of transport by type of MM and ME;



-the Member State of destination in the case of transport type or



-first Member State where the consignment enters the community in

If the transport type of the TT.



Part of the A-5 or B-5 (description of consignment/list of packaging): applicant

referred to in part A-1 or B-1.



Part A-6 or B-6 (confirmation of receipt): fill in the payee (for

the transport type of the MM and IM) or holder (for transport type ME) or the person

responsible for transport (transport type TT)



The EXPLANATORY NOTES



for each item in the parts of the standard document, and-1 to A-6 and B-1 to B-6:



The definition of the duly completed application: the application for a permit to transport

radioactive waste or spent fuel is properly filled in

accordance with Directive 2006/117/Euratom, if they are in the case of transport

radioactive waste in every part and item-1 or in the case of transport

spent fuel in each entry of the B-1 shows the information required

by selecting the appropriate window, clearing (scratch) delete

options or by filling out the relevant data and values. In the case of an application

concerning the repeated transport items 8 and 9 contain estimates.



(1) the applicant must duly fill in the all items 1 to 14. In item 1

selects one of the Windows that define the transport method and fill in the corresponding

border crossings, where concerns of third countries,



(a) selects the type of MM for transport between the Member States, while the consignment

may browse through another Member State or States or third

countries;



(b) selects the type of IM for the transport from a third country into a Member State (=

imports into the community), the application shall contain a proof, that the

beneficiaries with the holder established in the third country arrangements

accepted by the competent authority of the third country, and which the holder undertakes to

take back the radioactive waste or the spent fuel in the event that the

It will not be possible or will not be permitted to complete the transport;



(c) selects the type of ME for the carriage from a Member State to a third country (=

exports from the community) or



(d) selects the type of TT for the transport from one third country to another third country,

When the consignment passes through one or more Member States, the application

must include proof that the consignee established in the third country has concluded a

with the holder established in the third country which accepted the

authority of the third country and that holder to take back the

the radioactive waste or the spent fuel in case that is not possible or

transport will not be allowed to complete.



(2) by selecting the appropriate window, the applicant must clearly state whether the

the application concerns only a one-time shipment within a certain period (e.g. 05/2010

2009 or 2010-2011), or whether the application concerns the repeated transport in

a period, which shall not exceed three years from the date of issue of the permit.

For recurring shipments can be sent to one request, if you are satisfied

the conditions laid down in article. 6 (1). 2 Directive 2006/117/Euratom:



(a) the radioactive waste or the spent fuel to which it relates,

they have essentially the same physical, chemical and radioactive characteristics, and



(b) the consignment is sending the same holder to the same consignee under participation of the same

the competent authorities and



(c) in cases where transport involves transit through third countries, this

transit through the same border crossing on their way to the community

or from the community and via the same frontier post or the transitions

the third country or countries concerned, unless agreed otherwise, the relevant competent authorities.



(3) if the transport relates to one or more third countries, the applicant must

fill in the appropriate border crossings. These border crossings must be

identical for all shipments, which the application relates, unless the

the competent authorities otherwise.



(4) the applicant must fill in your business name, address and contact details.

A trade name, also known as a trade name or business

the company, which is the name of the firm uses in the course of trade, although its

registered legal name used for contracts and other formal situation

may vary. The applicant must check the appropriate box indicating his

function, which is according to the type of transport:
(a) the holder in the case of transport between Member States (MM type) or

exports from the community to a third country (ME);



(b) the beneficiary in the case of imports into the community from a third country (IM);



(c) the person responsible for the shipment in the Member State to which radioactive

waste or spent fuel is to enter the Community in the case of transit

Community (type TT).



(5) the applicant must fill in the business name, address and contact details

where radioactive waste or spent fuel is saved before

transport and which may be different from the address of the applicant.



(6) the applicant must fill in the business name, address and contact details

of the recipient. In the case of transport type IM these data are identical with those in the

item 4.



(7) the applicant must fill in the business name, address and contact details

the place where the radioactive waste or the spent fuel stored after

transport and which may be different from the address of the recipient.



(8) the applicant must fill in all the fields by selecting the appropriate window

(it is possible more than one answer) or by filling in a specific property

and the values of the radioactive waste or the spent fuel. In the case of

repeated transport can be as these values indicate estimates.



(9) the applicant must fill in item 9, the values may be estimates.



(10) the applicant must select and specify the type of activity, which was

radioactive waste or spent fuel and check the appropriate box

(Windows) or advanced another activity. It is maybe more than one

the answer.



(11) the applicant must indicate the purpose of the transport and check the appropriate box (it is

maybe only one answer) or advanced another purpose.



(12) the applicant must indicate the enumeration of individual modes of transport planned

for transport (road, rail, sea, air, inland

the water) and add the appropriate place of departure, place of arrival, and scheduled

the carrier (if already known). Later changes to this plan during the

processing of applications are possible and should be notified to the competent

the authorities, however, do not require a new application for authorisation.



(13) the applicant must indicate all countries concerned,

starting with the first Member State or third country where the radioactive

waste or spent fuel is located, and ending with the last Member State

or a third country, where the waste or fuel must be after the completion of the

transport. If the applicant will be a gradual change might want to enumerate the countries must

submit a new application.



(14) the applicant must indicate who the radioactive waste or the spent fuel

taken back in if it is not possible to carry out transportation or

meet the conditions of transport. In the case of transport by type of IM or TT must

the applicant to accompany the application document arrangement between the beneficiary in the Member

State or third country of destination and the holder of the radioactive waste or

spent fuel in a third country that the competent authority has accepted the

a third of the country.



After filling in the items 1 to 14, the applicant must send to the part 1 of the standard

document to the competent authority responsible for the issue of permits to transport.

The competent authority responsible for issuing the authorization to transport or for

rejection of the request is in accordance with the type of transport:



the competent authority of the Member State of origin for shipments between Member

States (MM type) and exports from the Community (ME);



the competent authority of the Member State of destination in the case of imports into the

The Community (IM);



the competent authority of the first Member State of transit, where the consignment

enters the community, in the case of transit through the territory of the community

(type TT).



The relevant contact details can be obtained from the electronic communications

the platform, which has set up and managed by the Commission, or from a published

list of the competent authorities.



(15) immediately after receipt of the request, the competent authority responsible for issuing the

authorisation for the transport of:



(a) write the registration number of the application in the top section of each part

the standard document, starting with part 1,



(b) to verify whether the applicant duly filled out all of the items, part 1



(c) fill in item 15 of part 2 and get a sufficient number of copies of parts of the

1, 2 and 3 for each Member State concerned, or the country. Consultation with the

third countries of transit is done for information purposes only.



(16) the competent authority responsible for issuing the permit must



(a) fill in item 16 of part 2 (and item 18 of part 3) for each

the competent authority of the Member States concerned or the countries listed in the list

in item 13, whose consent is needed for the authorization of the transport, and



(b) without delay, send a duly completed application (part 1), along with part 2

for the approval of each of the concerned competent authority referred to in the entry

16.



(17) Item 17, the competent authority fills in the Member State concerned

(the competent authorities of the Member States concerned). The date of filing and the receipt of the

applications must be entered immediately after receipt of the request. Within 20 days from the date of

the adoption of the competent authorities of the Member States concerned to verify whether the

the application duly filled (must be completed all items 1 to 14 and

must not be missing any data; some values may be estimates). Can

just pay the item 17 (a), or item 17 (b) Delete where inapplicable.



(a) if the competent authority of the Member State (competent authorities of Member

States), of transit or of destination considers the request for an incomplete,

must fill in item 17 (a), cut out the item 17 (b) and notify your

a request for missing information to the competent authority responsible for the issue

(referred to in item 15). Must clearly state that the data is missing

(or fill in the attached document). The competent authority of the requesting

missing data must be sent a copy to all other competent part 2

the authorities of the Member States concerned referred to in item 13 to 20 days from

the date of receipt of the request. The relevant contact details can be obtained from

the electronic communication platform, which has set up and managed by the Commission,

or from a published list of the competent authorities. If one of the Member

the State will assume that the application is duly completed, the proceeding shall be terminated. In

this case, the competent authority of the Member State of destination shall send

acknowledgement of receipt before they are delivered to the data requested and within 10 days

After obtaining the missing information is not sent to any other application, and even

If it considers the request duly completed. This procedure can be repeated,

until they obtained all the missing data and will not cease to be sent

other requests for missing information.



If the 20-day period was not in receipt of a request received no

a request for missing information and the competent authority of the Member

the State considers that the application is duly completed, the competent authority must

not later than 10 days after the expiry of the 20-day deadline to send part 2

the competent authority responsible for the issue of the permit referred to in item

15 and a copy of that section all the other competent authorities concerned

the Member States referred to in item 13. The relevant contact details can be

obtain from the electronic communication platform, which has set up and managed by the

The Commission, or from a published list of the competent authorities.



All the competent authorities of the Member States concerned may agree

on shorter time limits.



(b) in order to enable the competent authorities to request the missing information within 20

days from the receipt of the application, the competent authority of the Member State shall determine the

issue a receipt before the 20-day deadline expires.

If the competent authority of the Member State of destination after expiry of the 20-day

the period he considers that the application is duly completed, and are without prejudice to the other

Member States or any competent authority concerned did not ask for the missing

the information, the competent authority must fill in item 17 (b).



(18) as soon as the competent authority responsible for issuing the authorization receives the

acknowledgement of receipt of the duly completed application, the competent authority of the

the Member State of destination must verify whether the limits have been complied with, and shall

fill in item 18 of part 3 for each concerned Member State referred to in

item 13, whose agreement is to permit the shipment (s) to be.

The competent authority must fill in the necessary additional information in item 18.



(19) the competent authority responsible for issuing the permit must enroll in

the General time limit for automatic consent valid for all

the Member States concerned. This expiry date generally falls on the day

coming two months after the date on which the Member State of destination has given acknowledgement

on the adoption of item 17 (b). Then, the competent authority responsible for the

the authorization to send part 3 containing the approval or rejection of all

the Member States concerned or countries. Immediately after the receipt of the part 3 must each

the competent authority shall decide whether a further period is needed for the

the decision on rejection or approval of the shipment. The main general

the time limits under item 19, by filling in the new period and the announcement extended deadlines

all the competent authorities concerned may request a further period of not more than

one month.



(20) the relevant competent authority shall duly consider. Not later than

the expiry of the time limit for automatic approval by the competent
the authority to fill in the item 20 and return the original part 3 (the scanned

the original went sent by electronic mail) to the competent authority

responsible for granting the authorisation (referred to in item 15). In the case of

a refusal shall indicate the reasons for, and the pillow is (in the Member

States of transit) the relevant Community legislation or

international conventions applicable to transport of radioactive material

or (in the Member State of destination) relevant legislation

applicable to the management of radioactive waste or spent fuel

or the relevant national law, the law of the

The community or the international treaties in force for the transport

radioactive material. Any conditions imposed may not be more stringent

than the conditions that are laid down for similar shipments in the Member

States. Complete and the standard document leak in the

the time limit shall be deemed to consent to requests for carriage subject to the article. 9

paragraph. 2 Directive 2006/117/Euratom.



(21) the competent authority responsible for issuing the authorization to transport shall

fill in items 21 to 23, as soon as all the competent authorities concerned

issue the consent required for the transport, and that it was still

consent, it is only in the following cases:



(a) delivered to the acknowledgement of receipt (at least) from the competent authority of the

the Member State of destination (as referred to in item 17 (b),



(b) no request for the missing information shall be left pending and



(c) the competent authorities concerned in the applicable limits referred to in item 19

have the answer (matched or a negative).



(22) the competent authority referred to under 21 must state or, in the case

lack of space on a separate sheet attached to the enumeration of all possible

received consents (including terms and conditions) and the refusal (including grounds) from

all the competent authorities concerned.



(23) the competent authority referred to under 21 must 24



(a) fill in item 23, by period of validity of an authorization shall not be

more than three years and that one authorisation may cover recurring

transportation, are subject to the conditions laid down in article. 6 (1). 2 of Directive

2006/117/Euratom,



(b) submit the original section 4a of the applicant together with the parts 1, 4a, 5 and 6 and



(c) send copies of part 4a to all other competent authorities concerned.



(24) the competent authority responsible for issuing the authorization to transport shall

fill out items 24 and 25, when at least one of the relevant

transport authorities disagreed.



(25) the competent authority referred to in item 24 must state or on a special

the worksheet attached to enumerate all the supplied authorisation and rejections, including any

the conditions and reasons for rejection, and send the original part 4b to the applicant and the

a copy of that section, to all other competent authorities concerned.



(26) if the transport is enabled, and the applicant has received the part 4a, 5 and 6, must

properly fill in item 26. In the event that the request relates to the repeated

transport, the applicant must obtain a sufficient number of copies of 5 for

each consignment.



(27) the applicant must check the appropriate box and specify whether the authorisation is

relates to one-time or recurring shipments. In the case of recurring shipments

must be filled in with the relevant serial number.



(28) before each transport, the applicant must duly fill in items 28 to 30

(even if the authorization relates to the repeated transport). The values in this section

estimates may not be!



(29) the applicant must duly fill in item 29 (list of cases) and in the lower

part of the State the total number of packages, the total number of each type of packaging,

the total net weight, total gross weight and total activity

(GBq) of all packages. If the location in the document is not sufficient, please attach a separate

sheet with the requested information.



(30) the applicant must fill in item 30 (date of sending and statement) before the

each shipment of radioactive waste or spent fuel (even if

the authorisation concerns the repeated transport). Part 5 is along with parts 1 and 4a

in the carriage attached to a shipment of radioactive waste or spent

fuel. Description of the consignment and the list of packages (part 5) is then attached to section 6

(acknowledgement of receipt).



(31) the recipient (in the case of the transport type of the MM and IM, the holder (in the case of

the transport type to ME) or the person responsible for the shipment (in the case of transport

the type TT) shall duly fill in items 31 to 35 (or 36); all

necessary additions carried out by the applicant. The recipient established outside the European

However, the community can confirm receipt of radioactive waste or

spent fuel, the statement is not part of the standard

the document.



(32) the recipient must duly fill in the name, address and contact details of the place,

where radioactive waste or spent fuel stored after the transport.



(33) the recipient must fill in item 33 (item 23) and indicate whether the

the consignment is taken by the last, that authorization applies.



(a) in cases where the authorisation relates to one-time transportation type MM or

IM, the beneficiary shall fill in part 6, within 15 days from the receipt of radioactive

waste or spent fuel and submit part 5 and 6 to the competent

authority of the Member State of destination. The competent authority of the Member State of destination

then send copies of parts 5 and 6 of the other competent authorities concerned (and

where appropriate, the original of the two parts to the competent authority which issued the authorization).

For transport type MM the competent authority must send to the Member State of origin

a copy of the acknowledgement of receipt to the holder.



(b) in cases where the authorisation relates to one-time transportation type ME or

TT, the applicant must provide to the recipient established outside the European

posted by duly completed community part 5 and part 6, immediately after the adoption of the

radioactive waste or spent fuel. Part 6, you can replace the

a statement from the recipient containing at least the information referred to in items 31

up to 36. Within 15 days after the receipt of radioactive waste or spent

fuel, the applicant shall send the part 5, part 6 (if the recipient did not use part

6, the applicant must fill in) and, where applicable, the consignee's declaration to the competent

the authority which issued the authorization. This authority will then send copies of parts 5 and 6 and

where applicable, the consignee's declaration to the other competent authorities concerned.



(c) in cases where the authorisation relates to the repeated transport type MM or

IM, the beneficiary shall fill in part 6 for the transportation of any shipment (and for this

the purpose of the advance edit copies of the blank part 6) and present this part of

directly to the competent authority which issued the permit. Be accompanied by part 5 on

the same shipment.



(d) in cases where the authorisation relates to the repeated transport type ME or

TT, the applicant must ensure that each recipient after the transport of consignments

established outside the European Community filled out for each consignment

(blank) copy of part 6 and returned it, together with the relevant part of the 5.



(34) for the transport type ME or TT the beneficiary must indicate "not applicable"

or fill in item 34, or attach a separate statement and include a link

on the attachment.



(35) as soon as it is completed a one-off shipment or transport of all

consignments which are concerned, the beneficiary must fill in item 35. In

cases where the authorisation relates to the repeated transport, final

acknowledgement of receipt shall be completed and submitted as well as authorisation valid

for a one-time shipment, with the following exceptions:



(a) in item 30 section 6 States that the transport of the consignment in question is

the last, which is concerned.



(b) in any statement of the recipient established outside the European Community

It must be stated that all the radioactive waste or the spent fuel

which the permit relates, were actually brought.



According to the type of transport the beneficiary must send the part 6 (acknowledgement of receipt)

together with part 5 to the competent authority of the Member State of destination in the case of

the transport type of the MM or IM or the applicant, given in item 5 (part 1)

in the case of transport of type ME or TT. That was the total available

Overview, part 6 must be provided for each consignment, that authorisation relates,

attached to the final confirmation of acceptance.



(36) for shipments of type ME or TT, beneficiaries must indicate "not applicable"

or fill in item 36, or replace it with a specific declaration and indicate the

reference to the annex. The applicant must send the parts 5 and 6 of the authority which issued the

the authorization. That was an overview of available, must be part of the 6 for the

each consignment of which the authorisation concerns, attached to the final

the acknowledgement of receipt.



1) Council Directive 92/3/Euratom of 3 September. February 1992 on the supervision and control of

shipments of radioactive waste between Member States and to the community, and

from the community.



Council regulation 1493/93/Euratom of 8 June. June 1993 of consignments

of radioactive substances between Member States.



2) Law No. 123/2000 Coll., on medical devices and on the change

some of the related laws.



3) Decree No 307/2002 Coll., on radiation protection.



4) Law No. 455/1991 Coll., on trades (trade licensing

Act), as amended.



5) for example, Decree No. 214/1997 Coll., on quality assurance

activities related to the use of nuclear energy and the activities of the

leading to exposure and determining the criteria for the classification and Division

the selected device in the security classes, a series of standards ISO 9 000.
for example, the standard series 6), EN 60601-1-1 to EN 60601-2-45.



7 for example, the standards ČSN) 404,302, ISO 2919, ISO 9978.



8 for example, ISO 7205).



9) Law No. 22/1997 Coll., on technical requirements for products and amending

the addition of certain acts, as amended by law No 71/2000 Coll. and Act No.

102/2001 Sb.



10) Decree No 318/2002 Coll., on details to ensure emergency

the readiness of the nuclear facilities and workplaces with sources of ionizing

radiation and about the requirements on the content of the internal emergency plan and the

the emergency order.



11) for example, Act No. 266/1994 Coll., on rail, as amended

legislation, regulation of the Government No. 1/2000 Coll., on the railway transport

rail freight transport for the public, in the wording of later regulations,

Decree No. 8/1985 Coll., on the Convention on the international carriage of

(COTIF), as amended, Decree No. 64/1987 Coll., on

European Agreement concerning the international carriage of dangerous goods

(ADR), as amended, law No 111/1994 Coll., on the road

transport, as amended, law No 114/1995 Coll., on

inland waterway, as amended, Decree No. 222/1995

Coll., on waterways, shipping traffic in the ports, common

the crash and the transport of dangerous goods, as amended,

Act No. 49/1997 Coll., on civil aviation and on the amendment and supplement of the law

No. 455/1991 Coll., on trades (Trade Act), in the

as amended, Decree No. 17/1966 Coll., on air

the transport regulations, as amended.



12) Decree No. 144/1997 Coll., on the physical protection of nuclear materials and

nuclear facilities and their classification into individual categories.



13) Act No. 283/1991 Coll., on the police of the Czech Republic, as amended by law

No. 26/1993 Coll., Act No. 67/1993 Coll., Act No. 163/1993 Coll., Act

No. 326/1993 Coll., Act No. 82/1995 Coll., the Act No. 152/1995 Coll., Act

No. 18/1997 Coll., the finding of the Constitutional Court No. 186/1997 Coll., Act No.

168/1999 Coll., Act No. 325/1999 Coll., Act No. 326/1999 Coll., Act No.

105/2000 Coll., the finding of the Constitutional Court No. 138/1999 Coll., Act No.

329/1999 Coll., Act No. 258/2000 Coll., Act No. 361/2000 Coll., Act No.

60/2001 Coll., Act No. 120/2001 Coll. and Act No. 265/2001 Coll.



14) Decree No. 145/1997 Coll., on registration and control of nuclear materials

and their closer definition.