1. Safe Transport
Day 9 – Lecture 8

2. Objective
To provide an overview of the International Regulations for the Safe Transport of Radioactive Materials

3. Contents General requirements for transport of radioactive sources.
Procedures for the dispatch of radioactive sources.
Procedures for the receipt of radioactive sources.

4. General requirements for transport
The transport of radioactive sources shall be subject to the requirements of the IAEA Regulations for the Safe Transport of Radioactive Material (SSR-6) and any applicable international convention.
MODIFIED
IAEA Regulations are not mandatory for MSs, they are only recommendations . Each MS should have its local regulations following the requirements of IAEA Transport Regulations

5. The Regulations apply to:
the transport of radioactive material by all modes of transport:
on land (road, rail, inland waterway)
on water (maritime)
in the air
SSR 6 Regulations do not apply to internal movement of Radioactive material within an establishment where appropriate safety regulations are in force and where the movement does not involve public roads or railways

6. General requirements for transport
Package Types
Marking, Labeling and Placarding
Documentation
Vehicle
Training
Approval by competent authority
Transfer / receipt documents
MODIFIED

7. Classification
Package [para 231] i.e. the packaging with its radioactive contents
Excepted Package
Industrial Packages - Type 1 (Type IP-1)
- Type 2 (Type IP-2)
- Type 3 (Type IP-3)
Type A Package
Type B Packages -Type B(U)
-Type B(M)
Type C Package

8. Contents Limits - Sources
Packages for sources are designated on the basis of the A1 (special form) and A2 (non-special form) activity values assigned to each radionuclide, given in Table 2 of SSR 6
Examples
Cs-137 A1 = 2 TBq A2 = 600 GBq
Am-241 A1 = 10 TBq A2 = 1 GBq
Co-60 A1 = 0,4 TBq A2 = 0,4 TBq
Note: A1 and A2 can have the same value
MODIFIED
Explain that, for example, for Cs-137 in a solid state, it is possible to transport :
Up to 1/1000 of the A1 or A2 (2GBq or 600 MBq) in an excepted package
Up to the A1 or A2 in a Type A package
More than the A1 or A2 in a Type B or C package.
Explain that the higher the activity the tougher the package must be.

9. Definitions used in the International Regulations
Special Form Radioactive Material [para 239]
Either an indispersible solid radioactive material or a sealed capsule containing radioactive material, that has been subjected to, and has passed, specified tests (Paras and 802). Approval of the material by a competent authority is also required.
Special form radioactive material affords certain mechanical protection to the radioactive material that may (dependant on the nature of the radiological hazard) allow greater quantities of material to be transported in a given type of package than would otherwise be possible.

10. Contents Limits – LSA and SCO
Low Specific Activity (LSA) material and Surface Contaminated Objects (SCO) are split into groups on the basis of activity concentration / surface contamination levels
There are three groups of LSA material: LSA-I, LSA-II and LSA-III
There are two groups of SCO: SCO-I and SCO-II
Once the LSA material or SCO group is known, the correct IP can be determined by referring to Table 4 of TS-R-1
Explain that the higher the group the higher activity concentration/surface contamination levels and the tougher the Industrial Package must be.

11. Transport Index and Criticality Safety Index
Transport Index [para 244]
The Transport Index (TI) is designed to give an indication of the maximum equivalent dose rate (DR) at 1metre from the surface of a package:
DR = (TI x 10) µSv h-1
The higher the TI number,
the higher the dose rate.
Maximum TI = 10, unless
transport is under “Exclusive Use”
1 metre
Criticality Safety Index [para 218]
The Criticality Safety Index (CSI) is designed to prevent excess accumulation of fissile material in any given storage or stowage area.

12. UN Numbers and Proper Shipping Names
Examples (see Table 1 of SSR 6 for complete list)
UN 2910, RADIOACTIVE MATERIAL, EXCEPTED PACKAGE, LIMITED QUANTITY OF MATERIAL
UN 3332, RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM, non-fissile or fissile excepted
UN3328, RADIOACTIVE MATERIAL, TYPE B(U) PACKAGE, FISSILE
MODIFIED

13. Packages types
Packages [para 231] i.e. the packaging with its radioactive contents
Excepted Package
Industrial Packages - Type 1 (Type IP-1)
- Type 2 (Type IP-2)
- Type 3 (Type IP-3)
Type A Package
Type B Packages -Type B(U)
-Type B(M)
Type C Package

14. Packages types (cont)
Excepted Packages - the least restrictive package
Small quantities of radioactive material that present a very low hazard;
Package design requirements apply but no test requirements;
Maximum surface dose rate = 5 µSv h-1 [para 516];
Max TI = 0;
Maximum activity - see SSR-6 Table-4

15. Packages types (cont)
Industrial Packages (Type IP-1, Type IP-2 Type IP-3)
Maximum surface dose rate = 2 mSv h-1 (unless under Exclusive Use) [paras 527, 528];
Max TI = 10 (unless under Exclusive Use) [para 526];
Contents must be Low Specific Activity material (LSA-I, LSA-II or LSA-III) or Surface Contaminated Objects (SCO-I or SCO-II), as appropriate [paras 226, 408, 241, 413].
Often in the form of drums, freight containers, etc.;
Generally used to transport low specific activity materials in bulk quantities
UN3322

16. Packages types (cont) Type A packages
Maximum surface dose rate = 2 mSv h-1 (unless under Exclusive Use) [paras 527, 528];
Maximum TI = 10 (unless under Exclusive Use) [para 526];
Maximum activity = A1 (special form); otherwise A2;
Probably the most common of all the package types;
Used extensively to transport radiopharmaceuticals, such as 99Mo; 131I; 32P; 125I etc.
Packaging may be single use or re-useable.

17. Packages types (cont) Type B Packages – Type B (U) and Type B(M)
designed to survive severe accidents;
Maximum surface dose rate = 2 mSv h-1 (unless under Exclusive Use);
Maximum TI = 10 (unless under Exclusive Use);
Maximum activity - Competent Authority Approved;
Rigorous testing regime;
Competent Authority Approval of design required.

18. Packages types (cont) Type B Packages
May also be used for the transport of irradiated nuclear fuel and other nuclear fuel cycle materials.
Type B(U) packages require approval by the competent authority of the country of origin of the design (unilateral approval).
Type B(M) packages require approval by the competent authorities of the country of origin of the design, and of the countries through or into which they are to be transported (multilateral approval).

19. Packages types (cont) Type C Packages
Designed to survive severe air accidents;
Large quantities of radioactive material (for transport by air);
Rigorous testing regime;
Competent Authority Approval of design required.
Uncommon!

20. Packages types (cont) Fissile packages
Additional requirements apply to the design and operation of packages used to carry fissile material, including the requirement for multilateral competent authority approval of the package design.

21. Package Markings Excepted packages
Address of consignor / consignee and UN number
Type A and Industrial Packages
As above and Proper Shipping Name, ‘TYPE A’ or ‘IP-1’, ‘IP-2’ or ‘IP-3’
Type B packages
As above and ‘TYPE B (U) or (M), mark of certifying authority, specific serial number and embossed radiation trefoil

22. Package Labels Excepted packages carry no labels on the outside.
All other package types carry labels appropriate to the category of the package.
The category of the package is based on the Transport Index (TI) and on the maximum radiation level at any point on external surface.
MODIFIED

23. Max. radiation level (mSv/h)
Categorization
Transport index (TI)
Max. radiation level (mSv/h)
Category
1 m from the surface
at the surface
Up to 0.005
I – white
> 0 to 1
> 0 to 0.01
> to 0.5
II – yellow
> 1 to 10
> 0.01 to 0.1
> 0.5 to 2
III – yellow
> 10
Over 0.1
> 2 to 10
III – yellow (exclusive use)
MODIFIED
Explain this table
Transport Indexes should be quoted to 1 decimal place.
If the surface radiation level is over 2 mSv/h, the package shall be transported under exclusive use and under the provisions of paragraphs 573 (a), 575 or 579 as appropriate.
573. For consignments under exclusive use, the radiation level shall not exceed:-
(a)10 mSv/h at any point on the external surface of any package or overpack, and may only exceed 2 mSv/h provided that:
(i) the vehicle is equipped with an enclosure which, during routine conditions of transport, prevents the access of unauthorized persons to the interior of the enclosure; and
(ii) provisions are made to secure the package or overpack so that its position within the vehicle enclosure remains fixed during routine conditions of transport; and
(iii) there is no loading or unloading during the shipment;
575. Packages or overpacks having a surface radiation level greater than 2 mSv/h, unless being carried in or on a vehicle under exclusive use in accordance with Table 9, footnote (a), shall not be transported by vessel except under special arrangement.
579. Packages or overpacks having a surface radiation level greater than 2 mSv/h shall not be transported by air except by special arrangement.

24. Category I Package – White label
0.005 mSv/h at the package surface.
0 mSv/h at 1 m from surface.
MODIFIED
e.g. if the calculated TI is  0.05, the TI can be stated as 0.

25. Category II Package – Yellow
>0.005 mSv/h and  0.5 mSv/h at the package surface.
0.01 mSv/h at 1 m from surface.
e.g. if the calculated TI is 0.05 the TI should be stated as 0.1.
MODIFIED

26. Category III Package – Yellow
0.5 mSv/h to  2 mSv/h at the package surface.
Between 0.01 and 0.1 mSv/h at 1 m from surface.
e.g. if the calculated TI is 1 the TI should be stated as 1 .
MODIFIED

27. Vehicle Placarding
Three placards on vehicle; both sides and rear + UN Number
Not required if carrying only excepted packages
MDIFIED

28. Documentation Requirements
Transport Document
Must include name and address of consignor and consignee and details of the packages and their contents. Paragraphs 546 (particulars of consignment: 13 items) and 547 (consignor’s declaration) of SSR 6.
Instructions for the carrier
Must include requirements for handling, loading, carriage, unloading, any modal specific requirements, if necessary, and emergency arrangements.
MODIFIED

29. Training and Quality Management Requirements
Training Requirements
All those involved in transport of radioactive material must receive appropriate training, commensurate with their responsibilities
Training should cover: hazards involved, necessary precautions, requirements of the regulations, actions in emergency, etc
Training should be given prior to starting work and refreshed periodically
Quality Management System
A QA program based on standards acceptable to the competent authority shall be established and implemented for the design, manufacture, testing, documentation, use, maintenance and inspection of all special form material, low dispersible material, packages and transport operations.
Level of training for each person involved in transport operation to be determined by employer, based on relative risk of packages being handled and transported.
IAEA has produced their ‘Quality Assurance for the Safe Transport of Radioactive Material’ document, Safety Series 113, to assist organisations draw up a suitable QA Program for the transport of radioactive material.

30. Radiation Protection Program and Emergency Arrangements
Systematic arrangements aimed at keeping doses to those involved in the transport of radioactive material as low as reasonably achievable, established for assessed effective dose according to para 303 of SSR 6.
Emergency Arrangements
Consignors must have appropriate emergency arrangements in place.
The IAEA publishes guidance on emergency preparedness in relation to the transport of radioactive materials in guidance document TS-G-1.2.
MODIFIED
Explain that transport of radioactive material should form part of the overall radiation protection Program designed to keep doses are low as reasonably practicable and below any statutory dose limits.

31. Dispatch of radioactive sources – disused sources
For disused or spent radioactive sources, the consignor shall provide information to the consignee and the Regulatory Body for each package or container, including:
the nuclide, number and activity of sources;
a description of the source construction including leakage tests;
a special form approval certificate, where appropriate;
a description of the package.
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

32. Dispatch of radioactive sources – disused sources (cont)
an approval certificate for a Type B package
details of any special arrangements required , including multilateral approvals, where necessary; and
a copy of the transport documents (to be sent to the consignee by fax or before dispatch).
The licensee shall not dispatch the consignment unless confirmation has been received from the consignee of willingness to accept it.
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

33. Dispatch of radioactive sources – disused sources (cont)
To prepare the consignment for dispatch, the consignor shall:
(a) load the sources into the package, verifying the details to be provided to the consignee (e.g. serial numbers) and to be entered on the transport document;
(b) close the package or container securely and examine and test it (noting any procedures from the supplier) to ensure that it is in good condition;
(c) carry out external contamination monitoring of the package or container to ensure that there is no residual radioactive material present and that it is suitable for transport.
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

34. Dispatch of radioactive sources – disused sources (cont)
To prepare the consignment for dispatch, the consignor shall:
(d) carry out dose-rate monitoring of the package or container and attach appropriate transport labels. The transport labels relating to the sources contained in the package or container when received should not be reused; and
(e) complete a transport document.
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

35. Dispatch of radioactive sources – disused sources (cont)
Arrangements shall also be made, where necessary, for:
(a) special handling equipment (e.g. cranes, forklift trucks) during transfer from one mode of transport to another, or between vehicles;
(b) ensuring that the package or container is securely attached to the vehicle and that the vehicle is correctly placard;
(c) dealing with border controls; and
(d) the security of the consignment during transport, particularly during delays or overnight stops.
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

36. Dispatch of radioactive sources – empty packages
The consignor shall be required to return the packaging or containers for the radioactive sources to the source supplier after receipt of a consignment of radioactive material.
These containers may be returned either empty or containing spent or disused radioactive sources, when they meet the requirements
For empty packages, the consignor shall:
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996
carry out dose-rate of outside and contamination monitoring of both the inside and inside of the package to ensure compliance with limits and that it can be treated as an empty package or container;

37. Dispatch of radioactive sources – empty packages (cont)
For empty packages, the consignor shall:
remove or cover all transport labels relating to the sources that were contained in the package or container;
examine the package or container to ensure it is in good condition and close it securely in accordance with any procedures provided by the source supplier;
attach a label to the outside of the package or container stating UN 2908.
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

38. Dispatch of radioactive sources – empty packages (cont)
For empty packages, the consignor shall:
complete a transport document;
contact the source supplier and agree on the transport route and responsibility for each stage of the journey; and
inform the supplier of the proposed date of dispatch.
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

39. Loading and unloading of sources
Loading and unloading operations may expose persons to dose rates in excess of those experienced in normal operation of the facility.
The licensee shall:
make an evaluation of source loading and unloading procedures to ensure that the exposure of persons is kept as low as reasonably achievable (ALARA). For packages with approval certificate, procedures are included in the approval and cannot be changed without permission (designer / competent authority involved)
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

40. Dispatch of radioactive substances
Prior to each shipment of radioactive material to be dispatched to the licensee, there shall be a detailed exchange of information with the source supplier.
For each package or container this information shall include:
(a) the nuclide, number and activity of sources;
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996
(b) a description of the source construction and performance tests, including leakage tests;
(c) special form approval certificate, where appropriate;

41. Dispatch of radioactive substances (cont)
(d) a description of the package;
(e) approval certificate for Type B package;
(f) details of any special arrangements required, including multilateral approvals, where necessary; and
(g) a copy of the transport documents, to be sent to the licensee (requirement for consignor) by fax or before dispatch if possible.
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

42. Dispatch of radioactive substances (cont)
The licensee shall not agree to the supplier dispatching the consignment unless satisfied that all the previous items are satisfactory.
The supplier and licensee should agree on the transport route and responsibility for each stage of the journey.
Arrangements shall also be made, where necessary, for:
(a) special handling equipment (e.g. cranes, forklift trucks) during transfer from one mode of transport to another, or between vehicles;
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996

43. Dispatch of radioactive substances (cont)
(b) checking radiation dose rates from the package or container;
(c) checking that correct transport labels are attached to the package or container, and replacing any that are damaged or illegible;
(d) ensuring that the package or container is securely attached to the vehicle and that the vehicle is correctly placard;
MODIFIED
Ref: Safety Series 107 pages:
Practice specific model regulations: radiation safety of non-medical irradiation facilities TECDOC __ Version 2 July 11,2001 pages 45-49
Safety Series No. 6 as amended 1990
IAEA Regulations for the Safe Transport of Radioactive Material, Safety Series No.ST-1, Vienna 1996
(e) dealing with border controls (customs); and
(f) the security of the consignment during transport, particularly during delays or overnight stops.

44. Responsibilities – Registrants and Licensees
Accountability and security of sources:
Records of source inventory (source characteristics, locations);
Periodic inventory of sources;
Records of receipt, transfer and disposal;
Transfers only to receiver holding a license;
Prompt communication of information to the Regulatory Authority regarding decontrolled, lost, stolen or missing sources.
MODIFIED

45. Demonstrating the toughness of a nuclear flask container in the UK.
The container survived with very little damage and is currently on display outside Heysham 2 nuclear power station in the north-west of England.