For individual radionuclides:
(a) Which are not listed in Table 2.2.7.2.2.1 the determination of the basic radionuclide valuesreferred to in 2.2.7.2.2.1 shall require multilateral approval. For these radionuclides, activityconcentration limits for exempt material and activity limits for exempt consignments shall becalculated in accordance with the principles established in the International Basic SafetyStandards for Protection against Ionizing Radiation and for the Safety of Radiation Sources,Safety Series No.115, IAEA, Vienna (1996). It is permissible to use an A2value calculatedusing a dose coefficient for the appropriate lung absorption type as recommended by theInternational Commission on Radiological Protection, if the chemical forms of eachradionuclide under both normal and accident conditions of carriage are taken intoconsideration. Alternatively, the radionuclide values in Table2.2.7.2.2.2 may be used withoutobtaining competent authority approval;
(b) In instruments or articles in which the radioactive material is enclosed or is included as acomponent part of the instrument or other manufactured article and which meet 2.2.7.2.4.1.3(c), alternative basicradionuclide values to those in Table 2.2.7.2.2.1 for the activity limit foran exempt consignment are permitted and shall require multilateral approval. Such alternativeactivity limits for an exempt consignment shall be calculated in accordance with theprinciplesset out in the International Basic Safety Standards for Protection against Ionizing Radiation andfor the Safety of Radiation Sources, Safety Series No.115, IAEA, Vienna (1996).
Table 2.2.7.2.2.2: Basic radionuclide values for unknown radionuclides or mixtures
|
Radioactive contents |
A1 |
A2 |
Activity |
Activity |
|
(TBq) |
(TBq) |
(Bq/g) |
(Bq) |
|
|
Only beta or gamma emitting nuclides are known to be present |
0,1 |
0,02 |
1 x 101 |
1 x 104 |
|
Alpha emitting nuclides but no neutron emitters are known to be present |
0,2 |
9 x 10-5 |
1 x 10-1 |
1 x 103 |
|
Neutron emitting nuclides are known to be present or no relevant data are available |
0,001 |
9 x 10-5 |
1 x 10-1 |
1 x 103 |
In the calculations of A1and A2for a radionuclide not in Table2.2.7.2.2.1, a single radioactive decay chain in which the radionuclides are present in their naturally occurring proportions, and in which no daughter nuclide has a half-life either longer than 10 days or longer than that of the parent nuclide, shall be considered as a single radionuclide; and the activity to be taken into account and the A1or A2value to be applied shall be those corresponding to the parent nuclide of that chain. In the case of radioactive decay chains in which any daughter nuclide has a half-life either longer than 10 days or greater than that of the parent nuclide, the parent and such daughter nuclides shall be considered as mixtures of different nuclides.
For mixtures of radionuclides, the basic radionuclide values referred to in2.2.7.2.2.1 may be determined as follows:
where, 
f(i) is the fraction of activity or activity concentration of radionuclide i in the mixture;
X(i) is the appropriate value of A1or A2, or the activity concentration limitfor exempt material or the activity limit for an exempt consignment as appropriate for the radionuclide i; and
Xm is the derived value of A1or A2, or the activity concentration limitfor exempt material or the activity limit for an exempt consignment in the case of a mixture.
When the identity of each radionuclide is known but the individual activities of some of the radionuclides are not known, the radionuclides may be grouped and the lowest radionuclide value, as appropriate, for the radionuclides in each group may be used in applying the formulas in 2.2.7.2.2.4 and 2.2.7.2.4.4. Groups may be based on the total alpha activity and the total beta/gamma activity when these are known, using the lowest radionuclide values for the alpha emitters or beta/gamma emitters, respectively.
For individual radionuclides or for mixtures of radionuclides for which relevant data are not available, the values shown in Table 2.2.7.2.2.2 shall be used.
Determination of other material characteristics
Low specific activity (LSA) material
LSA material shall be in one of three groups:
(a)LSA-I
(i)uranium and thorium ores and concentrates of such ores, and other ores containingnaturally occurring radionuclides;
(ii)natural uranium, depleted uranium, natural thorium or their compounds or mixtures, thatare unirradiated and in solid or liquid form;
(iii)radioactive material for which the A2value is unlimited. Fissile material may beincluded only if excepted under 2.2.7.2.3.5;
(iv)other radioactive material in which the activity is distributed throughout and theestimated average specific activity does not exceed 30 times the values for activityconcentration specified in 2.2.7.2.2.1 to2.2.7.2.2.6.Fissile material may be includedonly if excepted under 2.2.7.2.3.5;
(b)LSA-II
(i)water with tritium concentration up to 0.8 TBq/l;
(ii)other material in which the activity is distributed throughout and the estimated averagespecific activity does not exceed 10-4 A2/g for solids and gases, and 10-5 A2/g forliquids;
(c)LSA-III- Solids (e.g. consolidated wastes, activated materials), excluding powders, that meetthe requirementsof 2.2.7.2.3.1.3,in which:
(i)the radioactive material is distributed throughout a solid or a collection of solid objects,or is essentially uniformly distributed in a solid compact binding agent (such asconcrete, bitumen and ceramic);
(ii)the radioactive material is relatively insoluble, or it is intrinsically contained in arelatively insoluble matrix, so that, even under loss of packaging, the loss of radioactivematerial per package by leaching when placed in water for seven days would not exceed0.1 A2; and
(iii)the estimated average specific activity of the solid, excluding any shielding material,does not exceed 2×10-3 A2/g.
LSA-III material shall be a solid of such a nature that if the entire contents of a package were subjected to the test specified in 2.2.7.2.3.1.4 the activity in the water would not exceed 0.1 A2.
LSA-III material shall be tested as follows:
A solid material sample representing the entire contents of the package shall be immersed for 7days in water at ambient temperature. The volume of water to be used in the test shall be sufficient to ensure that at the end of the7 day test period the free volume of the unabsorbed and unreacted water remaining shall be at least 10% of the volume of the solid test sample itself. The water shall have an initial pH of 6-8 and a maximum conductivity of 1mS/m at 20°C. The total activity of the free volume of water shall be measured following the 7 day immersion of the test sample.
Demonstration of compliance with the performance standards in2.2.7.2.3.1.4 shallbe in accordance with6.4.12.1 and 6.4.12.2.
Surface contaminated object (SCO)
SCO is classified in one of two groups:
(a)SCO-I: A solid object on which:
(i)the non-fixed contamination on the accessible surface averaged over 300cm2(or thearea of the surface if less than 300 cm2) does not exceed 4Bq/cm2for beta and gammaemitters and low toxicity alpha emitters, or 0.4 Bq/cm2for all other alpha emitters; and
(ii)the fixed contamination on the accessible surface averaged over 300cm2(or the area ofthe surface if less than 300 cm2) does not exceed 4 ×104Bq/cm2for beta and gammaemitters and low toxicity alpha emitters, or 4 ×103Bq/cm2for all other alpha emitters;and
(iii)the non-fixed contamination plus the fixed contamination on the inaccessible surfaceaveraged over 300 cm2(or the area of the surface if less than 300 cm2) does not exceed4 ×104Bq/cm2for beta and gamma emitters and low toxicity alpha emitters, or4 ×103Bq/cm2for all other alpha emitters;
(b)SCO-II: A solid object on which either the fixed or non-fixed contamination on the surfaceexceeds the applicable limits specified for SCO-I in (a) above and on which:
(i)the non-fixed contamination on the accessible surface averaged over 300cm2(or thearea of the surface if less than 300 cm2) does not exceed 400Bq/cm2for beta andgamma emitters and low toxicity alpha emitters, or 40 Bq/cm2for all other alphaemitters; and
(ii)the fixed contamination on the accessible surface, averaged over 300cm2(or the area ofthe surface if less than 300 cm2) does not exceed 8 ×105Bq/cm2for beta and gammaemitters and low toxicity alpha emitters, or 8×104Bq/cm2for all other alpha emitters;and
(iii)the non-fixed contamination plus the fixed contamination on the inaccessible surfaceaveraged over 300 cm2(or the area of the surface if less than 300 cm2) does not exceed8 ×105Bq/cm2for beta and gamma emitters and low toxicity alpha emitters, or8 ×104Bq/cm2for all other alpha emitters.
Special form radioactive material
Special form radioactive material shall have at least one dimension not less than 5mm. When a sealed capsule constitutes part of the special form radioactive material, the capsule shall be so manufactured that it can be opened only by destroying it.The design for special form radioactive material requires unilateral approval.