Louisiana Administrative Code › Title 33 - ENVIRONMENTAL QUALITY › Part XV - Radiation Protection › Chapter 15 - Transportation of Radioactive Material › Section XV-1599 - Appendix-Incorporation by Reference of 10 CFR Part 71, Appendix A, Tables A-1, A-2, A-3, and A-4; Procedures for Determining A[1] and A[2]

Current through Register Vol. 50, No. 6, June 20, 2024
A. Tables A-1, A-2, A-3, and A-4 in  10 CFR
				Part 71, Appendix A, October 16, 2020, are hereby incorporated by reference.
				These tables are used to determine the values of A1 and A2, as described in
				Subsections B-F of this Section.
B.
				Values of A1 and A2 for
				individual radionuclides, which are the bases for many activity limits
				elsewhere in these regulations, are given in Table A-1. The curie (Ci) values
				specified are obtained by converting from the Terabecquerel (TBq) value. The
				Terabecquerel values are the regulatory standard. The curie values are for
				information only and are not intended to be the regulatory standard. Where
				values of A1 and A2 are
				unlimited, the values are for radiation control purposes only. For nuclear
				criticality safety, some materials are subject to controls placed on fissile
				material.
C. For individual
				radionuclides whose identities are known, but which are not listed in Table
				A-1, the A1 and A2 values
				contained in Table A-3 may be used. Otherwise, the licensee shall obtain prior
				U.S. NRC approval of the A1 and
				A2 values for radionuclides not listed in Table A-1,
				before shipping the material. For individual radionuclides whose identities are
				known, but which are not listed in Table A-2, the exempt material activity
				concentration and exempt consignment activity values contained in Table A-3 may
				be used. Otherwise, the licensee shall obtain prior U.S. NRC approval of the
				exempt material activity concentration and exempt consignment activity values
				for radionuclides not listed in Table A-2, before shipping the material. The
				licensee shall submit the requests for prior approval described in this
				Subsection to the U.S. NRC, in accordance with
				10 CFR
				71.1.
D. In the calculations of
				A1 and A2 for a radionuclide not
				in Table A-1, a single radioactive decay chain, in which radionuclides are
				present in their naturally-occurring proportions, and in which no daughter
				radionuclide has a half-life either longer than 10 days, or longer than that of
				the parent radionuclide, shall be considered as a single radionuclide, and the
				activity to be taken into account, and the A1 or
				A2 value to be applied, shall be those corresponding to
				the parent radionuclide of that chain. In the case of radioactive decay chains
				in which any daughter radionuclide has a half-life either longer than 10 days,
				or greater than that of the parent radionuclide, the parent and those daughter
				radionuclides shall be considered as mixtures of different
				radionuclides.
E. For mixtures of
				radionuclides whose identities and respective activities are known, the
				following conditions apply.
1. For special
				form radioactive material, the maximum quantity that may be transported in a
				Type A package is as follows.
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where:
B(i) = the activity of radionuclide i in special form
A1(i) = the A1 value for radionuclide i
2. For normal form radioactive material, the
				maximum quantity that may be transported in a Type A package is as follow
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where:
B(i) = the activity of radionuclide i in normal form
A2(i) = the A2 value for radionuclide i
3. If the package contains both special and
				normal form radioactive material, the activity that may be transported in a
				Type A package is as follows.
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where:
B(i) = the activity of radionuclide i as special form
				  radioactive material
A1(i) = the A1 value for radionuclide i
C(j) = the activity of radionuclide j as normal form
				  radioactive material
A2(j) = the A2 value for radionuclide j.
4. Alternatively, the A1 value for mixtures
				of special form material may be determined as follows.
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where:
f(i) = the fraction of activity for radionuclide i in the
				  mixture
A1(i) = the appropriate A1 value for radionuclide
				  i
5. Alternatively, the A2
				value for mixtures of normal form material may be determined as follows.
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where:
f(i) = the fraction of activity for radionuclide i in the
				  mixture
A2(i) = the appropriate A2 value for radionuclide
				  i
6. The exempt activity
				concentration for mixtures of nuclides may be determined as follows.
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where:
f(i) = the fraction of activity concentration of radionuclide
				  i in the mixture
[A]= the activity concentration for exempt material
				  containing radionuclide i
7. The activity limit for an exempt
				consignment for mixtures of radionuclides may be determined as follows.
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where:
f(i) = the fraction of activity of radionuclide i in the
				  mixture
A(i) = the activity limit for exempt consignments for
				  radionuclide i