Ohio Administrative Code|Rule 3701:1-50-11 | General license: Fissile material.

                                                
(A) A general license is issued to any
		  licensee of the department to transport fissile material, or to deliver fissile
		  material to a carrier for transport, if the material is shipped in accordance
		  with this section. The fissile material need not be contained in a package
		  which meets the standards of subparts E and F of 10 C.F.R. 71 (as published in
		  the January 1, 2014 Code of Federal Regulations); however, the material must be
		  contained in a type A package. The type A package must also meet the DOT
		  requirements of 49 C.F.R. 173.417(a) (as published in the October 1, 2014 Code
		  of Federal Regulations).
(B) The general license applies only to a
		  licensee who has a quality assurance program approved by the department as
		  satisfying the provisions of rule 3701:1-50-24 of the Administrative
		  Code.
(C) The general license applies only when
		  a package's contents:
(1) Contain no more than
			 a type A quantity of radioactive material; and
(2) Contain less than
			 five hundred total grams of beryllium, graphite, or hydrogenous material
			 enriched in deuterium.
(D) The general license applies only to
		  packages containing fissile material that are labeled with a CSI
		  which:
(1) Has been determined
			 in accordance with paragraph (E) of this rule;
(2) Has a value less than
			 or equal to ten; and
(3) For a shipment of
			 multiple packages containing fissile material, the sum of the CSIs must be less
			 than or equal to fifty (for shipment on a nonexclusive use conveyance) and less
			 than or equal to one hundred (for shipment on an exclusive use
			 conveyance).
(E)  
(1) The value for the CSI
			 must be greater than or equal to the number calculated by the following
			 equation:
CSI = 10((grams of U-235/X) + (grams of
			 U-233/Y) + (grams of Pu/Z))
(2) The calculated CSI
			 must be rounded up to the first decimal place;
(3) The values of X, Y,
			 and Z used in the CSI equation must be taken from table 11-1 or table 11-2, as
			 appropriate;
(4) If table 11-2 is used
			 to obtain the value of X, then the values for the terms in the equation for
			 uranium-233 and plutonium must be assumed to be zero; and
(5) Table 11-1 values for
			 X, Y, and Z must be used to determine the CSI if:
(a) Uranium-233 is present in the package;
(b) The mass of plutonium exceeds one per cent of the mass of
				uranium-235;
(c) The uranium is of unknown uranium-235 enrichment or greater
				than twenty-four weight per cent enrichment; or
(d) Substances having a moderating effectiveness (i.e., an
				average hydrogen density greater than H2O) (e.g., certain hydrocarbon oils or plastics)
				are present in any form, except as polyethylene used for packing or
				wrapping.
Fissilematerial
Fissile material mass mixedwith moderating substances having an average hydrogen density less than orequal to H2O (grams)
Fissile material mass mixed with moderatingsubstances having an average hydrogen density greater than H2Oa(grams)
U-235(X)
60
38
U-233(Y)
43
27
Pu-239or Pu-241 (Z)
37
24
a When
		mixtures of moderating substances are present, the lower mass limits shall be
		used if more than fifteen per cent of the moderating substance has an average
		hydrogen density greater than H2O.
Uranium enrichment in weight per cent of U-235 notexceeding
Fissile material mass ofU-235 (X) (grams)
24
60
20
63
15
67
11
72
10
76
9.5
78
9
81
8.5
82
8
85
7.5
88
7
90
6.5
93
6
97
5.5
102
5
108
4.5
114
4
120
3.5
132
3
150
2.5
180
2
246
1.5
408
1.35
480
1
1,020
0.92
1,800