10 C.F.R. § 71.22   General license: Fissile material.


Title 10 - Energy


Title 10: Energy
PART 71—PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL
Subpart C—General Licenses

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§ 71.22   General license: Fissile material.

(a) A general license is issued to any licensee of the Commission 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 this part; however, the material must be contained in a Type A package. The Type A package must also meet the DOT requirements of 49 CFR 173.417(a).

(b) The general license applies only to a licensee who has a quality assurance program approved by the Commission as satisfying the provisions of subpart H of this part.

(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 500 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 section;

(2) Has a value less than or equal to 10; and

(3) For a shipment of multiple packages containing fissile material, the sum of the CSIs must be less than or equal to 50 (for shipment on a nonexclusive use conveyance) and less than or equal to 100 (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:

(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 Tables 71–1 or 71–2, as appropriate;

(4) If Table 71–2 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 71–1 values for X, Y, and Z must be used to determine the CSI if:

(i) Uranium-233 is present in the package;

(ii) The mass of plutonium exceeds 1 percent of the mass of uranium-235;

(iii) The uranium is of unknown uranium-235 enrichment or greater than 24 weight percent enrichment; or

(iv) 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.

  Table 71-1_Mass Limits for General License Packages Containing Mixed Quantities of Fissile Material or Uranium-235 of Unknown Enrichment per                             § 71.22(e)------------------------------------------------------------------------                                   Fissile material    Fissile material                                    mass mixed with     mass mixed with                                      moderating          moderating                                   substances having   substances having        Fissile material              an average          an average                                   hydrogen density    hydrogen density                                  less than or equal   greater than H2Oa                                    to H2O (grams)          (grams)------------------------------------------------------------------------\235\ U (X).....................                 60                  38\233\ U (Y).....................                 43                  27\239\ Pu or \241\ Pu (Z)........                 37                  24------------------------------------------------------------------------a When mixtures of moderating substances are present, the lower mass  limits shall be used if more than 15 percent of the moderating  substance has an average hydrogen density greater than H2O.
 Table 71-2_Mass Limits for General License Packages Containing Uranium-               235 of Known Enrichment per § 71.22(e)------------------------------------------------------------------------                                                               Fissile                                                              material    Uranium enrichment in weight percent of \235\ U not        mass of                         exceeding                           \235\ U (X)                                                               (grams)------------------------------------------------------------------------24........................................................           6020........................................................           6315........................................................           6711........................................................           7210........................................................           769.5.......................................................           789.........................................................           818.5.......................................................           828.........................................................           857.5.......................................................           887.........................................................           906.5.......................................................           936.........................................................           975.5.......................................................          1025.........................................................          1084.5.......................................................          1144.........................................................          1203.5.......................................................          1323.........................................................          1502.5.......................................................          1802.........................................................          2461.5.......................................................          4081.35......................................................          4801.........................................................        1,0200.92......................................................        1,800------------------------------------------------------------------------

[69 FR 3786, Jan. 26, 2004; 69 FR 58038, Sept. 29, 2004]

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