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CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
Element and Atomic No.
Activity concentration for exempt material (Bq/g)
Activity concentration for exempt material (Ci/g)
Activity limit for exempt consignment (Bq)
Activity limit for exempt consignment (Ci)
U−234 (fast lung absorption) (b)
Uranium (92)
1.0X101
2.7X10−10
1.0X104
2.7X10−7
U−234 (medium lung absorption) (c)
1.0X101
2.7X10−10
1.0X104
2.7X10−7
U−234 (slow lung absorption) (d)
1.0X101
2.7X10−10
1.0X104
2.7X10−7
U−235 (all lung absorption types) (a),(b),(c),(d)
1.0X101
2.7X10−10
1.0X104
2.7X10−7
U−236 (fast lung absorption) (b)
1.0X101
2.7X10−10
1.0X104
2.7X10−7
U−236 (medium lung absorption) (c)
1.0X101
2.7X10−10
1.0X104
2.7X10−7
U−236 (slow lung absorption) (d)
1.0X101
2.7X10−10
1.0X104
2.7X10−7
U−238 (all lung absorption types) (a), (b),(c),(d)
1.0X101
2.7X10−10
1.0X104
2.7X10−7
U (nat)(a)
1.0
2.7X10−11
1.0X103
2.7X10−8
U (enriched to 20% or less)(e)
1.0
2.7X10−11
1.0X103
2.7X10−8
U (dep)
1.0
2.7X10−11
1.0X103
2.7X10−8
V−48
Vanadium (23)
1.0X101
2.7X10−10
1.0X105
2.7X10−6
V−49
1.0X104
2.7X10−7
1.0X107
2.7X10−4
W−178
Tungsten (74)
1.0X101
2.7X10−10
1.0X106
2.7X10−5
W−181
1.0X103
2.7X10−8
1.0X107
2.7X10−4
W−185
1.0X104
2.7X10−7
1.0X107
2.7X10−4
W−187
1.0X102
2.7X10−9
1.0X106
2.7X10−5
W−188
1.0X102
2.7X10−9
1.0X105
2.7X10−6
Xe−122
Xenon (54)
1.0X102
2.7X10−9
1.0X109
2.7X10−2
Xe−123
1.0X102
2.7X10−9
1.0X109
2.7X10−2
Xe−127
1.0X103
2.7X10−8
1.0X105
2.7X10−6
Xe−131m
1.0X104
2.7X10−7
1.0X104
2.7X10−7
Xe−133
1.0X103
2.7X10−8
1.0X104
2.7X10−7
Xe−135
1.0X103
2.7X10−8
1.0X1010
2.7X10−1
Y−87
Yttrium (39)
1.0X101
2.7X10−10
1.0X106
2.7X10−5
Y−88
1.0X101
2.7X10−10
1.0X106
2.7X10−5
Y−90
1.0X103
2.7X10−8
1.0X105
2.7X10−6
TABLE VII
EXEMPT MATERIAL ACTIVITY CONCENTRATIONS AND EXEMPT
CONSIGNMENT ACTIVITY LIMITS FOR RADIONUCLIDES (Continued)
Symbol of Radionuclide
Element and Atomic No.
Activity concentration for exempt material (Bq/g)
Activity concentration for exempt material (Ci/g)
Activity limit for exempt consignment (Bq)
Activity limit for exempt consignment (Ci)
Y−91
1.0X103
2.7X10−8
1.0X106
2.7X10−5
Y−91m
1.0X102
2.7X10−9
1.0X106
2.7X10−5
Y−92
1.0X102
2.7X10−9
1.0X105
2.7X10−6
Y−93
1.0X102
2.7X10−9
1.0X105
2.7X10−6
Yb−169
Ytterbium (79)
1.0X102
2.7X10−9
1.0X107
2.7X10−4
Yb−175
1.0X103
2.7X10−8
1.0X107
2.7X10−4
Zn−65
Zinc (30)
1.0X101
2.7X10−10
1.0X106
2.7X10−5
Zn−69
1.0X104
2.7X10−7
1.0X106
2.7X10−5
Zn−69m
1.0X102
2.7X10−9
1.0X106
2.7X10−5
Zr−88
Zirconium (40)
1.0X102
2.7X10−9
1.0X106
2.7X10−5
Zr−93(a)
1.0X103
2.7X10−8
1.0X107
2.7X10−4
Zr−95
1.0X101
2.7X10−10
1.0X106
2.7X10−5
Zr−97 (a)
1.0X101
2.7X10−10
1.0X105
2.7X10−6
NOTES
(a) Parent nuclides and their progeny included in secular equilibrium are listed in the following:
Sr-90
Y-90
Zr-93
Nb-93m
Zr-97
Nb-97
Ru-106
Rh-106
Cs-137
Ba-137m
Ce-144
Pr-144
Ba-140
La-140
Bi-212
Tl-208 (0.36), Po-212 (0.64)
Pb-210
Bi-210, Po-210
Pb-212
Bi-212, Tl-208 (0.36), Po-212 (0.64)
Rn-222
Po-218, Pb-214, Bi-214, Po-214
Ra-223
Rn-219, Po-215, Pb-211, Bi-211, Tl-207
Ra-224
Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
Ra-226
Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210
Ra-228
Ac-228
Th-228
Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
Th-229
Ra-225, Ac-225, Fr-221, At-217, Bi-213, Po-213, Pb-209
Th-nat
Ra-228, Ac-228, Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
Th-234
Pa-234m
U-230
Th-226, Ra-222, Rn-218, Po-214
U-232
Th-228, Ra-224, Rn-220, Po-216, Pb-212, Bi-212, Tl-208 (0.36), Po-212 (0.64)
U-235
Th-231
U-238
Th-234, Pa-234m
U-nat
Th-234, Pa-234m, U-234, Th-230, Ra-226, Rn-222, Po-218, Pb-214, Bi-214, Po-214, Pb-210, Bi-210, Po-210
Np-237
Pa-233
Am-242m
Am-242
Am-243
Np-239
(b) These values apply only to compounds of uranium that take the chemical form of UF6, UO2F2, and UO2(NO3)2 in both normal and accident conditions of transport.
(c) These values apply only to compounds of uranium that take the chemical form of UO3, UF4, UCl4, and hexavalent compounds in both normal and accident conditions of transport.
(d) These values apply to all compounds of uranium other than those specified in (d) and (e), above.
(e) These values apply to unirradiated uranium only.
TABLE VIII
GENERAL VALUES FOR A1 AND A2
Contents
Only beta or gamma emitting radionuclides are known to be present
Alpha emitting nuclides, but no neutron emitters, are known to be present. (a)
Neutron emitting nuclides are known to be present or no relevant data are available
A1
(TBq)
1 x 10−1
2 x 10−1
1 x 10−3
(Ci)
2.7 x 100
5.4 x 100
2.7 x 10−
A2
(TBq)
2 x 10 −2
9 x 10−5
9 x 10−5
(Ci)
5.4 x 10−1
2.4 x 10−3
2.4 x 10−3
Activity concentration for exempt material
(Bq/g)
1 x 101
1 x 10−1
1 x 10−1
Activity concentration for exempt material
(Ci/g)
2.7 x10−10
2.7 x10−12
2.7 x10−12
Activity limits for exempt consignments
(Bq)
1 x 104
1 x 103
1 x 103
Activity limits for exempt consignments
(Ci)
2.7 x10−7
2.7 x10−
2.7 x10−8
(a) If beta or gamma emitting nuclides are known to be present, the A1 value of 0.1 TBq (2.7 Ci) should be used.
TABLE IX
ACTIVITY−MASS RELATIONSHIPS FOR URANIUM
Uranium Enrichment* wt % U−235 present
Specific Activity
TBq/g
Ci/g
0.45
1.9 x 10−8
5.0 x 10−7
0.72
2.6 x 10−8
7.1 x 10−7
1 2.
8 x 10−8
7.6 x 10−7
1.5
3.7 x 10−8
1.0 x 10−6
5
1.0 x 10−7
2.7 x 10−6
10
1.8 x 10−7
4.8 x 10−6
20
3.7 x 10−7
1.0 x 10−5
35
7.4 x 10−7
2.0 x 10−5
50
9.3 x 10−7
2.5 x 10−5
90
2.1 x 10−6
5.8 x 10−5
93
2.6 x 10−6
7.0 x 10−5
95
3.4 x 10−6
9.1 x 10−5
Natural thorium
8.1 x 10−9
2.2 x 10−7
Note: The figures for uranium include representative values for the activity of the uranium−234 that is concentrated
during the enrichment process.
SECTION 104. DHS 157 Appendix U is created to read:
Chapter DHS 157
APPENDIX U
Category 1 and Category 2 Quantity of Radioactive Material Thresholds
The sum of fractions’ methodology for evaluating combinations of multiple sources, aggregated sources, or multiple radionuclides is to be used in determining whether a location meets or exceeds the threshold and is thus subject to the requirements of subch. XV. Category 1 and category 2 quantities of radioactive material do not include the radioactive material contained in any fuel assembly, subassembly, fuel rod, or fuel pellet. The terabecquerel (TBq) values are the regulatory standard. The curie (Ci) values specified are obtained by converting from the TBq value. The curie values are provided for practical usefulness only.
 
Radioactive material
Category 1
(TBq)
Category 1
(Ci)
Category 2
(TBq)
Category 2
(Ci)
Americium-241......................................................................................
Americium-241/Be.................................................................................
Californium-252.....................................................................................
Cobalt-60...............................................................................................
Curium-244............................................................................................
Cesium-137...........................................................................................
Gadolinium-153.....................................................................................
Iridium-192............................................................................................
Plutonium-238.......................................................................................
Plutonium-239/Be..................................................................................
Promethium-147....................................................................................
Radium-226...........................................................................................
Selenium-75..........................................................................................
Strontium-90..........................................................................................
Thulium-170..........................................................................................
Ytterbium-169........................................................................................
60
60
20
30
50
100
1,000
80
60
60
40,000
40
200
1,000
20,000
300
1,620
1,620
540
810
1,350
2,700
27,000
2,160
1,620
1,620
1,080,000
1,080
5,400
27,000
540,000
8,100
0.6
0.6
0.2
0.3
0.5
1
10
0.8
0.6
0.6
400
0.4
2
10
200
3
16.2
16.2
5.40
8.10
13.5
27.0
270
21.6
16.2
16.2
10,800
10.8
54.0
270
5,400
81.0
Note: Calculations Concerning Multiple Sources or Multiple Radionuclides
I. If multiple sources of the same radionuclide or multiple radionuclides are aggregated at a location, the sum of the ratios of the total activity of each of the radionuclides shall be determined to verify whether the activity at the location is less than the category 1 or category 2 thresholds
of Appendix U, as appropriate. If the calculated sum of the ratios, using the equation below, is greater than or equal to 1.0, then the applicable requirements of subch. XV apply.
II. First determine the total activity for each radionuclide from Appendix U. This is done by adding the activity of each individual source, material in any device, and any loose or bulk material that contains the radionuclide. Then use the equation below to calculate the sum of the ratios by inserting the total activity of the applicable radionuclides from Appendix U in the numerator of the equation and the corresponding threshold activity from Table 1 in the denominator of the equation. Calculations shall be performed in metric values (i.e., TBq) and the numerator and denominator values shall be in the same units.
R1 = total activity for radionuclide 1
R2 = total activity for radionuclide 2
RN = total activity for radionuclide n
AR1 = activity threshold for radionuclide 1
AR2 = activity threshold for radionuclide 2
ARN = activity threshold for radionuclide n
SECTION 106. EFFECTIVE DATE: This rule shall take effect on the first day of the month following publication in the Wisconsin administrative register, as provided in s. 227.22 (2), Stats..
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