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Title 10 Part 20 → Subpart O

Title 10 → Chapter I → Part 20 → Subpart O

Electronic Code of Federal Regulations e-CFR

Title 10 Part 20 → Subpart O

e-CFR data is current as of September 18, 2019

Title 10Chapter IPart 20 → Subpart O


Title 10: Energy
PART 20—STANDARDS FOR PROTECTION AGAINST RADIATION


§20.2401   Violations.

(a) The Commission may obtain an injunction or other court order to prevent a violation of the provisions of—

(1) The Atomic Energy Act of 1954, as amended;

(2) Title II of the Energy Reorganization Act of 1974, as amended; or

(3) A regulation or order issued pursuant to those Acts.

(b) The Commission may obtain a court order for the payment of a civil penalty imposed under section 234 of the Atomic Energy Act:

(1) For violations of—

(i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107 or 109 of the Atomic Energy Act of 1954, as amended;

(ii) Section 206 of the Energy Reorganization Act;

(iii) Any rule, regulation, or order issued pursuant to the sections specified in paragraph (b)(1)(i) of this section; and

(iv) Any term, condition, or limitation of any license issued under the sections specified in paragraph (b)(1)(i) of this section.

(2) For any violation for which a license may be revoked under Section 186 of the Atomic Energy Act of 1954, as amended.

[56 FR 23408, May 21, 1991; 56 FR 61352, Dec. 3, 1991, as amended at 57 FR 55071, Nov. 24, 1992]

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§20.2402   Criminal penalties.

(a) Section 223 of the Atomic Energy Act of 1954, as amended, provides for criminal sanctions for willful violation of, attempted violation of, or conspiracy to violate, any regulation issued under sections 161b, 161i, or 161o of the Act. For purposes of section 223, all the regulations in §§20.1001 through 20.2402 are issued under one or more of sections 161b, 161i, or 161o, except for the sections listed in paragraph (b) this section.

(b) The regulations in §§20.1001 through 20.2402 that are not issued under Sections 161b, 161i, or 161o for the purposes of Section 223 are as follows: §§20.1001, 20.1002, 20.1003, 20.1004, 20.1005, 20.1006, 20.1007, 20.1008, 20.1009, 20.1405, 20.1704, 20.1903, 20.1905, 20.2002, 20.2007, 20.2301, 20.2302, 20.2401, and 20.2402.

[57 FR 55071, Nov. 24, 1992, as amended at 62 FR 39089, July 21, 1997]

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Appendix A to Part 20—Assigned Protection Factors for Respiratorsa

   Operating modeAssigned
Protection
Factors
I. Air Purifying Respirators [Particulateb only]c:
Filtering facepiece disposabledNegative Pressure(d)
Facepiece, halfeNegative Pressure10
Facepiece, fullNegative Pressure100
Facepiece, halfPowered air-purifying respirators50
Facepiece, fullPowered air-purifying respirators1000
Helmet/hoodPowered air-purifying respirators1000
Facepiece, loose-fittingPowered air-purifying respirators25
II. Atmosphere supplying respirators [particulate, gases and vaporsf]:
1. Air-line respirator:
Facepiece, halfDemand10
Facepiece, halfContinuous Flow50
Facepiece, halfPressure Demand50
Facepiece, fullDemand100
Facepiece, fullContinuous Flow1000
Facepiece, fullPressure Demand1000
Helmet/hoodContinuous Flow1000
Facepiece, loose-fittingContinuous Flow25
SuitContinuous Flow(g)
2. Self-contained breathing Apparatus (SCBA):
Facepiece, fullDemandh100
Facepiece, fullPressure Demandi10,000
Facepiece, fullDemand, Recirculatingh100
Facepiece, fullPositive Pressure Recirculatingi10,000
III. Combination Respirators:
Any combination of air-purifying and atmosphere-supplying respiratorsAssigned protection factor for type and mode of operation as listed above.

aThese assigned protection factors apply only in a respiratory protection program that meets the requirements of this Part. They are applicable only to airborne radiological hazards and may not be appropriate to circumstances when chemical or other respiratory hazards exist instead of, or in addition to, radioactive hazards. Selection and use of respirators for such circumstances must also comply with Department of Labor regulations.

   Radioactive contaminants for which the concentration values in Table 1, Column 3 of Appendix B to Part 20 are based on internal dose due to inhalation may, in addition, present external exposure hazards at higher concentrations. Under these circumstances, limitations on occupancy may have to be governed by external dose limits.

bAir purifying respirators with APF <100 must be equipped with particulate filters that are at least 95 percent efficient. Air purifying respirators with APF = 100 must be equipped with particulate filters that are at least 99 percent efficient. Air purifying respirators with APFs >100 must be equipped with particulate filters that are at least 99.97 percent efficient.

cThe licensee may apply to the Commission for the use of an APF greater than 1 for sorbent cartridges as protection against airborne radioactive gases and vapors (e.g., radioiodine).

dLicensees may permit individuals to use this type of respirator who have not been medically screened or fit tested on the device provided that no credit be taken for their use in estimating intake or dose. It is also recognized that it is difficult to perform an effective positive or negative pressure pre-use user seal check on this type of device. All other respiratory protection program requirements listed in §20.1703 apply. An assigned protection factor has not been assigned for these devices. However, an APF equal to 10 may be used if the licensee can demonstrate a fit factor of at least 100 by use of a validated or evaluated, qualitative or quantitative fit test.

eUnder-chin type only. No distinction is made in this Appendix between elastomeric half-masks with replaceable cartridges and those designed with the filter medium as an integral part of the facepiece (e.g., disposable or reusable disposable). Both types are acceptable so long as the seal area of the latter contains some substantial type of seal-enhancing material such as rubber or plastic, the two or more suspension straps are adjustable, the filter medium is at least 95 percent efficient and all other requirements of this Part are met.

fThe assigned protection factors for gases and vapors are not applicable to radioactive contaminants that present an absorption or submersion hazard. For tritium oxide vapor, approximately one-third of the intake occurs by absorption through the skin so that an overall protection factor of 3 is appropriate when atmosphere-supplying respirators are used to protect against tritium oxide. Exposure to radioactive noble gases is not considered a significant respiratory hazard, and protective actions for these contaminants should be based on external (submersion) dose considerations.

gNo NIOSH approval schedule is currently available for atmosphere supplying suits. This equipment may be used in an acceptable respiratory protection program as long as all the other minimum program requirements, with the exception of fit testing, are met (i.e., §20.1703).

hThe licensee should implement institutional controls to assure that these devices are not used in areas immediately dangerous to life or health (IDLH).

iThis type of respirator may be used as an emergency device in unknown concentrations for protection against inhalation hazards. External radiation hazards and other limitations to permitted exposure such as skin absorption shall be taken into account in these circumstances. This device may not be used by any individual who experiences perceptible outward leakage of breathing gas while wearing the device.

[64 FR 54558, Oct. 7, 1999; 64 FR 55524, Oct. 13, 1999]

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Appendix B to Part 20—Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage

Introduction

For each radionuclide table 1 indicates the chemical form which is to be used for selecting the appropriate ALI or DAC value. The ALIs and DACs for inhalation are given for an aerosol with an activity median aerodynamic diameter (AMAD) of 1 µm and for three classes (D,W,Y) of radioactive material, which refer to their retention (approximately days, weeks or years) in the pulmonary region of the lung. This classification applies to a range of clearance half-times of less than 10 days for D, for W from 10 to 100 days, and for Y greater than 100 days. The class (D, W, or Y) given in the column headed “Class” applies only to the inhalation ALIs and DACs given in table 1, columns 2 and 3. Table 2 provides concentration limits for airborne and liquid effluents released to the general environment. Table 3 provides concentration limits for discharges to sanitary sewer systems.

Notation

The values in tables 1, 2, and 3 are presented in the computer “E” notation. In this notation a value of 6E−02 represents a value of 6 × 10−2 or 0.06, 6E + 2 represents 6 × 102 or 600, and 6E + 0 represents 6 × 100 or 6.

Table 1 “Occupational”

Note that the columns in table 1, of this appendix captioned “Oral Ingestion ALI,” “Inhalation ALI,” and “DAC,” are applicable to occupational exposure to radioactive material.

The ALIs in this appendix are the annual intakes of a given radionuclide by “Reference Man” which would result in either (1) a committed effective dose equivalent of 5 rems (stochastic ALI) or (2) a committed dose equivalent of 50 rems to an organ or tissue (non-stochastic ALI). The stochastic ALIs were derived to result in a risk, due to irradiation of organs and tissues, comparable to the risk associated with deep dose equivalent to the whole body of 5 rems. The derivation includes multiplying the committed dose equivalent to an organ or tissue by a weighting factor, wT. This weighting factor is the proportion of the risk of stochastic effects resulting from irradiation of the organ or tissue, T, to the total risk of stochastic effects when the whole body is irradiated uniformly. The values of wT are listed under the definition of weighting factor in §20.1003. The non-stochastic ALIs were derived to avoid non-stochastic effects, such as prompt damage to tissue or reduction in organ function.

A value of wT = 0.06 is applicable to each of the five organs or tissues in the “remainder” category receiving the highest dose equivalents, and the dose equivalents of all other remaining tissues may be disregarded. The following parts of the GI tract—stomach, small intestine, upper large intestine, and lower large intestine—are to be treated as four separate organs.

Note that the dose equivalents for extremities (hands and forearms, feet and lower legs), skin, and lens of the eye are not considered in computing the committed effective dose equivalent, but are subject to limits that must be met separately.

When an ALI is defined by the stochastic dose limit, this value alone, is given. When an ALI is determined by the non-stochastic dose limit to an organ, the organ or tissue to which the limit applies is shown, and the ALI for the stochastic limit is shown in parentheses. (Abbreviated organ or tissue designations are used: LLI wall = lower large intestine wall; St. wall = stomach wall; Blad wall = bladder wall; and Bone surf = bone surface.)

The use of the ALIs listed first, the more limiting of the stochastic and non-stochastic ALIs, will ensure that non-stochastic effects are avoided and that the risk of stochastic effects is limited to an acceptably low value. If, in a particular situation involving a radionuclide for which the non-stochastic ALI is limiting, use of that non-stochastic ALI is considered unduly conservative, the licensee may use the stochastic ALI to determine the committed effective dose equivalent. However, the licensee shall also ensure that the 50-rem dose equivalent limit for any organ or tissue is not exceeded by the sum of the external deep dose equivalent plus the internal committed dose to that organ (not the effective dose). For the case where there is no external dose contribution, this would be demonstrated if the sum of the fractions of the nonstochastic ALIs (ALIns) that contribute to the committed dose equivalent to the organ receiving the highest dose does not exceed unity (i.e., Σ (intake (in µCi) of each radionuclide/ALIns) <1.0). If there is an external deep dose equivalent contribution of Hd then this sum must be less than l−(Hd/50) instead of being <1.0.

The derived air concentration (DAC) values are derived limits intended to control chronic occupational exposures. The relationship between the DAC and the ALI is given by: DAC = ALI(in µCi)/(2000 hours per working year × 60 minutes/hour × 2 × 104 ml per minute) = [ALI/2.4 × 109] µCi/ml, where 2 × 104 ml is the volume of air breathed per minute at work by “Reference Man” under working conditions of “light work.”

The DAC values relate to one of two modes of exposure: either external submersion or the internal committed dose equivalents resulting from inhalation of radioactive materials. Derived air concentrations based upon submersion are for immersion in a semi-infinite cloud of uniform concentration and apply to each radionuclide separately.

The ALI and DAC values relate to exposure to the single radionuclide named, but also include contributions from the in-growth of any daughter radionuclide produced in the body by the decay of the parent. However, intakes that include both the parent and daughter radionuclides should be treated by the general method appropriate for mixtures.

The value of ALI and DAC do not apply directly when the individual both ingests and inhales a radionuclide, when the individual is exposed to a mixture of radionuclides by either inhalation or ingestion or both, or when the individual is exposed to both internal and external radiation (see §20.1202). When an individual is exposed to radioactive materials which fall under several of the translocation classifications (i.e., Class D, Class W, or Class Y) of the same radionuclide, the exposure may be evaluated as if it were a mixture of different radionuclides.

It should be noted that the classification of a compound as Class D, W, or Y is based on the chemical form of the compound and does not take into account the radiological half-life of different radioisotopes. For this reason, values are given for Class D, W, and Y compounds, even for very short-lived radionuclides.

Table 2

The columns in table 2 of this appendix captioned “Effluents,” “Air,” and “Water,” are applicable to the assessment and control of dose to the public, particularly in the implementation of the provisions of §20.1302. The concentration values given in columns 1 and 2 of table 2 are equivalent to the radionuclide concentrations which, if inhaled or ingested continuously over the course of a year, would produce a total effective dose equivalent of 0.05 rem (50 millirem or 0.5 millisieverts).

Consideration of non-stochastic limits has not been included in deriving the air and water effluent concentration limits because non-stochastic effects are presumed not to occur at the dose levels established for individual members of the public. For radionuclides, where the non-stochastic limit was governing in deriving the occupational DAC, the stochastic ALI was used in deriving the corresponding airborne effluent limit in table 2. For this reason, the DAC and airborne effluent limits are not always proportional as was the case in appendix B to §§20.1-20.601.

The air concentration values listed in table 2, column 1, were derived by one of two methods. For those radionuclides for which the stochastic limit is governing, the occupational stochastic inhalation ALI was divided by 2.4 × 109 ml, relating the inhalation ALI to the DAC, as explained above, and then divided by a factor of 300. The factor of 300 includes the following components: a factor of 50 to relate the 5-rem annual occupational dose limit to the 0.1-rem limit for members of the public, a factor of 3 to adjust for the difference in exposure time and the inhalation rate for a worker and that for members of the public; and a factor of 2 to adjust the occupational values (derived for adults) so that they are applicable to other age groups.

For those radionuclides for which submersion (external dose) is limiting, the occupational DAC in table 1, column 3, was divided by 219. The factor of 219 is composed of a factor of 50, as described above, and a factor of 4.38 relating occupational exposure for 2,000 hours per year to full-time exposure (8,760 hours per year). Note that an additional factor of 2 for age considerations is not warranted in the submersion case.

The water concentrations were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 × 107. The factor of 7.3 × 107 (ml) includes the following components: the factors of 50 and 2 described above and a factor of 7.3 × 105 (ml) which is the annual water intake of “Reference Man.”

Note 2 of this appendix provides groupings of radionuclides which are applicable to unknown mixtures of radionuclides. These groupings (including occupational inhalation ALIs and DACs, air and water effluent concentrations and sewerage) require demonstrating that the most limiting radionuclides in successive classes are absent. The limit for the unknown mixture is defined when the presence of one of the listed radionuclides cannot be definitely excluded either from knowledge of the radionuclide composition of the source or from actual measurements.

Table 3 “Sewer Disposal”

The monthly average concentrations for release to sanitary sewers are applicable to the provisions in §20.2003. The concentration values were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 × 106 (ml). The factor of 7.3 × 106 (ml) is composed of a factor of 7.3 × 105 (ml), the annual water intake by “Reference Man,” and a factor of 10, such that the concentrations, if the sewage released by the licensee were the only source of water ingested by a reference man during a year, would result in a committed effective dose equivalent of 0.5 rem.

List of Elements

NameAtomic
SymbolNo.
ActiniumAc89
AluminumAl13
AmericiumAm95
AntimonySb51
ArgonAr18
ArsenicAs33
AstatineAt85
BariumBa56
BerkeliumBk97
BerylliumBe4
BismuthBi83
BromineBr35
CadmiumCd48
CalciumCa20
CaliforniumCf98
CarbonC6
CeriumCe58
CesiumCs55
ChlorineCl17
ChromiumCr24
CobaltCo27
CopperCu29
CuriumCm96
DysprosiumDy66
EinsteiniumEs99
ErbiumEr68
EuropiumEu63
FermiumFm100
FluorineF9
FranciumFr87
GadoliniumGd64
GalliumGa31
GermaniumGe32
GoldAu79
HafniumHf72
HolmiumHo67
HydrogenH1
IndiumIn49
IodineI53
IridiumIr77
IronFe26
KryptonKr36
LanthanumLa57
LeadPb82
LutetiumLu71
MagnesiumMg12
ManganeseMn25
MendeleviumMd101
MercuryHg80
MolybdenumMo42
NeodymiumNd60
NeptuniumNp93
NickelNi28
NiobiumNb41
NitrogenN7
OsmiumOs76
OxygenO8
PalladiumPd46
PhosphorusP15
PlatinumPt78
PlutoniumPu94
PoloniumPo84
PotassiumK19
PraseodymiumPr59
PromethiumPm61
ProtactiniumPa91
RadiumRa88
RadonRn86
RheniumRe75
RhodiumRh45
RubidiumRb37
RutheniumRu44
SamariumSm62
ScandiumSc21
SeleniumSe34
SiliconSi14
SilverAg47
SodiumNa11
StrontiumSr38
SulfurS16
TantalumTa73
TechnetiumTc43
TelluriumTe52
TerbiumTb65
ThalliumTl81
ThoriumTh90
ThuliumTm69
TinSn50
TitaniumTi22
TungstenW74
UraniumU92
VanadiumV23
XenonXe54
YtterbiumYb70
YttriumY39
ZincZn30
ZirconiumZr40
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[56 FR 23409, May 21, 1991; 56 FR 61352, Dec. 3, 1991, as amended at 57 FR 57879, Dec. 8, 1992. Redesignated at 58 FR 67659, Dec. 22, 1993, as amended at 71 FR 15007, Mar. 27, 2006; 72 FR 55922, Oct. 1, 2007; 75 FR 73938, Nov. 30, 2010]

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Appendix C to Part 20—Quantities1 of Licensed Material Requiring Labeling

RadionuclideQuantity (µCi)
Hydrogen-31,000
Beryllium-71,000
Beryllium-101
Carbon-111,000
Carbon-14100
Fluorine-181,000
Sodium-2210
Sodium-24100
Magnesium-28100
Aluminum-2610
Silicon-311,000
Silicon-321
Phosphorus-3210
Phosphorus-33100
Sulfur-35100
Chlorine-3610
Chlorine-381,000
Chlorine-391,000
Argon-391,000
Argon-411,000
Potassium-40100
Potassium-421,000
Potassium-431,000
Potassium-441,000
Potassium-451,000
Calcium-41100
Calcium-45100
Calcium-47100
Scandium-431,000
Scandium-44m100
Scandium-44100
Scandium-4610
Scandium-47100
Scandium-48100
Scandium-491,000
Titanium-441
Titanium-451,000
Vanadium-471,000
Vanadium-48100
Vanadium-491,000
Chromium-481,000
Chromium-491,000
Chromium-511,000
Manganese-511,000
Manganese-52m1,000
Manganese-52100
Manganese-531,000
Manganese-54100
Manganese-561,000
Iron-52100
Iron-55100
Iron-5910
Iron-601
Cobalt-55100
Cobalt-5610
Cobalt-57100
Cobalt-58m1,000
Cobalt-58100
Cobalt-60m1,000
Cobalt-601
Cobalt-611,000
Cobalt-62m1,000
Nickel-56100
Nickel-57100
Nickel-59100
Nickel-63100
Nickel-651,000
Nickel-6610
Copper-601,000
Copper-611,000
Copper-641,000
Copper-671,000
Zinc-62100
Zinc-631,000
Zinc-6510
Zinc-69m100
Zinc-691,000
Zinc-71m1,000
Zinc-72100
Gallium-651,000
Gallium-66100
Gallium-671,000
Gallium-681,000
Gallium-701,000
Gallium-72100
Gallium-731,000
Germanium-661,000
Germanium-671,000
Germanium-6810
Germanium-691,000
Germanium-711,000
Germanium-751,000
Germanium-771,000
Germanium-781,000
Arsenic-691,000
Arsenic-701,000
Arsenic-71100
Arsenic-72100
Arsenic-73100
Arsenic-74100
Arsenic-76100
Arsenic-77100
Arsenic-781,000
Selenium-701,000
Selenium-73m1,000
Selenium-73100
Selenium-75100
Selenium-79100
Selenium-81m1,000
Selenium-811,000
Selenium-831,000
Bromine-74m1,000
Bromine-741,000
Bromine-751,000
Bromine-76100
Bromine-771,000
Bromine-80m1,000
Bromine-801,000
Bromine-82100
Bromine-831,000
Bromine-841,000
Krypton-741,000
Krypton-761,000
Krypton-771,000
Krypton-791,000
Krypton-811,000
Krypton-83m1,000
Krypton-85m1,000
Krypton-851,000
Krypton-871,000
Krypton-881,000
Rubidium-791,000
Rubidium-81m1,000
Rubidium-811,000
Rubidium-82m1,000
Rubidium-83100
Rubidium-84100
Rubidium-86100
Rubidium-87100
Rubidium-881,000
Rubidium-891,000
Strontium-80100
Strontium-811,000
Strontium-83100
Strontium-85m1,000
Strontium-85100
Strontium-87m1,000
Strontium-8910
Strontium-900.1
Strontium-91100
Strontium-92100
Yttrium-86m1,000
Yttrium-86100
Yttrium-87100
Yttrium-8810
Yttrium-90m1,000
Yttrium-9010
Yttrium-91m1,000
Yttrium-9110
Yttrium-92100
Yttrium-93100
Yttrium-941,000
Yttrium-951,000
Zirconium-86100
Zirconium-8810
Zirconium-89100
Zirconium-931
Zirconium-9510
Zirconium-97100
Niobium-881,000
Niobium-89m (66 min)1,000
Niobium-89 (122 min)1,000
Niobium-90100
Niobium-93m10
Niobium-941
Niobium-95m100
Niobium-95100
Niobium-96100
Niobium-971,000
Niobium-981,000
Molybdenum-90100
Molybdenum-93m100
Molybdenum-9310
Molybdenum-99100
Molybdenum-1011,000
Technetium-93m1,000
Technetium-931,000
Technetium-94m1,000
Technetium-941,000
Technetium-96m1,000
Technetium-96100
Technetium-97m100
Technetium-971,000
Technetium-9810
Technetium-99m1,000
Technetium-99100
Technetium-1011,000
Technetium-1041,000
Ruthenium-941,000
Ruthenium-971,000
Ruthenium-103100
Ruthenium-1051,000
Ruthenium-1061
Rhodium-99m1,000
Rhodium-99100
Rhodium-100100
Rhodium-101m1,000
Rhodium-10110
Rhodium-102m10
Rhodium-10210
Rhodium-103m1,000
Rhodium-105100
Rhodium-106m1,000
Rhodium-1071,000
Palladium-100100
Palladium-1011,000
Palladium-103100
Palladium-10710
Palladium-109100
Silver-1021,000
Silver-1031,000
Silver-104m1,000
Silver-1041,000
Silver-105100
Silver-106m100
Silver-1061,000
Silver-108m1
Silver-110m10
Silver-111100
Silver-112100
Silver-1151,000
Cadmium-1041,000
Cadmium-1071,000
Cadmium-1091
Cadmium-113m0.1
Cadmium-113100
Cadmium-115m10
Cadmium-115100
Cadmium-117m1,000
Cadmium-1171,000
Indium-1091,000
Indium-110 (69.1min.)1,000
Indium-110
(4.9h)1,000
Indium-111100
Indium-1121,000
Indium-113m1,000
Indium-114m10
Indium-115m1,000
Indium-115100
Indium-116m1,000
Indium-117m1,000
Indium-1171,000
Indium-119m1,000
Tin-110100
Tin-1111,000
Tin-113100
Tin-117m100
Tin-119m100
Tin-121m100
Tin-1211,000
Tin-123m1,000
Tin-12310
Tin-12510
Tin-12610
Tin-1271,000
Tin-1281,000
Antimony-1151,000
Antimony-116m1,000
Antimony-1161,000
Antimony-1171,000
Antimony-118m1,000
Antimony-1191,000
Antimony-120 (16min.)1,000
Antimony-120 (5.76d)100
Antimony-122100
Antimony-124m1,000
Antimony-12410
Antimony-125100
Antimony-126m1,000
Antimony-126100
Antimony-127100
Antimony-128 (10.4min.)1,000
Antimony-128 (9.01h)100
Antimony-129100
Antimony-1301,000
Antimony-1311,000
Tellurium-1161,000
Tellurium-121m10
Tellurium-121100
Tellurium-123m10
Tellurium-123100
Tellurium-125m10
Tellurium-127m10
Tellurium-1271,000
Tellurium-129m10
Tellurium-1291,000
Tellurium-131m10
Tellurium-131100
Tellurium-13210
Tellurium-133m100
Tellurium-1331,000
Tellurium-1341,000
Iodine-120m1,000
Iodine-120100
Iodine-1211,000
Iodine-123100
Iodine-12410
Iodine-1251
Iodine-1261
Iodine-1281,000
Iodine-1291
Iodine-13010
Iodine-1311
Iodine-132m100
Iodine-132100
Iodine-13310
Iodine-1341,000
Iodine-135100
Xenon-1201,000
Xenon-1211,000
Xenon-1221,000
Xenon-1231,000
Xenon-1251,000
Xenon-1271,000
Xenon-129m1,000
Xenon-131m1,000
Xenon-133m1,000
Xenon-1331,000
Xenon-135m1,000
Xenon-1351,000
Xenon-1381,000
Cesium-1251,000
Cesium-1271,000
Cesium-1291,000
Cesium-1301,000
Cesium-1311,000
Cesium-132100
Cesium-134m1,000
Cesium-13410
Cesium-135m1,000
Cesium-135100
Cesium-13610
Cesium-13710
Cesium-1381,000
Barium-1261,000
Barium-128100
Barium-131m1,000
Barium-131100
Barium-133m100
Barium-133100
Barium-135m100
Barium-1391,000
Barium-140100
Barium-1411,000
Barium-1421,000
Lanthanum-1311,000
Lanthanum-132100
Lanthanum-1351,000
Lanthanum-13710
Lanthanum-138100
Lanthanum-140100
Lanthanum-141100
Lanthanum-1421,000
Lanthanum-1431,000
Cerium-134100
Cerium-135100
Cerium-137m100
Cerium-1371,000
Cerium-139100
Cerium-141100
Cerium-143100
Cerium-1441
Praseodymium-1361,000
Praseodymium-1371,000
Praseodymium-138m1,000
Praseodymium-1391,000
Praseodymium-142m1,000
Praseodymium-142100
Praseodymium-143100
Praseodymium-1441,000
Praseodymium-145100
Praseodymium-1471,000
Neodymium-1361,000
Neodymium-138100
Neodymium-139m1,000
Neodymium-1391,000
Neodymium-1411,000
Neodymium-147100
Neodymium-1491,000
Neodymium-1511,000
Promethium-1411,000
Promethium-143100
Promethium-14410
Promethium-14510
Promethium-1461
Promethium-14710
Promethium-148m10
Promethium-14810
Promethium-149100
Promethium-1501,000
Promethium-151100
Samarium-141m1,000
Samarium-1411,000
Samarium-1421,000
Samarium-145100
Samarium-1461
Samarium-147100
Samarium-15110
Samarium-153100
Samarium-1551,000
Samarium-1561,000
Europium-145100
Europium-146100
Europium-147100
Europium-14810
Europium-149100
Europium-150 (12.62h)100
Europium-150 (34.2y)1
Europium-152m100
Europium-1521
Europium-1541
Europium-15510
Europium-156100
Europium-157100
Europium-1581,000
Gadolinium-1451,000
Gadolinium-14610
Gadolinium-147100
Gadolinium-1480.001
Gadolinium-149100
Gadolinium-15110
Gadolinium-152100
Gadolinium-15310
Gadolinium-159100
Terbium-1471,000
Terbium-149100
Terbium-1501,000
Terbium-151100
Terbium-1531,000
Terbium-154100
Terbium-1551,000
Terbium-156m (5.0h)1,000
Terbium-156m (24.4h)1,000
Terbium-156100
Terbium-15710
Terbium-1581
Terbium-16010
Terbium-161100
Dysprosium-1551,000
Dysprosium-1571,000
Dysprosium-159100
Dysprosium-1651,000
Dysprosium-166100
Holmium-1551,000
Holmium-1571,000
Holmium-1591,000
Holmium-1611,000
Holmium-162m1,000
Holmium-1621,000
Holmium-164m1,000
Holmium-1641,000
Holmium-166m1
Holmium-166100
Holmium-1671,000
Erbium-1611,000
Erbium-1651,000
Erbium-169100
Erbium-171100
Erbium-172100
Thulium-1621,000
Thulium-166100
Thulium-167100
Thulium-17010
Thulium-17110
Thulium-172100
Thulium-173100
Thulium-1751,000
Ytterbium-1621,000
Ytterbium-166100
Ytterbium-1671,000
Ytterbium-169100
Ytterbium-175100
Ytterbium-1771,000
Ytterbium-1781,000
Lutetium-169100
Lutetium-170100
Lutetium-171100
Lutetium-172100
Lutetium-17310
Lutetium-174m10
Lutetium-17410
Lutetium-176m1,000
Lutetium-176100
Lutetium-177m10
Lutetium-177100
Lutetium-178m1,000
Lutetium-1781,000
Lutetium-1791,000
Hafnium-170100
Hafnium-1721
Hafnium-1731,000
Hafnium-175100
Hafnium-177m1,000
Hafnium-178m0.1
Hafnium-179m10
Hafnium-180m1,000
Hafnium-18110
Hafnium-182m1,000
Hafnium-1820.1
Hafnium-1831,000
Hafnium-184100
Tantalum-1721,000
Tantalum-1731,000
Tantalum-1741,000
Tantalum-1751,000
Tantalum-176100
Tantalum-1771,000
Tantalum-1781,000
Tantalum-179100
Tantalum-180m1,000
Tantalum-180100
Tantalum-182m1,000
Tantalum-18210
Tantalum-183100
Tantalum-184100
Tantalum-1851,000
Tantalum-1861,000
Tungsten-1761,000
Tungsten-1771,000
Tungsten-1781,000
Tungsten-1791,000
Tungsten-1811,000
Tungsten-185100
Tungsten-187100
Tungsten-18810
Rhenium-1771,000
Rhenium-1781,000
Rhenium-1811,000
Rhenium-182 (12.7h)1,000
Rhenium-182 (64.0h)100
Rhenium-184m10
Rhenium-184100
Rhenium-186m10
Rhenium-186100
Rhenium-1871,000
Rhenium-188m1,000
Rhenium-188100
Rhenium-189100
Osmium-1801,000
Osmium-1811,000
Osmium-182100
Osmium-185100
Osmium-189m1,000
Osmium-191m1,000
Osmium-191100
Osmium-193100
Osmium-1941
Iridium-1821,000
Iridium-1841,000
Iridium-1851,000
Iridium-186100
Iridium-1871,000
Iridium-188100
Iridium-189100
Iridium-190m1,000
Iridium-190100
Iridium-192 (73.8d)1
Iridium-192m (1.4min.)10
Iridium-194m10
Iridium-194100
Iridium-195m1,000
Iridium-1951,000
Platinum-1861,000
Platinum-188100
Platinum-1891,000
Platinum-191100
Platinum-193m100
Platinum-1931,000
Platinum-195m100
Platinum-197m1,000
Platinum-197100
Platinum-1991,000
Platinum-200100
Gold-1931,000
Gold-194100
Gold-19510
Gold-198m100
Gold-198100
Gold-199100
Gold-200m100
Gold-2001,000
Gold-2011,000
Mercury-193m100
Mercury-1931,000
Mercury-1941
Mercury-195m100
Mercury-1951,000
Mercury-197m100
Mercury-1971,000
Mercury-199m1,000
Mercury-203100
Thallium-194m1,000
Thallium-1941,000
Thallium-1951,000
Thallium-1971,000
Thallium-198m1,000
Thallium-1981,000
Thallium-1991,000
Thallium-2001,000
Thallium-2011,000
Thallium-202100
Thallium-204100
Lead-195m1,000
Lead-1981,000
Lead-1991,000
Lead-200100
Lead-2011,000
Lead-202m1,000
Lead-20210
Lead-2031,000
Lead-205100
Lead-2091,000
Lead-2100.01
Lead-211100
Lead-2121
Lead-214100
Bismuth-2001,000
Bismuth-2011,000
Bismuth-2021,000
Bismuth-203100
Bismuth-205100
Bismuth-206100
Bismuth-20710
Bismuth-210m0.1
Bismuth-2101
Bismuth-21210
Bismuth-21310
Bismuth-214100
Polonium-2031,000
Polonium-2051,000
Polonium-2071,000
Polonium-2100.1
Astatine-207100
Astatine-21110
Radon-2201
Radon-2221
Francium-222100
Francium-223100
Radium-2230.1
Radium-2240.1
Radium-2250.1
Radium-2260.1
Radium-2271,000
Radium-2280.1
Actinium-2241
Actinium-2250.01
Actinium-2260.1
Actinium-2270.001
Actinium-2281
Thorium-22610
Thorium-2270.01
Thorium-2280.001
Thorium-2290.001
Thorium-2300.001
Thorium-231100
Thorium-232100
Thorium-23410
Thorium-natural100
Protactinium-22710
Protactinium-2281
Protactinium-2300.1
Protactinium-2310.001
Protactinium-2321
Protactinium-233100
Protactinium-234100
Uranium-2300.01
Uranium-231100
Uranium-2320.001
Uranium-2330.001
Uranium-2340.001
Uranium-2350.001
Uranium-2360.001
Uranium-237100
Uranium-238100
Uranium-2391,000
Uranium-240100
Uranium-natural100
Neptunium-232100
Neptunium-2331,000
Neptunium-234100
Neptunium-235100
Neptunium-236 (1.15 × 105 y)0.001
Neptunium-236 (22.5h)1
Neptunium-2370.001
Neptunium-23810
Neptunium-239100
Neptunium-2401,000
Plutonium-23410
Plutonium-2351,000
Plutonium-2360.001
Plutonium-237100
Plutonium-2380.001
Plutonium-2390.001
Plutonium-2400.001
Plutonium-2410.01
Plutonium-2420.001
Plutonium-2431,000
Plutonium-2440.001
Plutonium-245100
Americium-2371,000
Americium-238100
Americium-2391,000
Americium-240100
Americium-2410.001
Americium-242m0.001
Americium-24210
Americium-2430.001
Americium-244m100
Americium-24410
Americium-2451,000
Americium-246m1,000
Americium-2461,000
Curium-238100
Curium-2400.1
Curium-2411
Curium-2420.01
Curium-2430.001
Curium-2440.001
Curium-2450.001
Curium-2460.001
Curium-2470.001
Curium-2480.001
Curium-2491,000
Berkelium-245100
Berkelium-246100
Berkelium-2470.001
Berkelium-2490.1
Berkelium-25010
Californium-244100
Californium-2461
Californium-2480.01
Californium-2490.001
Californium-2500.001
Californium-2510.001
Californium-2520.001
Californium-2530.1
Californium-2540.001
Any alpha emitting radionuclide not listed above or mixtures of alpha emitters of unknown composition0.001
Einsteinium-250100
Einsteinium-251100
Einsteinium-2530.1
Einsteinium-254m1
Einsteinium-2540.01
Fermium-2521
Fermium-2531
Fermium-25410
Fermium-2551
Fermium-2570.01
Mendelevium-25710
Mendelevium-2580.01
Any radionuclide other than alpha emitting radionuclides not listed above, or mixtures of beta emitters of unknown composition0.01

1The quantities listed above were derived by taking 110 th of the most restrictive ALI listed in table 1, columns 1 and 2, of appendix B to §§20.1001-20.2401 of this part, rounding to the nearest factor of 10, and arbitrarily constraining the values listed between 0.001 and 1,000 µCi. Values of 100 µCi have been assigned for radionuclides having a radioactive half-life in excess of 109 years (except rhenium, 1000 µCi) to take into account their low specific activity.

Note: For purposes of §§20.1902(e), 20.1905(a), and 20.2201(a) where there is involved a combination of radionuclides in known amounts, the limit for the combination should be derived as follows: determine, for each radionuclide in the combination, the ratio between the quantity present in the combination and the limit otherwise established for the specific radionuclide when not in combination. The sum of such ratios for all radionuclides in the combination may not exceed “1” (i.e., “unity”).

[56 FR 23465, May 21, 1991; 56 FR 61352, Dec. 3, 1991. Redesignated and amended at 58 FR 67659, Dec. 22, 1993; 60 FR 20186, Apr. 25, 1995]

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Appendix D to Part 20—United States Nuclear Regulatory Commission Regional Offices

   Address Telephone (24 hour) E-Mail
NRC Headquarters Operations CenterUSNRC, Division of Incident Response Operations, Washington, DC 20555-0001(301) 816-5100
(301) 951-0550
(301) 816-5151 (fax)
[email protected]
Region I: Connecticut, Delaware, District of Columbia, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and VermontUSNRC, Region I, 2100 Renaissance Boulevard, Suite 100, King of Prussia, PA 19406-2713(610) 337-5000, (800) 432-1156 TDD: (301) 415-5575[email protected]
Region II: Alabama, Florida, Georgia, Kentucky, North Carolina, Puerto Rico, South Carolina, Tennessee, Virginia, Virgin Islands, and West VirginiaUSNRC, Region II, 245 Peachtree Center Avenue, NE., Suite 1200, Atlanta, GA 30303-1257.(404) 997-4000
(800) 877-8510
TDD: (301) 415-5575
[email protected]
Region III: Illinois, Indiana, Iowa, Michigan, Minnesota, Missouri, Ohio and WisconsinUSNRC, Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352(630) 829-9500
(800) 522-3025
TDD: (301) 415-5575
[email protected]
Region IV: Alaska, Arizona, Arkansas, California, Colorado, Hawaii, Idaho, Kansas, Louisiana, Mississippi, Montana, Nebraska, Nevada, New Mexico, North Dakota, Oklahoma, Oregon, South Dakota, Texas, Utah, Washington, Wyoming, and the U.S. territories and possessions in the PacificUS NRC, Region IV, 1600 E. Lamar Blvd., Arlington, TX 76011-4511.(817) 860-8100
(800) 952-9677
TDD: (301) 415-5575
[email protected]

[68 FR 58802, Oct. 10, 2003, as amended at 71 FR 15007, Mar. 27, 2006; 73 FR 30457, May 28, 2008; 75 FR 21980, Apr. 27, 2010; 76 FR 72084, Nov. 22, 2011; 77 FR 39905, July 6, 2012; 79 FR 66602, Nov. 10, 2014]

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Appendix E to Part 20— Nationally Tracked Source Thresholds

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 and are rounded after conversion.

Radioactive material Category 1
(TBq)
Category 1
(Ci)
Category 2
(TBq)
Category 2
(Ci)
Actinium-227205400.25.4
Americium-241601,6000.616
Americium-241/Be601,6000.616
Californium-252205400.25.4
Cobalt-60308100.38.1
Curium-244501,4000.514
Cesium-1371002,700127
Gadolinium-1531,00027,00010270
Iridium-192802,2000.822
Plutonium-238601,6000.616
Plutonium-239/Be601,6000.616
Polonium-210601,6000.616
Promethium-14740,0001,100,00040011,000
Radium-226401,1000.411
Selenium-752005,400254
Strontium-901,00027,00010270
Thorium-228205400.25.4
Thorium-229205400.25.4
Thulium-17020,000540,0002005,400
Ytterbium-1693008,100381

[71 FR 65708, Nov. 8, 2006]

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Appendix F to Part 20 [Reserved]

Appendix G to Part 20—Requirements for Transfers of Low-Level Radioactive Waste Intended for Disposal at Licensed Land Disposal Facilities and Manifests

I. Manifest

A waste generator, collector, or processor who transports, or offers for transportation, low-level radioactive waste intended for ultimate disposal at a licensed low-level radioactive waste land disposal facility must prepare a Manifest (OMB Control Numbers 3150-0164, -0165, and -0166) reflecting information requested on applicable NRC Forms 540 (Uniform Low-Level Radioactive Waste Manifest (Shipping Paper)) and 541 (Uniform Low-Level Radioactive Waste Manifest (Container and Waste Description)) and, if necessary, on an applicable NRC Form 542 (Uniform Low-Level Radioactive Waste Manifest (Manifest Index and Regional Compact Tabulation)). NRC Forms 540 and 540A must be completed and must physically accompany the pertinent low-level waste shipment. Upon agreement between shipper and consignee, NRC Forms 541 and 541A and 542 and 542A may be completed, transmitted, and stored in electronic media with the capability for producing legible, accurate, and complete records on the respective forms. Licensees are not required by NRC to comply with the manifesting requirements of this part when they ship:

(a) LLW for processing and expect its return (i.e., for storage under their license) prior to disposal at a licensed land disposal facility;

(b) LLW that is being returned to the licensee who is the “waste generator” or “generator,” as defined in this part; or

(c) Radioactively contaminated material to a “waste processor” that becomes the processor's “residual waste.”

For guidance in completing these forms, refer to the instructions that accompany the forms. Copies of manifests required by this appendix may be legible carbon copies, photocopies, or computer printouts that reproduce the data in the format of the uniform manifest.

NRC Forms 540, 540A, 541, 541A, 542 and 542A, and the accompanying instructions, in hard copy, may be obtained by writing or calling the Office of the Chief Information Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-7232, or by visiting the NRC's Web site at http://www.nrc.gov and selecting forms from the index found on the home page.

This appendix includes information requirements of the Department of Transportation, as codified in 49 CFR part 172. Information on hazardous, medical, or other waste, required to meet Environmental Protection Agency regulations, as codified in 40 CFR parts 259, 261 or elsewhere, is not addressed in this section, and must be provided on the required EPA forms. However, the required EPA forms must accompany the Uniform Low-Level Radioactive Waste Manifest required by this chapter.

As used in this appendix, the following definitions apply:

Chelating agent has the same meaning as that given in §61.2 of this chapter.

Chemical description means a description of the principal chemical characteristics of a low-level radioactive waste.

Computer-readable medium means that the regulatory agency's computer can transfer the information from the medium into its memory.

Consignee means the designated receiver of the shipment of low-level radioactive waste.

Decontamination facility means a facility operating under a Commission or Agreement State license whose principal purpose is decontamination of equipment or materials to accomplish recycle, reuse, or other waste management objectives, and, for purposes of this part, is not considered to be a consignee for LLW shipments.

Disposal container means a container principally used to confine low-level radioactive waste during disposal operations at a land disposal facility (also see “high integrity container”). Note that for some shipments, the disposal container may be the transport package.

EPA identification number means the number received by a transporter following application to the Administrator of EPA as required by 40 CFR part 263.

Generator means a licensee operating under a Commission or Agreement State license who (1) is a waste generator as defined in this part, or (2) is the licensee to whom waste can be attributed within the context of the Low-Level Radioactive Waste Policy Amendments Act of 1985 (e.g., waste generated as a result of decontamination or recycle activities).

High integrity container (HIC) means a container commonly designed to meet the structural stability requirements of §61.56 of this chapter, and to meet Department of Transportation requirements for a Type A package.

Land disposal facility has the same meaning as that given in §61.2 of this chapter.

NRC Forms 540, 540A, 541, 541A, 542, and 542A are official NRC Forms referenced in this appendix. Licensees need not use originals of these NRC Forms as long as any substitute forms are equivalent to the original documentation in respect to content, clarity, size, and location of information. Upon agreement between the shipper and consignee, NRC Forms 541 (and 541A) and NRC Forms 542 (and 542A) may be completed, transmitted, and stored in electronic media. The electronic media must have the capability for producing legible, accurate, and complete records in the format of the uniform manifest.

Package means the assembly of components necessary to ensure compliance with the packaging requirements of DOT regulations, together with its radioactive contents, as presented for transport.

Physical description means the items called for on NRC Form 541 to describe a low-level radioactive waste.

Residual waste means low-level radioactive waste resulting from processing or decontamination activities that cannot be easily separated into distinct batches attributable to specific waste generators. This waste is attributable to the processor or decontamination facility, as applicable.

Shipper means the licensed entity (i.e., the waste generator, waste collector, or waste processor) who offers low-level radioactive waste for transportation, typically consigning this type of waste to a licensed waste collector, waste processor, or land disposal facility operator.

Shipping paper means NRC Form 540 and, if required, NRC Form 540A which includes the information required by DOT in 49 CFR part 172.

Source material has the same meaning as that given in §40.4 of this chapter.

Special nuclear material has the same meaning as that given in §70.4 of this chapter.

Uniform Low-Level Radioactive Waste Manifest or uniform manifest means the combination of NRC Forms 540, 541, and, if necessary, 542, and their respective continuation sheets as needed, or equivalent.

Waste collector means an entity, operating under a Commission or Agreement State license, whose principal purpose is to collect and consolidate waste generated by others, and to transfer this waste, without processing or repackaging the collected waste, to another licensed waste collector, licensed waste processor, or licensed land disposal facility.

Waste description means the physical, chemical and radiological description of a low-level radioactive waste as called for on NRC Form 541.

Waste generator means an entity, operating under a Commission or Agreement State license, who (1) possesses any material or component that contains radioactivity or is radioactively contaminated for which the licensee foresees no further use, and (2) transfers this material or component to a licensed land disposal facility or to a licensed waste collector or processor for handling or treatment prior to disposal. A licensee performing processing or decontamination services may be a “waste generator” if the transfer of low-level radioactive waste from its facility is defined as “residual waste.”

Waste processor means an entity, operating under a Commission or Agreement State license, whose principal purpose is to process, repackage, or otherwise treat low-level radioactive material or waste generated by others prior to eventual transfer of waste to a licensed low-level radioactive waste land disposal facility.

Waste type means a waste within a disposal container having a unique physical description (i.e., a specific waste descriptor code or description; or a waste sorbed on or solidified in a specifically defined media).

Information Requirements

A. General Information

The shipper of the radioactive waste, shall provide the following information on the uniform manifest:

1. The name, facility address, and telephone number of the licensee shipping the waste;

2. An explicit declaration indicating whether the shipper is acting as a waste generator, collector, processor, or a combination of these identifiers for purposes of the manifested shipment; and

3. The name, address, and telephone number, or the name and EPA identification number for the carrier transporting the waste.

B. Shipment Information

The shipper of the radioactive waste shall provide the following information regarding the waste shipment on the uniform manifest:

1. The date of the waste shipment;

2. The total number of packages/disposal containers;

3. The total disposal volume and disposal weight in the shipment;

4. The total radionuclide activity in the shipment;

5. The activity of each of the radionuclides H-3, C-14, Tc-99, and I-129 contained in the shipment; and

6. The total masses of U-233, U-235, and plutonium in special nuclear material, and the total mass of uranium and thorium in source material.

C. Disposal Container and Waste Information

The shipper of the radioactive waste shall provide the following information on the uniform manifest regarding the waste and each disposal container of waste in the shipment:

1. An alphabetic or numeric identification that uniquely identifies each disposal container in the shipment;

2. A physical description of the disposal container, including the manufacturer and model of any high integrity container;

3. The volume displaced by the disposal container;

4. The gross weight of the disposal container, including the waste;

5. For waste consigned to a disposal facility, the maximum radiation level at the surface of each disposal container;

6. A physical and chemical description of the waste;

7. The total weight percentage of chelating agent for any waste containing more than 0.1% chelating agent by weight, plus the identity of the principal chelating agent;

8. The approximate volume of waste within a container;

9. The sorbing or solidification media, if any, and the identity of the solidification media vendor and brand name;

10. The identities and activities of individual radionuclides contained in each container, the masses of U-233, U-235, and plutonium in special nuclear material, and the masses of uranium and thorium in source material. For discrete waste types (i.e., activated materials, contaminated equipment, mechanical filters, sealed source/devices, and wastes in solidification/stabilization media), the identities and activities of individual radionuclides associated with or contained on these waste types within a disposal container shall be reported;

11. The total radioactivity within each container; and

12. For wastes consigned to a disposal facility, the classification of the waste pursuant to §61.55 of this chapter. Waste not meeting the structural stability requirements of §61.56(b) of this chapter must be identified.

D. Uncontainerized Waste Information

The shipper of the radioactive waste shall provide the following information on the uniform manifest regarding a waste shipment delivered without a disposal container:

1. The approximate volume and weight of the waste;

2. A physical and chemical description of the waste;

3. The total weight percentage of chelating agent if the chelating agent exceeds 0.1% by weight, plus the identity of the principal chelating agent;

4. For waste consigned to a disposal facility, the classification of the waste pursuant to §61.55 of this chapter. Waste not meeting the structural stability requirements of §61.56(b) of this chapter must be identified;

5. The identities and activities of individual radionuclides contained in the waste, the masses of U-233, U-235, and plutonium in special nuclear material, and the masses of uranium and thorium in source material; and

6. For wastes consigned to a disposal facility, the maximum radiation levels at the surface of the waste.

E. Multi-Generator Disposal Container Information

This section applies to disposal containers enclosing mixtures of waste originating from different generators. (Note: The origin of the LLW resulting from a processor's activities may be attributable to one or more “generators” (including “waste generators”) as defined in this part). It also applies to mixtures of wastes shipped in an uncontainerized form, for which portions of the mixture within the shipment originate from different generators.

1. For homogeneous mixtures of waste, such as incinerator ash, provide the waste description applicable to the mixture and the volume of the waste attributed to each generator.

2. For heterogeneous mixtures of waste, such as the combined products from a large compactor, identify each generator contributing waste to the disposal container, and, for discrete waste types (i.e., activated materials, contaminated equipment, mechanical filters, sealed source/devices, and wastes in solidification/stabilization media), the identities and activities of individual radionuclides contained on these waste types within the disposal container. For each generator, provide the following:

(a) The volume of waste within the disposal container;

(b) A physical and chemical description of the waste, including the solidification agent, if any;

(c) The total weight percentage of chelating agents for any disposal container containing more than 0.1% chelating agent by weight, plus the identity of the principal chelating agent;

(d) The sorbing or solidification media, if any, and the identity of the solidification media vendor and brand name if the media is claimed to meet stability requirements in 10 CFR 61.56(b); and

(e) Radionuclide identities and activities contained in the waste, the masses of U-233, U-235, and plutonium in special nuclear material, and the masses of uranium and thorium in source material if contained in the waste.

II. Certification

An authorized representative of the waste generator, processor, or collector shall certify by signing and dating the shipment manifest that the transported materials are properly classified, described, packaged, marked, and labeled and are in proper condition for transportation according to the applicable regulations of the Department of Transportation and the Commission. A collector in signing the certification is certifying that nothing has been done to the collected waste which would invalidate the waste generator's certification.

III. Control and Tracking

A. Any licensee who transfers radioactive waste to a land disposal facility or a licensed waste collector shall comply with the requirements in paragraphs A.1 through 9 of this section. Any licensee who transfers waste to a licensed waste processor for waste treatment or repackaging shall comply with the requirements of paragraphs A.4 through 9 of this section. A licensee shall:

1. Prepare all wastes so that the waste is classified according to §61.55 and meets the waste characteristics requirements in §61.56 of this chapter;

2. Label each disposal container (or transport package if potential radiation hazards preclude labeling of the individual disposal container) of waste to identify whether it is Class A waste, Class B waste, Class C waste, or greater then Class C waste, in accordance with §61.55 of this chapter;

3. Conduct a quality assurance program to assure compliance with §§61.55 and 61.56 of this chapter (the program must include management evaluation of audits);

4. Prepare the NRC Uniform Low-Level Radioactive Waste Manifest as required by this appendix;

5. Forward a copy or electronically transfer the Uniform Low-Level Radioactive Waste Manifest to the intended consignee so that either (i) receipt of the manifest precedes the LLW shipment or (ii) the manifest is delivered to the consignee with the waste at the time the waste is transferred to the consignee. Using both (i) and (ii) is also acceptable;

6. Include NRC Form 540 (and NRC Form 540A, if required) with the shipment regardless of the option chosen in paragraph A.5 of this section;

7. Receive acknowledgement of the receipt of the shipment in the form of a signed copy of NRC Form 540;

8. Retain a copy of or electronically store the Uniform Low-Level Radioactive Waste Manifest and documentation of acknowledgement of receipt as the record of transfer of licensed material as required by 10 CFR parts 30, 40, and 70 of this chapter; and

9. For any shipments or any part of a shipment for which acknowledgement of receipt has not been received within the times set forth in this appendix, conduct an investigation in accordance with paragraph E of this appendix.

B. Any waste collector licensee who handles only prepackaged waste shall:

1. Acknowledge receipt of the waste from the shipper within one week of receipt by returning a signed copy of NRC Form 540;

2. Prepare a new manifest to reflect consolidated shipments that meet the requirements of this appendix. The waste collector shall ensure that, for each container of waste in the shipment, the manifest identifies the generator of that container of waste;

3. Forward a copy or electronically transfer the Uniform Low-Level Radioactive Waste Manifest to the intended consignee so that either: (i) Receipt of the manifest precedes the LLW shipment or (ii) the manifest is delivered to the consignee with the waste at the time the waste is transferred to the consignee. Using both (i) and (ii) is also acceptable;

4. Include NRC Form 540 (and NRC Form 540A, if required) with the shipment regardless of the option chosen in paragraph B.3 of this section;

5. Receive acknowledgement of the receipt of the shipment in the form of a signed copy of NRC Form 540;

6. Retain a copy of or electronically store the Uniform Low-Level Radioactive Waste Manifest and documentation of acknowledgement of receipt as the record of transfer of licensed material as required by 10 CFR parts 30, 40, and 70 of this chapter;

7. For any shipments or any part of a shipment for which acknowledgement of receipt has not been received within the times set forth in this appendix, conduct an investigation in accordance with paragraph E of this appendix; and

8. Notify the shipper and the Administrator of the nearest Commission Regional Office listed in appendix D of this part when any shipment, or part of a shipment, has not arrived within 60 days after receipt of an advance manifest, unless notified by the shipper that the shipment has been cancelled.

C. Any licensed waste processor who treats or repackages waste shall:

1. Acknowledge receipt of the waste from the shipper within one week of receipt by returning a signed copy of NRC Form 540;

2. Prepare a new manifest that meets the requirements of this appendix. Preparation of the new manifest reflects that the processor is responsible for meeting these requirements. For each container of waste in the shipment, the manifest shall identify the waste generators, the preprocessed waste volume, and the other information as required in paragraph I.E. of this appendix;

3. Prepare all wastes so that the waste is classified according to §61.55 of this chapter and meets the waste characteristics requirements in §61.56 of this chapter;

4. Label each package of waste to identify whether it is Class A waste, Class B waste, or Class C waste, in accordance with §§61.55 and 61.57 of this chapter;

5. Conduct a quality assurance program to assure compliance with §§61.55 and 61.56 of this chapter (the program shall include management evaluation of audits);

6. Forward a copy or electronically transfer the Uniform Low-Level Radioactive Waste Manifest to the intended consignee so that either: (i) Receipt of the manifest precedes the LLW shipment or (ii) the manifest is delivered to the consignee with the waste at the time the waste is transferred to the consignee. Using both (i) and (ii) is also acceptable;

7. Include NRC Form 540 (and NRC Form 540A, if required) with the shipment regardless of the option chosen in paragraph C.6 of this section;

8. Receive acknowledgement of the receipt of the shipment in the form of a signed copy of NRC Form 540;

9. Retain a copy of or electronically store the Uniform Low-Level Radioactive Waste Manifest and documentation of acknowledgement of receipt as the record of transfer of licensed material as required by 10 CFR parts 30, 40, and 70 of this chapter;

10. For any shipment or any part of a shipment for which acknowledgement of receipt has not been received within the times set forth in this appendix, conduct an investigation in accordance with paragraph E of this appendix; and

11. Notify the shipper and the Administrator of the nearest Commission Regional Office listed in appendix D of this part when any shipment, or part of a shipment, has not arrived within 60 days after receipt of an advance manifest, unless notified by the shipper that the shipment has been cancelled.

D. The land disposal facility operator shall:

1. Acknowledge receipt of the waste within one week of receipt by returning, as a minimum, a signed copy of NRC Form 540 to the shipper. The shipper to be notified is the licensee who last possessed the waste and transferred the waste to the operator. If any discrepancy exists between materials listed on the Uniform Low-Level Radioactive Waste Manifest and materials received, copies or electronic transfer of the affected forms must be returned indicating the discrepancy;

2. Maintain copies of all completed manifests and electronically store the information required by 10 CFR 61.80(l) until the Commission terminates the license; and

3. Notify the shipper and the Administrator of the nearest Commission Regional Office listed in appendix D of this part when any shipment, or part of a shipment, has not arrived within 60 days after receipt of an advance manifest, unless notified by the shipper that the shipment has been cancelled.

E. Any shipment or part of a shipment for which acknowledgement is not received within the times set forth in this section must:

1. Be investigated by the shipper if the shipper has not received notification or receipt within 20 days after transfer; and

2. Be traced and reported. The investigation shall include tracing the shipment and filing a report with the nearest Commission Regional Office listed in appendix D to this part. Each licensee who conducts a trace investigation shall file a written report with the appropriate NRC Regional Office within 2 weeks of completion of the investigation.

[60 FR 15664, Mar. 27, 1995, as amended at 60 FR 25983, May 16, 1995; 68 FR 58802, Oct. 10, 2003; 73 FR 30457, May 28, 2008; 80 FR 74979, Dec. 1, 2015]

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