10 CFR Part 20 — Standards for Protection Against Radiation

PART 20—STANDARDS FOR PROTECTION AGAINST RADIATION Authority: Atomic Energy Act of 1954, secs. 11, 53, 63, 65, 81, 103, 104, 161, 170H, 182, 186, 223, 234, 274, 1701 (42 U.S.C. 2014, 2073, 2093, 2095, 2111, 2133, 2134, 2201, 2210h, 2232, 2236, 2273, 2282, 2021, 2297f); Energy Reorganization Act of 1974, secs. 201, 202 (42 U.S.C. 5841, 5842); Low-Level Radioactive Waste Policy Amendments Act of 1985, sec. 2 (42 U.S.C. 2021b); 44 U.S.C. 3504 note. Subpart A—General Provisions Source: 56 FR 23391, May 21, 1991, unless otherwise noted. § 20.1001 Purpose. (a) The regulations in this part establish standards for protection against ionizing radiation resulting from activities conducted under licenses issued by the Nuclear Regulatory Commission. These regulations are issued under the Atomic Energy Act of 1954, as amended, and the Energy Reorganization Act of 1974, as amended. (b) It is the purpose of the regulations in this part to control the receipt, possession, use, transfer, and disposal of licensed material by any licensee in such a manner that the total dose to an individual (including doses resulting from licensed and unlicensed radioactive material and from radiation sources other than background radiation) does not exceed the standards for protection against radiation prescribed in the regulations in this part. However, nothing in this part shall be construed as limiting actions that may be necessary to protect health and safety. § 20.1002 Scope. The regulations in this part apply to persons licensed by the Commission to receive, possess, use, transfer, or dispose of byproduct, source, or special nuclear material or to operate a production or utilization facility under parts 30 through 36 or part 39, 40, 50, 52, 53, 60, 61, 63, 70, or 72 of this chapter, and in accordance with 10 CFR 76.60 to persons required to obtain a certificate of compliance or an approved compliance plan under part 76 of this chapter. The limits in this part do not apply to doses due to background radiation, to exposure of patients to radiation for the purpose of medical diagnosis or therapy, to exposure from individuals administered radioactive material and released under § 35.75, or to exposure from voluntary participation in medical research programs. [72 FR 49485, Aug. 28, 2007, as amended at 91 FR 15772, Mar. 30, 2026; 91 FR 18772, Apr. 13, 2026] § 20.1003 Definitions. As used in this part: Absorbed dose Accelerator-produced radioactive material Act et seq. Activity Adult Airborne radioactive material Airborne radioactivity area (1) In excess of the derived air concentrations (DACs) specified in appendix B, to §§ 20.1001-20.2401, or (2) To such a degree that an individual present in the area without respiratory protective equipment could exceed, during the hours an individual is present in a week, an intake of 0.6 percent of the annual limit on intake (ALI) or 12 DAC-hours. Air-purifying respirator ALARA Annual limit on intake Assigned protection factor (APF) Atmosphere-supplying respirator Background radiation “Background radiation” Bioassay Byproduct material (1) Any radioactive material (except special nuclear material) yielded in, or made radioactive by, exposure to the radiation incident to the process of producing or using special nuclear material; (2) The tailings or wastes produced by the extraction or concentration of uranium or thorium from ore processed primarily for its source material content, including discrete surface wastes resulting from uranium solution extraction processes. Underground ore bodies depleted by these solution extraction operations do not constitute “byproduct material” within this definition; (3)(i) Any discrete source of radium-226 that is produced, extracted, or converted after extraction, before, on, or after August 8, 2005, for use for a commercial, medical, or research activity; or (ii) Any material that— (A) Has been made radioactive by use of a particle accelerator; and (B) Is produced, extracted, or converted after extraction, before, on, or after August 8, 2005, for use for a commercial, medical, or research activity; and (4) Any discrete source of naturally occurring radioactive material, other than source material, that— (i) The Commission, in consultation with the Administrator of the Environmental Protection Agency, the Secretary of Energy, the Secretary of Homeland Security, and the head of any other appropriate Federal agency, determines would pose a threat similar to the threat posed by a discrete source of radium-226 to the public health and safety or the common defense and security; and (ii) Before, on, or after August 8, 2005, is extracted or converted after extraction for use in a commercial, medical, or research activity. Class lung class inhalation class Collective dose Commission Committed dose equivalent T,50 Committed effective dose equivalent E,50 E,50 T T,50 Constraint (dose constraint) Controlled area Critical Group Declared pregnant woman Decommission (1) Release of the property for unrestricted use and termination of the license; or (2) Release of the property under restricted conditions and the termination of the license. Deep-dose equivalent d 2 Demand respirator Department et seq. Derived air concentration Derived air concentration-hour Discrete source Disposable respirator Distinguishable from background Dose radiation dose Dose equivalent T Dosimetry processor Effective dose equivalent E T T E T T Embryo/fetus Entrance or access point Exposure External dose Extremity Filtering facepiece (dust mask) Fit factor Fit test Generally applicable environmental radiation standards Government agency Gray Helmet High radiation area Hood Individual Individual monitoring (1) The assessment of dose equivalent by the use of devices designed to be worn by an individual; (2) The assessment of committed effective dose equivalent by bioassay (see Bioassay (3) The assessment of dose equivalent by the use of survey data. Individual monitoring devices Internal dose Lens dose equivalent (LDE) 2 License Licensed material Licensee Limits Loose-fitting facepiece Lost or missing licensed material Member of the public Minor Monitoring Nationally tracked source Negative pressure respirator (tight fitting) Nonstochastic effect NRC Occupational dose Particle accelerator Person (1) Any individual, corporation, partnership, firm, association, trust, estate, public or private institution, group, Government agency other than the Commission or the Department of Energy (except that the Department shall be considered a person within the meaning of the regulations in 10 CFR chapter I to the extent that its facilities and activities are subject to the licensing and related regulatory authority of the Commission under section 202 of the Energy Reorganization Act of 1974 (88 Stat. 1244), the Uranium Mill Tailings Radiation Control Act of 1978 (92 Stat. 3021), the Nuclear Waste Policy Act of 1982 (96 Stat. 2201), and section 3(b)(2) of the Low-Level Radioactive Waste Policy Amendments Act of 1985 (99 Stat. 1842)), any State or any political subdivision of or any political entity within a State, any foreign government or nation or any political subdivision of any such government or nation, or other entity; and (2) Any legal successor, representative, agent, or agency of the foregoing. Planned special exposure Positive pressure respirator Powered air-purifying respirator (PAPR) Pressure demand respirator Public dose Qualitative fit test (QLFT) Quality Factor (Q) Quantitative fit test (QNFT) Quarter Rad Radiation Radiation area Reference man Rem Residual radioactivity Respiratory protective device Restricted area Sanitary sewerage Self-contained breathing apparatus (SCBA) Shallow-dose equivalent (H s ), 2 Site boundary Source material (1) Uranium or thorium or any combination of uranium and thorium in any physical or chemical form; or (2) Ores that contain, by weight, one-twentieth of 1 percent (0.05 percent), or more, of uranium, thorium, or any combination of uranium and thorium. Source material does not include special nuclear material. Special nuclear material (1) Plutonium, uranium-233, uranium enriched in the isotope 233 or in the isotope 235, and any other material that the Commission, pursuant to the provisions of section 51 of the Act, determines to be special nuclear material, but does not include source material; or (2) Any material artificially enriched by any of the foregoing but does not include source material. Stochastic effects Supplied-air respirator (SAR) airline respirator Survey Tight-fitting facepiece Total Effective Dose Equivalent Unrestricted area Uranium fuel cycle User seal check (fit check) Very high radiation area Note: At very high doses received at high dose rates, units of absorbed dose (e.g., rads and grays) are appropriate, rather than units of dose equivalent (e.g., rems and sieverts)). Waste Week Weighting factor T T Organ Dose Weighting Factors Organ or tissue w T Gonads 0.25 Breast 0.15 Red bone marrow 0.12 Lung 0.12 Thyroid 0.03 Bone surfaces 0.03 Remainder 1 Whole Body 2 1 2 T Whole body Working level 5 Working level month Year [56 FR 23391, May 21, 1991, as amended at 57 FR 57878, Dec. 8, 1992; 58 FR 7736, Feb. 9, 1993; 60 FR 36043, July 13, 1995; 60 FR 48625, Sept. 20, 1995; 61 FR 65127, Dec. 10, 1996; 62 FR 4133, Jan. 29, 1997; 62 FR 39087, July 21, 1997; 63 FR 39481, July 23, 1998; 64 FR 54556, Oct. 7, 1999; 66 FR 55789, Nov. 2, 2001; 67 FR 16304, Apr. 5, 2002; 67 FR 20370, Apr. 24, 2002; 67 FR 62872, Oct. 9, 2002; 71 FR 65707, Nov. 8, 2006; 72 FR 55921, Oct. 1, 2007; 72 FR 68058, Dec. 4, 2007; 74 FR 62680, Dec. 1, 2009; 91 FR 15772, Mar. 30, 2026] § 20.1004 Units of radiation dose. (a) Definitions. Gray Rad Rem Sievert (b) As used in this part, the quality factors for converting absorbed dose to dose equivalent are shown in table 1004(b).1. Table 1004( b Type of radiation Quality factor Absorbed dose equal to a unit dose equivalent a (Q) X-, gamma, or beta radiation 1 1 Alpha particles, multiple-charged particles, fission fragments and heavy particles of unknown charge 20 0.05 Neutrons of unknown energy 10 0.1 High-energy protons 10 0.1 a (c) If it is more convenient to measure the neutron fluence rate than to determine the neutron dose equivalent rate in rems per hour or sieverts per hour, as provided in paragraph (b) of this section, 1 rem (0.01 Sv) of neutron radiation of unknown energies may, for purposes of the regulations in this part, be assumed to result from a total fluence of 25 million neutrons per square centimeter incident upon the body. If sufficient information exists to estimate the approximate energy distribution of the neutrons, the licensee may use the fluence rate per unit dose equivalent or the appropriate Q value from table 1004(b).2 to convert a measured tissue dose in rads to dose equivalent in rems. Table 1004( b Neutron energy (MeV) Quality factor a Fluence per unit dose equivalent b −2 −1 (thermal) 2.5 × 10 −8 2 980 × 10 6 1 × 10 −7 2 980 × 10 6 1 × 10 −6 2 810 × 10 6 1 × 10 −5 2 810 × 10 6 1 × 10 −4 2 840 × 10 6 1 × 10 −3 2 980 × 10 6 1 × 10 −2 2.5 1010 × 10 6 1 × 10 −1 7.5 170 × 10 6 5 × 10 −1 11 39 × 10 6 1 11 27 × 10 6 2.5 9 29 × 10 6 5 8 23 × 10 6 7 7 24 × 10 6 10 6.5 24 × 10 6 14 7.5 17 × 10 6 20 8 16 × 10 6 40 7 14 × 10 6 60 5.5 16 × 10 6 1 × 10 2 4 20 × 10 6 2 × 10 2 3.5 19 × 10 6 3 × 10 2 3.5 16 × 10 6 4 × 10 2 3.5 14 × 10 6 a b § 20.1005 Units of radioactivity. For the purposes of this part, activity is expressed in the special unit of curies (Ci) or in the SI unit of becquerels (Bq), or their multiples, or disintegrations (transformations) per unit of time. (a) One becquerel = 1 disintegration per second (s −1 (b) One curie = 3.7 × 10 10 10 12 [56 FR 23391, May 21, 1991; 56 FR 61352, Dec. 3, 1991] § 20.1006 Interpretations. Except as specifically authorized by the Commission in writing, no interpretation of the meaning of the regulations in this part by an officer or employee of the Commission other than a written interpretation by the General Counsel will be recognized to be binding upon the Commission. This section shall cease to have effect on January 8, 2027, unless the NRC determines that the cessation deadline should be extended to a date not more than 5 years in the future after offering the public an opportunity to provide input on the costs and benefits of this section and considering that input. The NRC will publish a document in the Federal Register [56 FR 23391, May 21, 1991, as amended at 90 FR 55628, Dec. 3, 2025] § 20.1007 Communications. Unless otherwise specified, communications or reports concerning the regulations in this part should be addressed to the Executive Director for Operations (EDO), and sent either by mail to the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; by hand delivery to the NRC's offices at 11555 Rockville Pike, Rockville, Maryland; or, where practicable, by electronic submission, for example, via Electronic Information Exchange, or CD-ROM. Electronic submissions must be made in a manner that enables the NRC to receive, read, authenticate, distribute, and archive the submission, and process and retrieve it a single page at a time. Detailed guidance on making electronic submissions can be obtained by visiting the NRC's Web site at http://www.nrc.gov/site-help/e-submittals.html; [email protected]; [68 FR 58801, Oct. 10, 2003, as amended at 74 FR 62680, Dec. 1, 2009; 80 FR 74979, Dec. 1, 2015] § 20.1008 Implementation. (a) [Reserved] (b) The applicable section of §§ 20.1001-20.2402 must be used in lieu of requirements in the standards for protection against radiation in effect prior to January 1, 1994 1 1 (c) Any existing license condition or technical specification that is more restrictive than a requirement in §§ 20.1001-20.2402 remains in force until there is a technical specification change, license amendment, or license renewal. (d) If a license condition or technical specification exempted a licensee from a requirement in the standards for protection against radiation in effect prior to January 1, 1994, 1 (e) If a license condition cites provisions in requirements in the standards for protection against radiation in effect prior to January 1, 1994 1 [59 FR 41643, Aug. 15, 1994] § 20.1009 Information collection requirements: OMB approval. (a) The Nuclear Regulatory Commission has submitted the information collection requirements contained in this part to the Office of Management and Budget (OMB) for approval as required by the Paperwork Reduction Act (44 U.S.C. 3501 et seq. (b) The approved information collection requirements contained in this part appear in §§ 20.1003, 20.1101, 20.1202, 20.1203, 20.1204, 20.1206, 20.1208, 20.1301, 20.1302, 20.1403, 20.1404, 20.1406, 20.1501, 20.1601, 20.1703, 20.1901, 20.1904, 20.1905, 20.1906, 20.2002, 20.2004, 20.2005, 20.2006, 20.2102, 20.2103, 20.2104, 20.2105, 20.2106, 20.2107, 20.2108, 20.2110, 20.2201, 20.2202, 20.2203, 20.2204, 20.2205, 20.2206, 20.2207, 20.2301, and appendix G to this part. (c) This part contains information collection requirements in addition to those approved under the control number specified in paragraph (a) of this section. These information collection requirements and the control numbers under which they are approved are as follows: (1) In § 20.2104, NRC Form 4 is approved under control number 3150-0005. (2) In §§ 20.2106 and 20.2206, NRC Form 5 is approved under control number 3150-0006. (3) In § 20.2006 and appendix G to 10 CFR part 20, NRC Form 540 and 540A is approved under control number 3150-0164. (4) In § 20.2006 and appendix G to 10 CFR part 20, NRC Form 541 and 541A is approved under control number 3150-0166. (5) In § 20.2006 and appendix G to 10 CFR part 20, NRC Form 542 and 542A is approved under control number 3150-0165. (6) In § 20.2207, NRC Form 748 is approved under control number 3150-0202. [63 FR 50128, Sept. 21, 1998, as amended at 67 FR 67099, Nov. 4, 2002; 71 FR 65707, Nov. 8, 2006; 72 FR 55922, Oct. 1, 2007; 77 FR 39905, July 6, 2012] Subpart B—Radiation Protection Programs Source: 56 FR 23396, May 21, 1991, unless otherwise noted. § 20.1101 Radiation protection programs. Link to an amendment published at 91 FR 15772, Mar. 30, 2026. (a) Each licensee shall develop, document, and implement a radiation protection program commensurate with the scope and extent of licensed activities and sufficient to ensure compliance with the provisions of this part. (See § 20.2102 for recordkeeping requirements relating to these programs.) (b) The licensee shall use, to the extent practical, procedures and engineering controls based upon sound radiation protection principles to achieve occupational doses and doses to members of the public that are as low as is reasonably achievable (ALARA). (c) The licensee shall periodically (at least annually) review the radiation protection program content and implementation. (d) To implement the ALARA requirements of paragraph (b) of this section, and notwithstanding the requirements in § 20.1301, a constraint on air emissions of radioactive material to the environment, excluding Radon-222 and its daughters, shall be established by licensees other than those subject to § 50.34a or § 53.260 of this chapter, such that the individual member of the public likely to receive the highest dose will not be expected to receive a total effective dose equivalent in excess of 10 mrem (0.1 mSv) per year from these emissions. If a licensee subject to this requirement exceeds this dose constraint, the licensee shall report the exceedance as provided in § 20.2203 and promptly take appropriate corrective action to ensure against recurrence. [56 FR 23396, May 21, 1991, as amended at 61 FR 65127, Dec. 10, 1996; 63 FR 39482, July 23, 1998; 91 FR 15772, Mar. 30, 2026] Subpart C—Occupational Dose Limits Source: 56 FR 23396, May 21, 1991, unless otherwise noted. § 20.1201 Occupational dose limits for adults. (a) The licensee shall control the occupational dose to individual adults, except for planned special exposures under § 20.1206, to the following dose limits. (1) An annual limit, which is the more limiting of— (i) The total effective dose equivalent being equal to 5 rems (0.05 Sv); or (ii) The sum of the deep-dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye being equal to 50 rems (0.5 Sv). (2) The annual limits to the lens of the eye, to the skin of the whole body, and to the skin of the extremities, which are: (i) A lens dose equivalent of 15 rems (0.15 Sv), and (ii) A shallow-dose equivalent of 50 rem (0.5 Sv) to the skin of the whole body or to the skin of any extremity. (b) Doses received in excess of the annual limits, including doses received during accidents, emergencies, and planned special exposures, must be subtracted from the limits for planned special exposures that the individual may receive during the current year (see § 20.1206(e)(1)) and during the individual's lifetime (see § 20.1206(e)(2)). (c) When the external exposure is determined by measurement with an external personal monitoring device, the deep-dose equivalent must be used in place of the effective dose equivalent, unless the effective dose equivalent is determined by a dosimetry method approved by the NRC. The assigned deep-dose equivalent must be for the part of the body receiving the highest exposure. The assigned shallow-dose equivalent must be the dose averaged over the contiguous 10 square centimeters of skin receiving the highest exposure. The deep-dose equivalent, lens-dose equivalent, and shallow-dose equivalent may be assessed from surveys or other radiation measurements for the purpose of demonstrating compliance with the occupational dose limits, if the individual monitoring device was not in the region of highest potential exposure, or the results of individual monitoring are unavailable. (d) Derived air concentration (DAC) and annual limit on intake (ALI) values are presented in table 1 of appendix B to part 20 and may be used to determine the individual's dose (see § 20.2106) and to demonstrate compliance with the occupational dose limits. (e) In addition to the annual dose limits, the licensee shall limit the soluble uranium intake by an individual to 10 milligrams in a week in consideration of chemical toxicity (see footnote 3 of appendix B to part 20). (f) The licensee shall reduce the dose that an individual may be allowed to receive in the current year by the amount of occupational dose received while employed by any other person (see § 20.2104(e)). [56 FR 23396, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995; 63 FR 39482, July 23, 1998; 67 FR 16304, Apr. 5, 2002; 72 FR 68059, Dec. 4, 2007] § 20.1202 Compliance with requirements for summation of external and internal doses. (a) If the licensee is required to monitor under both §§ 20.1502 (a) and (b), the licensee shall demonstrate compliance with the dose limits by summing external and internal doses. If the licensee is required to monitor only under § 20.1502(a) or only under § 20.1502(b), then summation is not required to demonstrate compliance with the dose limits. The licensee may demonstrate compliance with the requirements for summation of external and internal doses by meeting one of the conditions specified in paragraph (b) of this section and the conditions in paragraphs (c) and (d) of this section. (Note: The dose equivalents for the lens of the eye, the skin, and the extremities are not included in the summation, but are subject to separate limits.) (b) Intake by inhalation. (1) The sum of the fractions of the inhalation ALI for each radionuclide, or (2) The total number of derived air concentration-hours (DAC-hours) for all radionuclides divided by 2,000, or (3) The sum of the calculated committed effective dose equivalents to all significantly irradiated 1 1 T T,50 T,50 i.e. T T,50 (c) Intake by oral ingestion. (d) Intake through wounds or absorption through skin. Note: The intake through intact skin has been included in the calculation of DAC for hydrogen-3 and does not need to be further evaluated. [56 FR 23396, May 21, 1991, as amended at 57 FR 57878, Dec. 8, 1992] § 20.1203 Determination of external dose from airborne radioactive material. Licensees shall, when determining the dose from airborne radioactive material, include the contribution to the deep-dose equivalent, lens dose equivalent, and shallow-dose equivalent from external exposure to the radioactive cloud (see appendix B to part 20, footnotes 1 and 2). Note: Airborne radioactivity measurements and DAC values should not be used as the primary means to assess the deep-dose equivalent when the airborne radioactive material includes radionuclides other than noble gases or if the cloud of airborne radioactive material is not relatively uniform. The determination of the deep-dose equivalent to an individual should be based upon measurements using instruments or individual monitoring devices. [56 FR 23396, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995; 63 FR 39482, July 23, 1998] § 20.1204 Determination of internal exposure. (a) For purposes of assessing dose used to determine compliance with occupational dose equivalent limits, the licensee shall, when required under § 20.1502, take suitable and timely measurements of— (1) Concentrations of radioactive materials in air in work areas; or (2) Quantities of radionuclides in the body; or (3) Quantities of radionuclides excreted from the body; or (4) Combinations of these measurements. (b) Unless respiratory protective equipment is used, as provided in § 20.1703, or the assessment of intake is based on bioassays, the licensee shall assume that an individual inhales radioactive material at the airborne concentration in which the individual is present. (c) When specific information on the physical and biochemical properties of the radionuclides taken into the body or the behavior or the material in an individual is known, the licensee may— (1) Use that information to calculate the committed effective dose equivalent, and, if used, the licensee shall document that information in the individual's record; and (2) Upon prior approval of the Commission, adjust the DAC or ALI values to reflect the actual physical and chemical characteristics of airborne radioactive material (e.g., aerosol size distribution or density); and (3) Separately assess the contribution of fractional intakes of Class D, W, or Y compounds of a given radionuclide (see appendix B to part 20) to the committed effective dose equivalent. (d) If the licensee chooses to assess intakes of Class Y material using the measurements given in § 20.1204(a)(2) or (3), the licensee may delay the recording and reporting of the assessments for periods up to 7 months, unless otherwise required by §§ 20.2202 or 20.2203, in order to permit the licensee to make additional measurements basic to the assessments. (e) If the identity and concentration of each radionuclide in a mixture are known, the fraction of the DAC applicable to the mixture for use in calculating DAC-hours must be either— (1) The sum of the ratios of the concentration to the appropriate DAC value (e.g., D, W, Y) from appendix B to part 20 for each radio-nuclide in the mixture; or (2) The ratio of the total concentration for all radionuclides in the mixture to the most restrictive DAC value for any radionuclide in the mixture. (f) If the identity of each radionuclide in a mixture is known, but the concentration of one or more of the radionuclides in the mixture is not known, the DAC for the mixture must be the most restrictive DAC of any radionuclide in the mixture. (g) When a mixture of radionuclides in air exists, licensees may disregard certain radionuclides in the mixture if— (1) The licensee uses the total activity of the mixture in demonstrating compliance with the dose limits in § 20.1201 and in complying with the monitoring requirements in § 20.1502(b), and (2) The concentration of any radionuclide disregarded is less than 10 percent of its DAC, and (3) The sum of these percentages for all of the radionuclides disregarded in the mixture does not exceed 30 percent. (h)(1) In order to calculate the committed effective dose equivalent, the licensee may assume that the inhalation of one ALI, or an exposure of 2,000 DAC-hours, results in a committed effective dose equivalent of 5 rems (0.05 Sv) for radionuclides that have their ALIs or DACs based on the committed effective dose equivalent. (2) When the ALI (and the associated DAC) is determined by the nonstochastic organ dose limit of 50 rems (0.5 Sv), the intake of radionuclides that would result in a committed effective dose equivalent of 5 rems (0.05 Sv) (the stochastic ALI) is listed in parentheses in table 1 of appendix B to part 20. In this case, the licensee may, as a simplifying assumption, use the stochastic ALIs to determine committed effective dose equivalent. However, if the licensee uses the stochastic ALIs, the licensee must also demonstrate that the limit in § 20.1201(a)(1)(ii) is met. [56 FR 23396, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995] § 20.1205 [Reserved] § 20.1206 Planned special exposures. A licensee may authorize an adult worker to receive doses in addition to and accounted for separately from the doses received under the limits specified in § 20.1201 provided that each of the following conditions is satisfied— (a) The licensee authorizes a planned special exposure only in an exceptional situation when alternatives that might avoid the dose estimated to result from the planned special exposure are unavailable or impractical. (b) The licensee (and employer if the employer is not the licensee) specifically authorizes the planned special exposure, in writing, before the exposure occurs. (c) Before a planned special exposure, the licensee ensures that the individuals involved are— (1) Informed of the purpose of the planned operation; (2) Informed of the estimated doses and associated potential risks and specific radiation levels or other conditions that might be involved in performing the task; and (3) Instructed in the measures to be taken to keep the dose ALARA considering other risks that may be present. (d) Prior to permitting an individual to participate in a planned special exposure, the licensee ascertains prior doses as required by § 20.2104(b) during the lifetime of the individual for each individual involved. (e) Subject to § 20.1201(b), the licensee does not authorize a planned special exposure that would cause an individual to receive a dose from all planned special exposures and all doses in excess of the limits to exceed— (1) The numerical values of any of the dose limits in § 20.1201(a) in any year; and (2) Five times the annual dose limits in § 20.1201(a) during the individual's lifetime. (f) The licensee maintains records of the conduct of a planned special exposure in accordance with § 20.2105 and submits a written report in accordance with § 20.2204. (g) The licensee records the best estimate of the dose resulting from the planned special exposure in the individual's record and informs the individual, in writing, of the dose within 30 days from the date of the planned special exposure. The dose from planned special exposures is not to be considered in controlling future occupational dose of the individual under § 20.1201(a) but is to be included in evaluations required by § 20.1206 (d) and (e). [56 FR 23396, May 21, 1991, as amended at 63 FR 39482, July 23, 1998] § 20.1207 Occupational dose limits for minors. The annual occupational dose limits for minors are 10 percent of the annual dose limits specified for adult workers in § 20.1201. § 20.1208 Dose equivalent to an embryo/fetus. (a) The licensee shall ensure that the dose equivalent to the embryo/fetus during the entire pregnancy, due to the occupational exposure of a declared pregnant woman, does not exceed 0.5 rem (5 mSv). (For recordkeeping requirements, see § 20.2106.) (b) The licensee shall make efforts to avoid substantial variation above a uniform monthly exposure rate to a declared pregnant woman so as to satisfy the limit in paragraph (a) of this section. (c) The dose equivalent to the embryo/fetus is the sum of— (1) The deep-dose equivalent to the declared pregnant woman; and (2) The dose equivalent to the embryo/fetus resulting from radionuclides in the embryo/fetus and radionuclides in the declared pregnant woman. (d) If the dose equivalent to the embryo/fetus is found to have exceeded 0.5 rem (5 mSv), or is within 0.05 rem (0.5 mSv) of this dose, by the time the woman declares the pregnancy to the licensee, the licensee shall be deemed to be in compliance with paragraph (a) of this section if the additional dose equivalent to the embryo/fetus does not exceed 0.05 rem (0.5 mSv) during the remainder of the pregnancy. [56 FR 23396, May 21, 1991, as amended at 63 FR 39482, July 23, 1998] Subpart D—Radiation Dose Limits for Individual Members of the Public Source: 56 FR 23398, May 21, 1991, unless otherwise noted. § 20.1301 Dose limits for individual members of the public. (a) Each licensee shall conduct operations so that— (1) The total effective dose equivalent to individual members of the public from the licensed operation does not exceed 0.1 rem (1 mSv) in a year, exclusive of the dose contributions from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under § 35.75, from voluntary participation in medical research programs, and from the licensee's disposal of radioactive material into sanitary sewerage in accordance with § 20.2003, and (2) The dose in any unrestricted area from external sources, exclusive of the dose contributions from patients administered radioactive material and released in accordance with § 35.75, does not exceed 0.002 rem (0.02 millisievert) in any one hour. (b) If the licensee permits members of the public to have access to controlled areas, the limits for members of the public continue to apply to those individuals. (c) Notwithstanding paragraph (a)(1) of this section, a licensee may permit visitors to an individual who cannot be released, under § 35.75, to receive a radiation dose greater than 0.1 rem (1 mSv) if— (1) The radiation dose received does not exceed 0.5 rem (5 mSv); and (2) The authorized user, as defined in 10 CFR Part 35, has determined before the visit that it is appropriate. (d) A licensee or license applicant may apply for prior NRC authorization to operate up to an annual dose limit for an individual member of the public of 0.5 rem (5 mSv). The licensee or license applicant shall include the following information in this application: (1) Demonstration of the need for and the expected duration of operations in excess of the limit in paragraph (a) of this section; (2) The licensee's program to assess and control dose within the 0.5 rem (5 mSv) annual limit; and (3) The procedures to be followed to maintain the dose as low as is reasonably achievable. (e) In addition to the requirements of this part, a licensee subject to the provisions of EPA's generally applicable environmental radiation standards in 40 CFR part 190 shall comply with those standards. (f) The Commission may impose additional restrictions on radiation levels in unrestricted areas and on the total quantity of radionuclides that a licensee may release in effluents in order to restrict the collective dose. [56 FR 23398, May 21, 1991, as amended at 60 FR 48625, Sept. 20, 1995; 62 FR 4133, Jan. 29, 1997; 67 FR 20370, Apr. 24, 2002; 67 FR 62872, Oct. 9, 2002] § 20.1302 Compliance with dose limits for individual members of the public. (a) The licensee shall make or cause to be made, as appropriate, surveys of radiation levels in unrestricted and controlled areas and radioactive materials in effluents released to unrestricted and controlled areas to demonstrate compliance with the dose limits for individual members of the public in § 20.1301. (b) A licensee shall show compliance with the annual dose limit in § 20.1301 by— (1) Demonstrating by measurement or calculation that the total effective dose equivalent to the individual likely to receive the highest dose from the licensed operation does not exceed the annual dose limit; or (2) Demonstrating that— (i) The annual average concentrations of radioactive material released in gaseous and liquid effluents at the boundary of the unrestricted area do not exceed the values specified in table 2 of appendix B to part 20; and (ii) If an individual were continuously present in an unrestricted area, the dose from external sources would not exceed 0.002 rem (0.02 mSv) in an hour and 0.05 rem (0.5 mSv) in a year. (c) Upon approval from the Commission, the licensee may adjust the effluent concentration values in appendix B to part 20, table 2, for members of the public, to take into account the actual physical and chemical characteristics of the effluents (e.g., aerosol size distribution, solubility, density, radioactive decay equilibrium, chemical form). [56 FR 23398, May 21, 1991; 56 FR 61352, Dec. 3, 1991, as amended at 57 FR 57878, Dec. 8, 1992; 60 FR 20185, Apr. 25, 1995] Subpart E—Radiological Criteria for License Termination Source: 62 FR 39088, July 21, 1997, unless otherwise noted. § 20.1401 General provisions and scope. (a) The criteria in this subpart apply to the decommissioning of facilities licensed under parts 30, 40, 50, 52, 53, 60, 61, 63, 70, and 72 of this chapter, and release of part of a facility or site for unrestricted use in accordance with § 50.83 or § 53.1080 of this chapter, as well as other facilities subject to the Commission's jurisdiction under the Atomic Energy Act of 1954, as amended, and the Energy Reorganization Act of 1974, as amended. For high-level and low-level waste disposal facilities (10 CFR parts 60, 61, and 63), the criteria apply only to ancillary surface facilities that support radioactive waste disposal activities. The criteria do not apply to uranium and thorium recovery facilities already subject to appendix A to 10 CFR part 40 or the uranium solution extraction facilities. (b) The criteria in this subpart do not apply to sites which: (1) Have been decommissioned prior to the effective date of the rule in accordance with criteria identified in the Site Decommissioning Management Plan (SDMP) Action Plan of April 16, 1992 (57 FR 13389); (2) Have previously submitted and received Commission approval on a license termination plan (LTP) or decommissioning plan that is compatible with the SDMP Action Plan criteria; or (3) Submit a sufficient LTP or decommissioning plan before August 20, 1998 and such LTP or decommissioning plan is approved by the Commission before August 20, 1999 and in accordance with the criteria identified in the SDMP Action Plan, except that if an EIS is required in the submittal, there will be a provision for day-for-day extension. (c) After a site has been decommissioned and the license terminated in accordance with the criteria in this subpart, or after part of a facility or site has been released for unrestricted use in accordance with § 50.83 or § 53.1080 of this chapter and in accordance with the criteria in this subpart, the Commission will require additional cleanup only, if based on new information, it determines that the criteria of this subpart were not met and residual radioactivity remaining at the site could result in significant threat to public health and safety. (d) When calculating TEDE to the average member of the critical group the licensee shall determine the peak annual TEDE dose expected within the first 1000 years after decommissioning. [62 FR 39088, July 21, 1997, as amended at 66 FR 55789, Nov. 2, 2001; 68 FR 19726, Apr. 22, 2003; 72 FR 49485, Aug. 28, 2007; 91 FR 15772, Mar. 30, 2026; 91 FR 18772, Apr. 13, 2026] § 20.1402 Radiological criteria for unrestricted use. A site will be considered acceptable for unrestricted use if the residual radioactivity that is distinguishable from background radiation results in a TEDE to an average member of the critical group that does not exceed 25 mrem (0.25 mSv) per year, including that from groundwater sources of drinking water, and that the residual radioactivity has been reduced to levels that are as low as reasonably achievable (ALARA). Determination of the levels which are ALARA must take into account consideration of any detriments, such as deaths from transportation accidents, expected to potentially result from decontamination and waste disposal. § 20.1403 Criteria for license termination under restricted conditions. A site will be considered acceptable for license termination under restricted conditions if: (a) The licensee can demonstrate that further reductions in residual radioactivity necessary to comply with the provisions of § 20.1402 would result in net public or environmental harm or were not being made because the residual levels associated with restricted conditions are ALARA. Determination of the levels which are ALARA must take into account consideration of any detriments, such as traffic accidents, expected to potentially result from decontamination and waste disposal; (b) The licensee has made provisions for legally enforceable institutional controls that provide reasonable assurance that the TEDE from residual radioactivity distinguishable from background to the average member of the critical group will not exceed 25 mrem (0.25 mSv) per year; (c) The licensee has provided sufficient financial assurance to enable an independent third party, including a governmental custodian of a site, to assume and carry out responsibilities for any necessary control and maintenance of the site. Acceptable financial assurance mechanisms are— (1) Funds placed into a trust segregated from the licensee's assets and outside the licensee's administrative control, and in which the adequacy of the trust funds is to be assessed based on an assumed annual 1 percent real rate of return on investment; (2) A statement of intent in the case of Federal, State, or local Government licensees, as described in § 30.35(f)(4) of this chapter; or (3) When a government entity is assuming custody and ownership of a site, an arrangement that is deemed acceptable by such governmental entity. (d) The licensee has submitted a decommissioning plan or License Termination Plan (LTP) to the Commission indicating the licensee's intent to decommission in accordance with § 30.36(d), § 40.42(d), § 50.82 (a) and (b), subpart G of part 53, § 70.38(d), or § 72.54 of this chapter, and specifying that the licensee intends to decommission by restricting use of the site. The licensee shall document in the LTP or decommissioning plan how the advice of individuals and institutions in the community who may be affected by the decommissioning has been sought and incorporated, as appropriate, following analysis of that advice. (1) Licensees proposing to decommission by restricting use of the site shall seek advice from such affected parties regarding the following matters concerning the proposed decommissioning— (i) Whether provisions for institutional controls proposed by the licensee: (A) Will provide reasonable assurance that the TEDE from residual radioactivity distinguishable from background to the average member of the critical group will not exceed 25 mrem (0.25 mSv) TEDE per year; (B) Will be enforceable; and (C) Will not impose undue burdens on the local community or other affected parties. (ii) Whether the licensee has provided sufficient financial assurance to enable an independent third party, including a governmental custodian of a site, to assume and carry out responsibilities for any necessary control and maintenance of the site; (2) In seeking advice on the issues identified in § 20.1403(d)(1), the licensee shall provide for: (i) Participation by representatives of a broad cross section of community interests who may be affected by the decommissioning; (ii) An opportunity for a comprehensive, collective discussion on the issues by the participants represented; and (iii) A publicly available summary of the results of all such discussions, including a description of the individual viewpoints of the participants on the issues and the extent of agreement or disagreement among the participants on the issues; and (e) Residual radioactivity at the site has been reduced so that if the institutional controls were no longer in effect, there is reasonable assurance that the TEDE from residual radioactivity distinguishable from background to the average member of the critical group is as low as reasonably achievable and would not exceed either— (1) 100 mrem (1 mSv) per year; or (2) 500 mrem (5 mSv) per year provided that the licensee— (i) Demonstrates that further reductions in residual radioactivity necessary to comply with the 100 mrem/y (1 mSv/y) value of paragraph (e)(1) of this section are not technically achievable, would be prohibitively expensive, or would result in net public or environmental harm; (ii) Makes provisions for durable institutional controls; (iii) Provides sufficient financial assurance to enable a responsible government entity or independent third party, including a governmental custodian of a site, both to carry out periodic rechecks of the site no less frequently than every 5 years to assure that the institutional controls remain in place as necessary to meet the criteria of § 20.1403(b) and to assume and carry out responsibilities for any necessary control and maintenance of those controls. Acceptable financial assurance mechanisms are those in paragraph (c) of this section. [62 FR 39088, July 21, 1997, as amended at 76 FR 35564, July 17, 2011; 91 FR 15772, Mar. 30, 2026] § 20.1404 Alternate criteria for license termination. (a) The Commission may terminate a license using alternate criteria greater than the dose criterion of §§ 20.1402, 20.1403(b), and 20.1403(d)(1)(i)(A), if the licensee— (1) Provides assurance that public health and safety would continue to be protected, and that it is unlikely that the dose from all man-made sources combined, other than medical, would be more than the 1 mSv/y (100 mrem/y) limit of subpart D, by submitting an analysis of possible sources of exposure; (2) Has employed to the extent practical restrictions on site use according to the provisions of § 20.1403 in minimizing exposures at the site; and (3) Reduces doses to ALARA levels, taking into consideration any detriments such as traffic accidents expected to potentially result from decontamination and waste disposal. (4) Has submitted a decommissioning plan or License Termination Plan (LTP) to the Commission indicating the licensee's intent to decommission in accordance with § 30.36(d), § 40.42(d), § 50.82 (a) and (b), subpart G of part 53, § 70.38(d), or § 72.54 of this chapter, and specifying that the licensee proposes to decommission by use of alternate criteria. The licensee shall document in the decommissioning plan or LTP how the advice of individuals and institutions in the community who may be affected by the decommissioning has been sought and addressed, as appropriate, following analysis of that advice. In seeking such advice, the licensee shall provide for: (i) Participation by representatives of a broad cross section of community interests who may be affected by the decommissioning; (ii) An opportunity for a comprehensive, collective discussion on the issues by the participants represented; and (iii) A publicly available summary of the results of all such discussions, including a description of the individual viewpoints of the participants on the issues and the extent of agreement and disagreement on the issues. (5) Has provided sufficient financial assurance in the form of a trust fund to enable an independent third party, including a governmental custodian of a site, to assume and carry out responsibilities for any necessary control and maintenance of the site. (b) The use of alternate criteria to terminate a license requires the approval of the Commission after consideration of the NRC staff's recommendations that will address any comments provided by the Environmental Protection Agency and any public comments submitted pursuant to § 20.1405. [62 FR 39088, July 21, 1997, as amended at 76 FR 35564, July 17, 2011; 91 FR 15772, Mar. 30, 2026] § 20.1405 Public notification and public participation. Upon the receipt of an LTP or decommissioning plan from the licensee, or a proposal by the licensee for release of a site pursuant to §§ 20.1403 or 20.1404, or whenever the Commission deems such notice to be in the public interest, the Commission shall: (a) Notify and solicit comments from: (1) Local and State governments in the vicinity of the site and any Indian Nation or other indigenous people that have treaty or statutory rights that could be affected by the decommissioning; and (2) The Environmental Protection Agency for cases where the licensee proposes to release a site pursuant to § 20.1404. (b) Publish a notice in the Federal Register § 20.1406 Minimization of contamination. (a) Applicants for licenses, other than early site permits and manufacturing licenses under part 52 or 53 of this chapter and renewals, whose applications are submitted after August 20, 1997, shall describe in the application how facility design and procedures for operation will minimize, to the extent practicable, contamination of the facility and the environment, facilitate eventual decommissioning, and minimize, to the extent practicable, the generation of radioactive waste. (b) Applicants for standard design certifications, standard design approvals, and manufacturing licenses under part 52 or 53 of this chapter, whose applications are submitted after August 20, 1997, shall describe in the application how facility design will minimize, to the extent practicable, contamination of the facility and the environment, facilitate eventual decommissioning, and minimize, to the extent practicable, the generation of radioactive waste. (c) Licensees shall, to the extent practical, conduct operations to minimize the introduction of residual radioactivity into the site, including the subsurface, in accordance with the existing radiation protection requirements in subpart B and radiological criteria for license termination in subpart E of this part. [72 FR 49485, Aug. 28, 2007, as amended at 76 FR 35564, June 17, 2011; 91 FR 15772, Mar. 30, 2026] Subpart F—Surveys and Monitoring Source: 56 FR 23398, May 21, 1991, unless otherwise noted. § 20.1501 General. (a) Each licensee shall make or cause to be made, surveys of areas, including the subsurface, that— (1) May be necessary for the licensee to comply with the regulations in this part; and (2) Are reasonable under the circumstances to evaluate— (i) The magnitude and extent of radiation levels; and (ii) Concentrations or quantities of residual radioactivity; and (iii) The potential radiological hazards of the radiation levels and residual radioactivity detected. (b) Notwithstanding § 20.2103(a), records from surveys describing the location and amount of subsurface residual radioactivity identified at the site must be kept with records important for decommissioning, and such records must be retained in accordance with § 30.35(g), § 40.36(f), § 50.75(g), subpart G of part 53, § 70.25(g), or § 72.30(d) of this chapter, as applicable. (c) The licensee shall ensure that instruments and equipment used for quantitative radiation measurements (e.g., dose rate and effluent monitoring) are calibrated periodically for the radiation measured. (d) All personnel dosimeters (except for direct and indirect reading pocket ionization chambers and those dosimeters used to measure the dose to the extremities) that require processing to determine the radiation dose and that are used by licensees to comply with § 20.1201, with other applicable provisions of this chapter, or with conditions specified in a license must be processed and evaluated by a dosimetry processor— (1) Holding current personnel dosimetry accreditation from the National Voluntary Laboratory Accreditation Program (NVLAP) of the National Institute of Standards and Technology; and (2) Approved in this accreditation process for the type of radiation or radiations included in the NVLAP program that most closely approximates the type of radiation or radiations for which the individual wearing the dosimeter is monitored. [56 FR 23398, May 21, 1991, as amended at 63 FR 39482, July 23, 1998; 76 FR 35564, June 17, 2011; 91 FR 15772, Mar. 30, 2026] § 20.1502 Conditions requiring individual monitoring of external and internal occupational dose. Each licensee shall monitor exposures to radiation and radioactive material at levels sufficient to demonstrate compliance with the occupational dose limits of this part. As a minimum— (a) Each licensee shall monitor occupational exposure to radiation from licensed and unlicensed radiation sources under the control of the licensee and shall supply and require the use of individual monitoring devices by— (1) Adults likely to receive, in 1 year from sources external to the body, a dose in excess of 10 percent of the limits in § 20.1201(a), (2) Minors likely to receive, in 1 year, from radiation sources external to the body, a deep dose equivalent in excess of 0.1 rem (1 mSv), a lens dose equivalent in excess of 0.15 rem (1.5 mSv), or a shallow dose equivalent to the skin or to the extremities in excess of 0.5 rem (5 mSv); (3) Declared pregnant women likely to receive during the entire pregnancy, from radiation sources external to the body, a deep dose equivalent in excess of 0.1 rem (1 mSv); 2 2 (4) Individuals entering a high or very high radiation area. (b) Each licensee shall monitor (see § 20.1204) the occupational intake of radioactive material by and assess the committed effective dose equivalent to— (1) Adults likely to receive, in 1 year, an intake in excess of 10 percent of the applicable ALI(s) in table 1, columns 1 and 2, of appendix B to §§ 20.1001-20.2402; (2) Minors likely to receive, in 1 year, a committed effective dose equivalent in excess of 0.1 rem (1 mSv); and (3) Declared pregnant women likely to receive, during the entire pregnancy, a committed effective dose equivalent in excess of 0.1 rem (1 mSv). [56 FR 23398, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995; 63 FR 39482, July 23, 1998] Subpart G—Control of Exposure From External Sources in Restricted Areas Source: 56 FR 23398, May 21, 1991, unless otherwise noted. § 20.1601 Control of access to high radiation areas. (a) The licensee shall ensure that each entrance or access point to a high radiation area has one or more of the following features— (1) A control device that, upon entry into the area, causes the level of radiation to be reduced below that level at which an individual might receive a deep-dose equivalent of 0.1 rem (1 mSv) in 1 hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates; (2) A control device that energizes a conspicuous visible or audible alarm signal so that the individual entering the high radiation area and the supervisor of the activity are made aware of the entry; or (3) Entryways that are locked, except during periods when access to the areas is required, with positive control over each individual entry. (b) In place of the controls required by paragraph (a) of this section for a high radiation area, the licensee may substitute continuous direct or electronic surveillance that is capable of preventing unauthorized entry. (c) A licensee may apply to the Commission for approval of alternative methods for controlling access to high radiation areas. (d) The licensee shall establish the controls required by paragraphs (a) and (c) of this section in a way that does not prevent individuals from leaving a high radiation area. (e) Control is not required for each entrance or access point to a room or other area that is a high radiation area solely because of the presence of radioactive materials prepared for transport and packaged and labeled in accordance with the regulations of the Department of Transportation provided that— (1) The packages do not remain in the area longer than 3 days; and (2) The dose rate at 1 meter from the external surface of any package does not exceed 0.01 rem (0.1 mSv) per hour. (f) Control of entrance or access to rooms or other areas in hospitals is not required solely because of the presence of patients containing radioactive material, provided that there are personnel in attendance who will take the necessary precautions to prevent the exposure of individuals to radiation or radioactive material in excess of the limits established in this part and to operate within the ALARA provisions of the licensee's radiation protection program. § 20.1602 Control of access to very high radiation areas. In addition to the requirements in § 20.1601, the licensee shall institute additional measures to ensure that an individual is not able to gain unauthorized or inadvertent access to areas in which radiation levels could be encountered at 500 rads (5 grays) or more in 1 hour at 1 meter from a radiation source or any surface through which the radiation penetrates. Subpart H—Respiratory Protection and Controls To Restrict Internal Exposure in Restricted Areas Source: 56 FR 23400, May 21, 1991, unless otherwise noted. § 20.1701 Use of process or other engineering controls. The licensee shall use, to the extent practical, process or other engineering controls (e.g., containment, decontamination, or ventilation) to control the concentration of radioactive material in air. [64 FR 54556, Oct. 7, 1999] § 20.1702 Use of other controls. (a) When it is not practical to apply process or other engineering controls to control the concentrations of radioactive material in the air to values below those that define an airborne radioactivity area, the licensee shall, consistent with maintaining the total effective dose equivalent ALARA, increase monitoring and limit intakes by one or more of the following means— (1) Control of access; (2) Limitation of exposure times; (3) Use of respiratory protection equipment; or (4) Other controls. (b) If the licensee performs an ALARA analysis to determine whether or not respirators should be used, the licensee may consider safety factors other than radiological factors. The licensee should also consider the impact of respirator use on workers' industrial health and safety. [64 FR 54556, Oct. 7, 1999] § 20.1703 Use of individual respiratory protection equipment. If the licensee assigns or permits the use of respiratory protection equipment to limit the intake of radioactive material, (a) The licensee shall use only respiratory protection equipment that is tested and certified by the National Institute for Occupational Safety and Health (NIOSH) except as otherwise noted in this part. (b) If the licensee wishes to use equipment that has not been tested or certified by NIOSH, or for which there is no schedule for testing or certification, the licensee shall submit an application to the NRC for authorized use of this equipment except as provided in this part. The application must include evidence that the material and performance characteristics of the equipment are capable of providing the proposed degree of protection under anticipated conditions of use. This must be demonstrated either by licensee testing or on the basis of reliable test information. (c) The licensee shall implement and maintain a respiratory protection program that includes: (1) Air sampling sufficient to identify the potential hazard, permit proper equipment selection, and estimate doses; (2) Surveys and bioassays, as necessary, to evaluate actual intakes; (3) Testing of respirators for operability (user seal check for face sealing devices and functional check for others) immediately prior to each use; (4) Written procedures regarding— (i) Monitoring, including air sampling and bioassays; (ii) Supervision and training of respirator users; (iii) Fit testing; (iv) Respirator selection; (v) Breathing air quality; (vi) Inventory and control; (vii) Storage, issuance, maintenance, repair, testing, and quality assurance of respiratory protection equipment; (viii) Recordkeeping; and (ix) Limitations on periods of respirator use and relief from respirator use; (5) Determination by a physician that the individual user is medically fit to use respiratory protection equipment: (i) Before the initial fitting of a face sealing respirator; (ii) Before the first field use of non-face sealing respirators, and (iii) Either every 12 months thereafter, or periodically at a frequency determined by a physician. (6) Fit testing, with fit factor ≥10 times the APF for negative pressure devices, and a fit factor ≥500 for any positive pressure, continuous flow, and pressure-demand devices, before the first field use of tight fitting, face-sealing respirators and periodically thereafter at a frequency not to exceed 1 year. Fit testing must be performed with the facepiece operating in the negative pressure mode. (d) The licensee shall advise each respirator user that the user may leave the area at any time for relief from respirator use in the event of equipment malfunction, physical or psychological distress, procedural or communication failure, significant deterioration of operating conditions, or any other conditions that might require such relief. (e) The licensee shall also consider limitations appropriate to the type and mode of use. When selecting respiratory devices the licensee shall provide for vision correction, adequate communication, low temperature work environments, and the concurrent use of other safety or radiological protection equipment. The licensee shall use equipment in such a way as not to interfere with the proper operation of the respirator. (f) Standby rescue persons are required whenever one-piece atmosphere-supplying suits, or any combination of supplied air respiratory protection device and personnel protective equipment are used from which an unaided individual would have difficulty extricating himself or herself. The standby persons must be equipped with respiratory protection devices or other apparatus appropriate for the potential hazards. The standby rescue persons shall observe or otherwise maintain continuous communication with the workers (visual, voice, signal line, telephone, radio, or other suitable means), and be immediately available to assist them in case of a failure of the air supply or for any other reason that requires relief from distress. A sufficient number of standby rescue persons must be immediately available to assist all users of this type of equipment and to provide effective emergency rescue if needed. (g) Atmosphere-supplying respirators must be supplied with respirable air of grade D quality or better as defined by the Compressed Gas Association in publication G-7.1, “Commodity Specification for Air,” 1997 and included in the regulations of the Occupational Safety and Health Administration (29 CFR 1910.134(i)(1)(ii)(A) through (E)). Grade D quality air criteria include— (1) Oxygen content (v/v) of 19.5-23.5%; (2) Hydrocarbon (condensed) content of 5 milligrams per cubic meter of air or less; (3) Carbon monoxide (CO) content of 10 ppm or less; (4) Carbon dioxide content of 1,000 ppm or less; and (5) Lack of noticeable odor. (h) The licensee shall ensure that no objects, materials or substances, such as facial hair, or any conditions that interfere with the face—facepiece seal or valve function, and that are under the control of the respirator wearer, are present between the skin of the wearer's face and the sealing surface of a tight-fitting respirator facepiece. (i) In estimating the dose to individuals from intake of airborne radioactive materials, the concentration of radioactive material in the air that is inhaled when respirators are worn is initially assumed to be the ambient concentration in air without respiratory protection, divided by the assigned protection factor. If the dose is later found to be greater than the estimated dose, the corrected value must be used. If the dose is later found to be less than the estimated dose, the corrected value may be used. [64 FR 54557, Oct. 7, 1999, as amended at 67 FR 77652, Dec. 19, 2002] § 20.1704 Further restrictions on the use of respiratory protection equipment. The Commission may impose restrictions in addition to the provisions of §§ 20.1702, 20.1703, and Appendix A to Part 20, in order to: (a) Ensure that the respiratory protection program of the licensee is adequate to limit doses to individuals from intakes of airborne radioactive materials consistent with maintaining total effective dose equivalent ALARA; and (b) Limit the extent to which a licensee may use respiratory protection equipment instead of process or other engineering controls. [64 FR 54557, Oct. 7, 1999] § 20.1705 Application for use of higher assigned protection factors. The licensee shall obtain authorization from the Commission before using assigned protection factors in excess of those specified in Appendix A to part 20. The Commission may authorize a licensee to use higher assigned protection factors on receipt of an application that— (a) Describes the situation for which a need exists for higher protection factors; and (b) Demonstrates that the respiratory protection equipment provides these higher protection factors under the proposed conditions of use. [64 FR 54557, Oct. 7, 1999] Subpart I—Storage and Control of Licensed Material Source: 56 FR 23401, May 21, 1991, unless otherwise noted. § 20.1801 Security of stored material. The licensee shall secure from unauthorized removal or access licensed materials that are stored in controlled or unrestricted areas. § 20.1802 Control of material not in storage. The licensee shall control and maintain constant surveillance of licensed material that is in a controlled or unrestricted area and that is not in storage. Subpart J—Precautionary Procedures Source: 56 FR 23401, May 21, 1991, unless otherwise noted. § 20.1901 Caution signs. (a) Standard radiation symbol. (1) Cross-hatched area is to be magenta, or purple, or black, and (2) The background is to be yellow. (b) Exception to color requirements for standard radiation symbol. (c) Additional information on signs and labels. § 20.1902 Posting requirements. (a) Posting of radiation areas. (b) Posting of high radiation areas. (c) Posting of very high radiation areas. (d) Posting of airborne radioactivity areas. (e) Posting of areas or rooms in which licensed material is used or stored. [56 FR 23401, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995] § 20.1903 Exceptions to posting requirements. (a) A licensee is not required to post caution signs in areas or rooms containing radioactive materials for periods of less than 8 hours, if each of the following conditions is met: (1) The materials are constantly attended during these periods by an individual who takes the precautions necessary to prevent the exposure of individuals to radiation or radioactive materials in excess of the limits established in this part; and (2) The area or room is subject to the licensee's control. (b) Rooms or other areas in hospitals that are occupied by patients are not required to be posted with caution signs pursuant to § 20.1902 provided that the patient could be released from licensee control pursuant to § 35.75 of this chapter. (c) A room or area is not required to be posted with a caution sign because of the presence of a sealed source provided the radiation level at 30 centimeters from the surface of the source container or housing does not exceed 0.005 rem (0.05 mSv) per hour. (d) Rooms in hospitals or clinics that are used for teletherapy are exempt from the requirement to post caution signs under § 20.1902 if— (1) Access to the room is controlled pursuant to 10 CFR 35.615; and (2) Personnel in attendance take necessary precautions to prevent the inadvertent exposure of workers, other patients, and members of the public to radiation in excess of the limits established in this part. [56 FR 23401, May 21, 1991, as amended at 57 FR 39357, Aug. 31, 1992; 62 FR 4133, Jan. 29, 1997; 63 FR 39482, July 23, 1998] § 20.1904 Labeling containers. (a) The licensee shall ensure that each container of licensed material bears a durable, clearly visible label bearing the radiation symbol and the words “CAUTION, RADIOACTIVE MATERIAL” or “DANGER, RADIOACTIVE MATERIAL.” The label must also provide sufficient information (such as the radionuclide(s) present, an estimate of the quantity of radioactivity, the date for which the activity is estimated, radiation levels, kinds of materials, and mass enrichment) to permit individuals handling or using the containers, or working in the vicinity of the containers, to take precautions to avoid or minimize exposures. (b) Each licensee shall, prior to removal or disposal of empty uncontaminated containers to unrestricted areas, remove or deface the radioactive material label or otherwise clearly indicate that the container no longer contains radioactive materials. § 20.1905 Exemptions to labeling requirements. A licensee is not required to label— (a) Containers holding licensed material in quantities less than the quantities listed in appendix C to part 20; or (b) Containers holding licensed material in concentrations less than those specified in table 3 of appendix B to part 20; or (c) Containers attended by an individual who takes the precautions necessary to prevent the exposure of individuals in excess of the limits established by this part; or (d) Containers when they are in transport and packaged and labeled in accordance with the regulations of the Department of Transportation, 3 3 (e) Containers that are accessible only to individuals authorized to handle or use them, or to work in the vicinity of the containers, if the contents are identified to these individuals by a readily available written record (examples of containers of this type are containers in locations such as water-filled canals, storage vaults, or hot cells). The record must be retained as long as the containers are in use for the purpose indicated on the record; or (f) Installed manufacturing or process equipment, such as reactor components, piping, and tanks; or (g) Containers holding licensed material (other than sealed sources that are either specifically or generally licensed) at a facility licensed under part 50, 52, or 53 of this chapter, not including non-power production or utilization facilities, that are within an area posted under the requirements in § 20.1902 if the containers are: (1) Conspicuously marked (such as by providing a system of color coding of containers) commensurate with the radiological hazard; (2) Accessible only to individuals who have sufficient instruction to minimize radiation exposure while handling or working in the vicinity of the containers; and (3) Subject to plant procedures to ensure they are appropriately labeled, as specified at § 20.1904 before being removed from the posted area. [56 FR 23401, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995; 72 FR 68059, Dec. 4, 2007; 89 FR 106250, Dec. 30, 2024; 91 FR 15772, Mar. 30, 2026] § 20.1906 Procedures for receiving and opening packages. (a) Each licensee who expects to receive a package containing quantities of radioactive material in excess of a Type A quantity, as defined in § 71.4 and appendix A to part 71 of this chapter, shall make arrangements to receive— (1) The package when the carrier offers it for delivery; or (2) Notification of the arrival of the package at the carrier's terminal and to take possession of the package expeditiously. (b) Each licensee shall— (1) Monitor the external surfaces of a labeled 3a 3a (2) Monitor the external surfaces of a labeled 3a (3) Monitor all packages known to contain radioactive material for radioactive contamination and radiation levels if there is evidence of degradation of package integrity, such as packages that are crushed, wet, or damaged. (c) The licensee shall perform the monitoring required by paragraph (b) of this section as soon as practical after receipt of the package, but not later than 3 hours after the package is received at the licensee's facility if it is received during the licensee's normal working hours, or not later than 3 hours from the beginning of the next working day if it is received after working hours. (d) The licensee shall immediately notify the final delivery carrier and the NRC Headquarters Operations Center by telephone at the numbers specified in appendix A to part 73 of this chapter, when— (1) Removable radioactive surface contamination exceeds the limits of § 71.87(i) of this chapter; or (2) External radiation levels exceed the limits of § 71.47 of this chapter. (e) Each licensee shall— (1) Establish, maintain, and retain written procedures for safely opening packages in which radioactive material is received; and (2) Ensure that the procedures are followed and that due consideration is given to special instructions for the type of package being opened. (f) Licensees transferring special form sources in licensee-owned or licensee-operated vehicles to and from a work site are exempt from the contamination monitoring requirements of paragraph (b) of this section, but are not exempt from the survey requirement in paragraph (b) of this section for measuring radiation levels that is required to ensure that the source is still properly lodged in its shield. [56 FR 23401, May 21, 1991, as amended at 57 FR 39357, Aug. 31, 1992; 60 FR 20185, Apr. 25, 1995; 63 FR 39482, July 23, 1998; 85 FR 65661, Oct. 16, 2020; 85 FR 68243, Oct. 28, 2020] Subpart K—Waste Disposal Source: 56 FR 23403, May 21, 1991, unless otherwise noted. § 20.2001 General requirements. (a) A licensee shall dispose of licensed material only— (1) By transfer to an authorized recipient as provided in § 20.2006 or in the regulations in parts 30, 40, 60, 61, 63, 70, and 72 of this chapter; (2) By decay in storage; or (3) By release in effluents within the limits in § 20.1301; or (4) As authorized under §§ 20.2002, 20.2003, 20.2004, 20.2005, or 20.2008. (b) A person must be specifically licensed to receive waste containing licensed material from other persons for: (1) Treatment prior to disposal; or (2) Treatment or disposal by incineration; or (3) Decay in storage; or (4) Disposal at a land disposal facility licensed under part 61 of this chapter; or (5) Disposal at a geologic repository under part 60 or part 63 of this chapter. [56 FR 23403, May 21, 1991, as amended at 66 FR 55789, Nov. 2, 2001; 72 FR 55922, Oct. 1, 2007] § 20.2002 Method for obtaining approval of proposed disposal procedures. A licensee or applicant for a license may apply to the Commission for approval of proposed procedures, not otherwise authorized in the regulations in this chapter, to dispose of licensed material generated in the licensee's activities. Each application shall include: (a) A description of the waste containing licensed material to be disposed of, including the physical and chemical properties important to risk evaluation, and the proposed manner and conditions of waste disposal; and (b) An analysis and evaluation of pertinent information on the nature of the environment; and (c) The nature and location of other potentially affected licensed and unlicensed facilities; and (d) Analyses and procedures to ensure that doses are maintained ALARA and within the dose limits in this part. § 20.2003 Disposal by release into sanitary sewerage. (a) A licensee may discharge licensed material into sanitary sewerage if each of the following conditions is satisfied: (1) The material is readily soluble (or is readily dispersible biological material) in water; and (2) The quantity of licensed or other radioactive material that the licensee releases into the sewer in 1 month divided by the average monthly volume of water released into the sewer by the licensee does not exceed the concentration listed in table 3 of appendix B to part 20; and (3) If more than one radionuclide is released, the following conditions must also be satisfied: (i) The licensee shall determine the fraction of the limit in table 3 of appendix B to part 20 represented by discharges into sanitary sewerage by dividing the actual monthly average concentration of each radionuclide released by the licensee into the sewer by the concentration of that radionuclide listed in table 3 of appendix B to part 20; and (ii) The sum of the fractions for each radionuclide required by paragraph (a)(3)(i) of this section does not exceed unity; and (4) The total quantity of licensed and other radioactive material that the licensee releases into the sanitary sewerage system in a year does not exceed 5 curies (185 GBq) of hydrogen-3, 1 curie (37 GBq) of carbon-14, and 1 curie (37 GBq) of all other radioactive materials combined. (b) Excreta from individuals undergoing medical diagnosis or therapy with radioactive material are not subject to the limitations contained in paragraph (a) of this section. [56 FR 23403, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995] § 20.2004 Treatment or disposal by incineration. (a) A licensee may treat or dispose of licensed material by incineration only: (1) As authorized by paragraph (b) of this section; or (2) If the material is in a form and concentration specified in § 20.2005; or (3) As specifically approved by the Commission pursuant to § 20.2002. (b)(1) Waste oils (petroleum derived or synthetic oils used principally as lubricants, coolants, hydraulic or insulating fluids, or metalworking oils) that have been radioactively contaminated in the course of the operation or maintenance of a nuclear power reactor licensed under part 50 or 53 of this chapter may be incinerated on the site where generated provided that the total radioactive effluents from the facility, including the effluents from such incineration, conform to the requirements of appendix I to part 50 or § 53.425(c) of this chapter and the effluent release limits contained in applicable license conditions other than effluent limits specifically related to incineration of waste oil. The licensee shall report any changes or additions to the information supplied under § 50.34 or § 50.34a or under subpart H of part 53 of this chapter associated with this incineration pursuant to § 50.71 or § 53.1620 of this chapter, as appropriate. The licensee shall also follow the procedures of § 50.59 or § 53.1565 of this chapter with respect to such changes to the facility or procedures. (2) Solid residues produced in the process of incinerating waste oils must be disposed of as provided by § 20.2001. (3) The provisions of this section authorize onsite waste oil incineration under the terms of this section and supersede any provision in an individual plant license or technical specification that may be inconsistent. [57 FR 57656, Dec. 7, 1992, as amended at 91 FR 15773, Mar. 30, 2026] § 20.2005 Disposal of specific wastes. (a) A licensee may dispose of the following licensed material as if it were not radioactive: (1) 0.05 microcurie (1.85 kBq), or less, of hydrogen-3 or carbon-14 per gram of medium used for liquid scintillation counting; and (2) 0.05 microcurie (1.85 kBq), or less, of hydrogen-3 or carbon-14 per gram of animal tissue, averaged over the weight of the entire animal. (b) A licensee may not dispose of tissue under paragraph (a)(2) of this section in a manner that would permit its use either as food for humans or as animal feed. (c) The licensee shall maintain records in accordance with § 20.2108. § 20.2006 Transfer for disposal and manifests. (a) The requirements of this section and appendix G to 10 CFR part 20 are designed to— (1) Control transfers of low-level radioactive waste by any waste generator, waste collector, or waste processor licensee, as defined in this part, who ships low-level waste either directly, or indirectly through a waste collector or waste processor, to a licensed low-level waste land disposal facility (as defined in part 61 of this chapter); (2) Establish a manifest tracking system; and (3) Supplement existing requirements concerning transfers and recordkeeping for those wastes. (b) Any licensee shipping radioactive waste intended for ultimate disposal at a licensed land disposal facility must document the information required on NRC's Uniform Low-Level Radioactive Waste Manifest and transfer this recorded manifest information to the intended consignee in accordance with appendix G to 10 CFR part 20. (c) Each shipment manifest must include a certification by the waste generator as specified in section II of appendix G to 10 CFR part 20. (d) Each person involved in the transfer for disposal and disposal of waste, including the waste generator, waste collector, waste processor, and disposal facility operator, shall comply with the requirements specified in section III of appendix G to 10 CFR part 20. (e) Any licensee shipping byproduct material as defined in paragraphs (3) and (4) of the definition of Byproduct material [63 FR 50128, Sept. 21, 1998, as amended at 72 FR 55922, Oct. 1, 2007] § 20.2007 Compliance with environmental and health protection regulations. Nothing in this subpart relieves the licensee from complying with other applicable Federal, State, and local regulations governing any other toxic or hazardous properties of materials that may be disposed of under this subpart. § 20.2008 Disposal of certain byproduct material. (a) Licensed material as defined in paragraphs (3) and (4) of the definition of Byproduct material (b) A licensee may dispose of byproduct material, as defined in paragraphs (3) and (4) of the definition of Byproduct material [72 FR 55922, Oct. 1, 2007] Subpart L—Records Source: 56 FR 23404, May 21, 1991, unless otherwise noted. § 20.2101 General provisions. (a) Each licensee shall use the units: curie, rad, rem, including multiples and subdivisions, and shall clearly indicate the units of all quantities on records required by this part. (b) In the records required by this part, the licensee may record quantities in SI units in parentheses following each of the units specified in paragraph (a) of this section. However, all quantities must be recorded as stated in paragraph (a) of this section. (c) Not withstanding the requirements of paragraph (a) of this section, when recording information on shipment manifests, as required in § 20.2006(b), information must be recorded in the International System of Units (SI) or in SI and units as specified in paragraph (a) of this section. (d) The licensee shall make a clear distinction among the quantities entered on the records required by this part (e.g., total effective dose equivalent, shallow-dose equivalent, lens dose equivalent, deep-dose equivalent, committed effective dose equivalent). [56 FR 23404, May 21, 1991, as amended at 60 FR 15663, Mar. 27, 1995; 63 FR 39483, July 23, 1998] § 20.2102 Records of radiation protection programs. (a) Each licensee shall maintain records of the radiation protection program, including: (1) The provisions of the program; and (2) Audits and other reviews of program content and implementation. (b) The licensee shall retain the records required by paragraph (a)(1) of this section until the Commission terminates each pertinent license requiring the record. The licensee shall retain the records required by paragraph (a)(2) of this section for 3 years after the record is made. § 20.2103 Records of surveys. (a) Each licensee shall maintain records showing the results of surveys and calibrations required by §§ 20.1501 and 20.1906(b). The licensee shall retain these records for 3 years after the record is made. (b) The licensee shall retain each of the following records until the Commission terminates each pertinent license requiring the record: (1) Records of the results of surveys to determine the dose from external sources and used, in the absence of or in combination with individual monitoring data, in the assessment of individual dose equivalents. This includes those records of results of surveys to determine the dose from external sources and used, in the absence of or in combination with individual monitoring data, in the assessment of individual dose equivalents required under the standards for protection against radiation in effect prior to January 1, 1994; and (2) Records of the results of measurements and calculations used to determine individual intakes of radioactive material and used in the assessment of internal dose. This includes those records of the results of measurements and calculations used to determine individual intakes of radioactive material and used in the assessment of internal dose required under the standards for protection against radiation in effect prior to January 1, 1994; and (3) Records showing the results of air sampling, surveys, and bioassays required pursuant to § 20.1703(c)(1) and (2). This includes those records showing the results of air sampling, surveys, and bioassays required under the standards for protection against radiation in effect prior to January 1, 1994; and (4) Records of the results of measurements and calculations used to evaluate the release of radioactive effluents to the environment. This includes those records of the results of measurements and calculations used to evaluate the release of radioactive effluents to the environment required under the standards for protection against radiation in effect prior to January 1, 1994. [56 FR 23404, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995; 66 FR 64737, Dec. 14, 2001] § 20.2104 Determination of prior occupational dose. (a) For each individual who is likely to receive an annual occupational dose requiring monitoring under § 20.1502, the licensee shall determine the occupational radiation dose received during the current year. (b) Prior to permitting an individual to participate in a planned special exposure, the licensee shall determine— (1) The internal and external doses from all previous planned special exposures; and (2) All doses in excess of the limits (including doses received during accidents and emergencies) received during the lifetime of the individual. (c) In complying with the requirements of paragraphs (a) or (b) of this section, a licensee may— (1) Accept, as a record of the occupational dose that the individual received during the current year, a written signed statement from the individual, or from the individual's most recent employer for work involving radiation exposure, that discloses the nature and the amount of any occupational dose that the individual may have received during the current year; (2) Accept, as the record of cumulative radiation dose, an up-to-date NRC Form 4, or equivalent, signed by the individual and countersigned by an appropriate official of the most recent employer for work involving radiation exposure, or the individual's current employer (if the individual is not employed by the licensee); and (3) Obtain reports of the individual's dose equivalent(s) from the most recent employer for work involving radiation exposure, or the individual's current employer (if the individual is not employed by the licensee) by telephone, telegram, electronic media, or letter. The licensee shall request a written verification of the dose data if the authenticity of the transmitted report cannot be established. (d) The licensee shall record the exposure history of each individual, as required by paragraphs (a) or (b) of this section, on NRC Form 4, or other clear and legible record, including all of the information required by NRC Form 4. 4 4 (e) If the licensee is unable to obtain a complete record of an individual's current and previously accumulated occupational dose, the licensee shall assume— (1) In establishing administrative controls under § 20.1201(f) for the current year, that the allowable dose limit for the individual is reduced by 1.25 rems (12.5 mSv) for each quarter for which records were unavailable and the individual was engaged in activities that could have resulted in occupational radiation exposure; and (2) That the individual is not available for planned special exposures. (f) The licensee shall retain the records on NRC Form 4 or equivalent until the Commission terminates each pertinent license requiring this record. The licensee shall retain records used in preparing NRC Form 4 for 3 years after the record is made. This includes records required under the standards for protection against radiation in effect prior to January 1, 1994. [56 FR 23404, May 21, 1991, as amended at 57 FR 57878, Dec. 8, 1992; 60 FR 20186, Apr. 25, 1995; 60 FR 36043, July 13, 1995; 72 FR 68059, Dec. 4, 2007] § 20.2105 Records of planned special exposures. (a) For each use of the provisions of § 20.1206 for planned special exposures, the licensee shall maintain records that describe— (1) The exceptional circumstances requiring the use of a planned special exposure; and (2) The name of the management official who authorized the planned special exposure and a copy of the signed authorization; and (3) What actions were necessary; and (4) Why the actions were necessary; and (5) How doses were maintained ALARA; and (6) What individual and collective doses were expected to result, and the doses actually received in the planned special exposure. (b) The licensee shall retain the records until the Commission terminates each pertinent license requiring these records. § 20.2106 Records of individual monitoring results. (a) Recordkeeping requirement. 5 5 (1) The deep-dose equivalent to the whole body, lens dose equivalent, shallow-dose equivalent to the skin, and shallow-dose equivalent to the extremities; (2) The estimated intake of radionuclides (see § 20.1202); (3) The committed effective dose equivalent assigned to the intake of radionuclides; (4) The specific information used to assess the committed effective dose equivalent pursuant to § 20.1204 (a) and (c), and when required by § 20.1502; (5) The total effective dose equivalent when required by § 20.1202; and (6) The total of the deep-dose equivalent and the committed dose to the organ receiving the highest total dose. (b) Recordkeeping frequency. (c) Recordkeeping format. (d) Privacy protection. (e) The licensee shall maintain the records of dose to an embryo/fetus with the records of dose to the declared pregnant woman. The declaration of pregnancy shall also be kept on file, but may be maintained separately from the dose records. (f) The licensee shall retain the required form or record until the Commission terminates each pertinent license requiring this record. This includes records required under the standards for protection against radiation in effect prior to January 1, 1994. [56 FR 23404, May 21, 1991, as amended at 60 FR 20186, Apr. 25, 1995; 63 FR 39483, July 23, 1998] § 20.2107 Records of dose to individual members of the public. (a) Each licensee shall maintain records sufficient to demonstrate compliance with the dose limit for individual members of the public (see § 20.1301). (b) The licensee shall retain the records required by paragraph (a) of this section until the Commission terminates each pertinent license requiring the record. § 20.2108 Records of waste disposal. (a) Each licensee shall maintain records of the disposal of licensed materials made under §§ 20.2002, 20.2003, 20.2004, 20.2005, 10 CFR part 61 and disposal by burial in soil, including burials authorized before January 28, 1981. 6 6 (b) The licensee shall retain the records required by paragraph (a) of this section until the Commission terminates each pertinent license requiring the record. Requirements for disposition of these records, prior to license termination, are located in §§ 30.51, 40.61, 70.51, and 72.80 for activities licensed under these parts. [56 FR 23404, May 21, 1991, as amended at 60 FR 20186, Apr. 25, 1995; 61 FR 24673, May 16, 1996] § 20.2109 [Reserved] § 20.2110 Form of records. Each record required by this part must be legible throughout the specified retention period. The record may be the original or a reproduced copy or a microform provided that the copy or microform is authenticated by authorized personnel and that the microform is capable of producing a clear copy throughout the required retention period. The record may also be stored in electronic media with the capability for producing legible, accurate, and complete records during the required retention period. Records, such as letters, drawings, and specifications, must include all pertinent information, such as stamps, initials, and signatures. The licensee shall maintain adequate safeguards against tampering with and loss of records. Subpart M—Reports Source: 56 FR 23406, May 21, 1991, unless otherwise noted. § 20.2201 Reports of theft or loss of licensed material. (a) Telephone reports. (i) Immediately after its occurrence becomes known to the licensee, any lost, stolen, or missing licensed material in an aggregate quantity equal to or greater than 1,000 times the quantity specified in appendix C to part 20 under such circumstances that it appears to the licensee that an exposure could result to persons in unrestricted areas; or (ii) Within 30 days after the occurrence of any lost, stolen, or missing licensed material becomes known to the licensee, all licensed material in a quantity greater than 10 times the quantity specified in appendix C to part 20 that is still missing at this time. (2) Reports must be made as follows: (i) Licensees having an installed Emergency Notification System shall make the reports to the NRC Operations Center under § 50.72 or § 53.1630 of this chapter, and (ii) All other licensees shall make reports by telephone to the NRC Headquarters Operations Center at the numbers specified in appendix A to part 73 of this chapter. (b) Written reports. (i) A description of the licensed material involved, including kind, quantity, and chemical and physical form; and (ii) A description of the circumstances under which the loss or theft occurred; and (iii) A statement of disposition, or probable disposition, of the licensed material involved; and (iv) Exposures of individuals to radiation, circumstances under which the exposures occurred, and the possible total effective dose equivalent to persons in unrestricted areas; and (v) Actions that have been taken, or will be taken, to recover the material; and (vi) Procedures or measures that have been, or will be, adopted to ensure against a recurrence of the loss or theft of licensed material. (2) Reports must be made as follows: (i) For holders of an operating license for a nuclear power plant, the events included in paragraph (b) of this section must be reported under the procedures described in § 50.73(b) through (e) and (g) or § 53.1640(b) through (e) of this chapter and must include the information required in paragraph (b)(1) of this section; and (ii) All other licensees shall make reports to the Administrator of the appropriate NRC Regional Office listed in appendix D to part 20. (c) A duplicate report is not required under paragraph (b) of this section if the licensee is also required to submit a report pursuant to § 30.55(c), § 37.57, § 37.81, § 40.64(c), § 50.72, § 50.73, § 53.1630, § 53.1640, § 70.52, § 73.27(b), § 73.67(e)(3)(vii) or (g)(3)(iii), § 73.1205, or § 150.19(c) of this chapter. (d) Subsequent to filing the written report, the licensee shall also report any additional substantive information on the loss or theft within 30 days after the licensee learns of such information. (e) The licensee shall prepare any report filed with the Commission pursuant to this section so that names of individuals who may have received exposure to radiation are stated in a separate and detachable part of the report. [56 FR 23406, May 21, 1991, as amended at 58 FR 69220, Dec. 30, 1993; 60 FR 20186, Apr. 25, 1995; 66 FR 64738, Dec. 14, 2001; 67 FR 3585, Jan. 25, 2002; 78 FR 17006, Mar. 19, 2013; 85 FR 65661, Oct. 16, 2020; 88 FR 15880, Mar. 14, 2023; 91 FR 15773, Mar. 30, 2026] § 20.2202 Notification of incidents. (a) Immediate notification. Notwithstanding any other requirements for notification, each licensee shall immediately report any event involving byproduct, source, or special nuclear material possessed by the licensee that may have caused or threatens to cause any of the following conditions— (1) An individual to receive— (i) A total effective dose equivalent of 25 rems (0.25 Sv) or more; or (ii) A lens dose equivalent of 75 rems (0.75 Sv) or more; or (iii) A shallow-dose equivalent to the skin or extremities of 250 rads (2.5 Gy) or more; or (2) The release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours, the individual could have received an intake five times the annual limit on intake (the provisions of this paragraph do not apply to locations where personnel are not normally stationed during routine operations, such as hot-cells or process enclosures). (b) Twenty-four hour notification. Each licensee shall, within 24 hours of discovery of the event, report any event involving loss of control of licensed material possessed by the licensee that may have caused, or threatens to cause, any of the following conditions: (1) An individual to receive, in a period of 24 hours— (i) A total effective dose equivalent exceeding 5 rems (0.05 Sv); or (ii) A lens dose equivalent exceeding 15 rems (0.15 Sv); or (iii) A shallow-dose equivalent to the skin or extremities exceeding 50 rems (0.5 Sv); or (2) The release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours, the individual could have received an intake in excess of one occupational annual limit on intake (the provisions of this paragraph do not apply to locations where personnel are not normally stationed during routine operations, such as hot-cells or process enclosures). (c) The licensee shall prepare any report filed with the Commission pursuant to this section so that names of individuals who have received exposure to radiation or radioactive material are stated in a separate and detachable part of the report. (d) Reports made by licensees in response to the requirements of this section must be made as follows: (1) Licensees having an installed Emergency Notification System shall make the reports required by paragraphs (a) and (b) of this section to the NRC Operations Center in accordance with 50.72 or § 53.1630 of this chapter; and (2) All other licensees shall make the reports required by paragraphs (a) and (b) of this section by telephone to the NRC Headquarters Operations Center at the numbers specified in appendix A to part 73 of this chapter. (e) The provisions of this section do not include doses that result from planned special exposures, that are within the limits for planned special exposures, and that are reported under § 20.2204. [56 FR 23406, May 21, 1991, as amended at 56 FR 40766, Aug. 16, 1991; 57 FR 57879, Dec. 8, 1992; 59 FR 14086, Mar. 25, 1994; 63 FR 39483, July 23, 1998; 85 FR 65661, Oct. 16, 2020; 91 FR 15773, Mar. 30, 2026] § 20.2203 Reports of exposures, radiation levels, and concentrations of radioactive material exceeding the constraints or limits. (a) Reportable events. (1) Any incident for which notification is required by § 20.2202; or (2) Doses in excess of any of the following: (i) The occupational dose limits for adults in § 20.1201; or (ii) The occupational dose limits for a minor in § 20.1207; or (iii) The limits for an embryo/fetus of a declared pregnant woman in § 20.1208; or (iv) The limits for an individual member of the public in § 20.1301; or (v) Any applicable limit in the license; or (vi) The ALARA constraints for air emissions established under § 20.1101(d); or (3) Levels of radiation or concentrations of radioactive material in— (i) A restricted area in excess of any applicable limit in the license; or (ii) An unrestricted area in excess of 10 times any applicable limit set forth in this part or in the license (whether or not involving exposure of any individual in excess of the limits in § 20.1301); or (4) For licensees subject to the provisions of EPA's generally applicable environmental radiation standards in 40 CFR part 190, levels of radiation or releases of radioactive material in excess of those standards, or of license conditions related to those standards. (b) Contents of reports. (i) Estimates of each individual's dose; and (ii) The levels of radiation and concentrations of radioactive material involved; and (iii) The cause of the elevated exposures, dose rates, or concentrations; and (iv) Corrective steps taken or planned to ensure against a recurrence, including the schedule for achieving conformance with applicable limits, ALARA constraints, generally applicable environmental standards, and associated license conditions. (2) Each report filed pursuant to paragraph (a) of this section must include for each occupationally overexposed 1 1 (c) For holders of an operating license or a combined license for a nuclear power plant, the occurrences included in paragraph (a) of this section must be reported under the procedures described in § 50.73(b) through (e) and (g) or § 53.1640(b) through (e) of this chapter, and must include the information required by paragraph (b) of this section. Occurrences reported under § 50.73 or § 53.1640 of this chapter need not be reported by a duplicate report under paragraph (a) of this section. (d) All licensees, other than those holding an operating license or a combined license for a nuclear power plant, who make reports under paragraph (a) of this section shall submit the report in writing either by mail addressed to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; by hand delivery to the NRC's offices at 11555 Rockville Pike, Rockville, Maryland; or, where practicable, by electronic submission, for example, Electronic Information Exchange, or CD-ROM. Electronic submissions must be made in a manner that enables the NRC to receive, read, authenticate, distribute, and archive the submission, and process and retrieve it a single page at a time. Detailed guidance on making electronic submissions can be obtained by visiting the NRC's Web site at http://www.nrc.gov/site-help/e-submittals.html; [email protected]; [56 FR 23406, May 21, 1991, as amended at 60 FR 20186, Apr. 25, 1995; 61 FR 65127, Dec. 10, 1996; 68 FR 14308, Mar. 25, 2003; 68 FR 58801, Oct. 10, 2003; 72 FR 49486, Aug. 28, 2007; 74 FR 62680, Dec. 1, 2009; 80 FR 74979, Dec. 1, 2015; 91 FR 15773, Mar. 30, 2026] § 20.2204 Reports of planned special exposures. The licensee shall submit a written report to the Administrator of the appropriate NRC Regional Office listed in appendix D to part 20 within 30 days following any planned special exposure conducted in accordance with § 20.1206, informing the Commission that a planned special exposure was conducted and indicating the date the planned special exposure occurred and the information required by § 20.2105. [56 FR 23406, May 21, 1991, as amended at 60 FR 20186, Apr. 25, 1995] § 20.2205 Reports to individuals of exceeding dose limits. When a licensee is required by §§ 20.2203 or 20.2204 to report to the Commission any exposure of an identified occupationally exposed individual, or an identified member of the public, to radiation or radioactive material, the licensee shall also provide the individual a report on his or her exposure data included in the report to Commission. This report must be transmitted no later than the transmittal to the Commission. [72 FR 68059, Dec. 4, 2007] § 20.2206 Reports of individual monitoring. (a) This section applies to each person licensed by the Commission to— (1) Operate a nuclear reactor designed to produce electrical or heat energy pursuant to § 50.21(b) or § 50.22 or part 53 of this chapter or a testing facility as defined in § 50.2 of this chapter; or (2) Possess or use byproduct material for purposes of radiography pursuant to parts 30 and 34 of this chapter; or (3) Possess or use at any one time, for purposes of fuel processing, fabricating, or reprocessing, special nuclear material in a quantity exceeding 5,000 grams of contained uranium-235, uranium-233, or plutonium, or any combination thereof pursuant to part 70 of this chapter; or (4) Possess high-level radioactive waste at a geologic repository operations area pursuant to part 60 or 63 of this chapter; or (5) Possess spent fuel in an independent spent fuel storage installation (ISFSI) pursuant to part 72 of this chapter; or (6) Receive radioactive waste from other persons for disposal under part 61 of this chapter; or (7) Possess or use at any time, for processing or manufacturing for distribution pursuant to parts 30, 32, 33 or 35 of this chapter, byproduct material in quantities exceeding any one of the following quantitites: Radionuclide Quantity of radionuclide 1 Cesium-137 1 Cobalt-60 1 Gold-198 100 Iodine-131 1 Iridium-192 10 Krypton-85 1,000 Promethium-147 10 Techetium-99m 1,000 1 (b) Each licensee in a category listed in paragraph (a) of this section shall submit an annual report of the results of individual monitoring carried out by the licensee for each individual for whom monitoring was required by § 20.1502 during that year. The licensee may include additional data for individuals for whom monitoring was provided but not required. The licensee shall use Form NRC 5 or electronic media containing all the information required by Form NRC 5. (c) The licensee shall file the report required by § 20.2206(b), covering the preceding year, on or before April 30 of each year. The licensee shall submit the report to the REIRS Project Manager by an appropriate method listed in § 20.1007 or via the REIRS Web site at http://www.reirs.com. [56 FR 23406, May 21, 1991, as amended at 56 FR 32072, July 15, 1991; 66 FR 55789, Nov. 2, 2001; 68 FR 58802, Oct. 10, 2003; 91 FR 15773, Mar. 30, 2026] § 20.2207 Reports of transactions involving nationally tracked sources. Each licensee who manufactures, transfers, receives, disassembles, or disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report as specified in paragraphs (a) through (e) of this section for each type of transaction. (a) Each licensee who manufactures a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information: (1) The name, address, and license number of the reporting licensee; (2) The name of the individual preparing the report; (3) The manufacturer, model, and serial number of the source; (4) The radioactive material in the source; (5) The initial source strength in becquerels (curies) at the time of manufacture; and (6) The manufacture date of the source. (b) Each licensee that transfers a nationally tracked source to another person shall complete and submit a National Source Tracking Transaction Report. The report must include the following information: (1) The name, address, and license number of the reporting licensee; (2) The name of the individual preparing the report; (3) The name and license number of the recipient facility and the shipping address; (4) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source; (5) The radioactive material in the source; (6) The initial or current source strength in becquerels (curies); (7) The date for which the source strength is reported; (8) The shipping date; (9) The estimated arrival date; and (10) For nationally tracked sources transferred as waste under a Uniform Low-Level Radioactive Waste Manifest, the waste manifest number and the container identification of the container with the nationally tracked source. (c) Each licensee that receives a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information: (1) The name, address, and license number of the reporting licensee; (2) The name of the individual preparing the report; (3) The name, address, and license number of the person that provided the source; (4) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source; (5) The radioactive material in the source; (6) The initial or current source strength in becquerels (curies); (7) The date for which the source strength is reported; (8) The date of receipt; and (9) For material received under a Uniform Low-Level Radioactive Waste Manifest, the waste manifest number and the container identification with the nationally tracked source. (d) Each licensee that disassembles a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information: (1) The name, address, and license number of the reporting licensee; (2) The name of the individual preparing the report; (3) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source; (4) The radioactive material in the source; (5) The initial or current source strength in becquerels (curies); (6) The date for which the source strength is reported; (7) The disassemble date of the source. (e) Each licensee who disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report. The report must include the following information: (1) The name, address, and license number of the reporting licensee; (2) The name of the individual preparing the report; (3) The waste manifest number; (4) The container identification with the nationally tracked source. (5) The date of disposal; and (6) The method of disposal. (f) The reports discussed in paragraphs (a) through (e) of this section must be submitted by the close of the next business day after the transaction. A single report may be submitted for multiple sources and transactions. The reports must be submitted to the National Source Tracking System by using: (1) The on-line National Source Tracking System; (2) Electronically using a computer-readable format; (3) By facsimile; (4) By mail to the address on the National Source Tracking Transaction Report Form (NRC Form 748); or (5) By telephone with followup by facsimile or mail. (g) Each licensee shall correct any error in previously filed reports or file a new report for any missed transaction within 5 business days of the discovery of the error or missed transaction. Such errors may be detected by a variety of methods such as administrative reviews or by physical inventories required by regulation. In addition, each licensee shall reconcile the inventory of nationally tracked sources possessed by the licensee against that licensee's data in the National Source Tracking System. The reconciliation must be conducted during the month of January in each year. The reconciliation process must include resolving any discrepancies between the National Source Tracking System and the actual inventory by filing the reports identified by paragraphs (a) through (e) of this section. By January 31 of each year, each licensee must submit to the National Source Tracking System confirmation that the data in the National Source Tracking System is correct. [71 FR 65707, Nov. 8, 2006, as amended at 72 FR 59163, Oct. 19, 2007; 86 FR 43401, Aug. 9, 2021] Subpart N—Exemptions and Additional Requirements Source: 56 FR 23408, May 21, 1991, unless otherwise noted. § 20.2301 Applications for exemptions. The Commission may, upon application by a licensee or upon its own initiative, grant an exemption from the requirements of the regulations in this part if it determines the exemption is authorized by law and would not result in undue hazard to life or property. § 20.2302 Additional requirements. The Commission may, by rule, regulation, or order, impose requirements on a licensee, in addition to those established in the regulations in this part, as it deems appropriate or necessary to protect health or to minimize danger to life or property. Subpart O—Enforcement § 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] § 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] Appendix A to Part 20—Assigned Protection Factors for Respirators a Operating mode Assigned I. Air Purifying Respirators [Particulate b c Filtering facepiece disposable d Negative Pressure ( d Facepiece, half e Negative Pressure 10 Facepiece, full Negative Pressure 100 Facepiece, half Powered air-purifying respirators 50 Facepiece, full Powered air-purifying respirators 1000 Helmet/hood Powered air-purifying respirators 1000 Facepiece, loose-fitting Powered air-purifying respirators 25 II. Atmosphere supplying respirators [particulate, gases and vapors f 1. Air-line respirator: Facepiece, half Demand 10 Facepiece, half Continuous Flow 50 Facepiece, half Pressure Demand 50 Facepiece, full Demand 100 Facepiece, full Continuous Flow 1000 Facepiece, full Pressure Demand 1000 Helmet/hood Continuous Flow 1000 Facepiece, loose-fitting Continuous Flow 25 Suit Continuous Flow ( g 2. Self-contained breathing Apparatus (SCBA): Facepiece, full Demand h Facepiece, full Pressure Demand i Facepiece, full Demand, Recirculating h Facepiece, full Positive Pressure Recirculating i III. Combination Respirators: Any combination of air-purifying and atmosphere-supplying respirators Assigned protection factor for type and mode of operation as listed above. a 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. b c d e f g i.e. h i [64 FR 54558, Oct. 7, 1999; 64 FR 55524, Oct. 13, 1999] 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 2 0 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, w T T A value of w T 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 (ALI ns i.e. ns d d 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 × 10 4 9 4 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. 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 × 10 9 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 × 10 7 7 5 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 × 10 6 6 5 List of Elements Name Atomic Symbol No. Actinium Ac 89 Aluminum Al 13 Americium Am 95 Antimony Sb 51 Argon Ar 18 Arsenic As 33 Astatine At 85 Barium Ba 56 Berkelium Bk 97 Beryllium Be 4 Bismuth Bi 83 Bromine Br 35 Cadmium Cd 48 Calcium Ca 20 Californium Cf 98 Carbon C 6 Cerium Ce 58 Cesium Cs 55 Chlorine Cl 17 Chromium Cr 24 Cobalt Co 27 Copper Cu 29 Curium Cm 96 Dysprosium Dy 66 Einsteinium Es 99 Erbium Er 68 Europium Eu 63 Fermium Fm 100 Fluorine F 9 Francium Fr 87 Gadolinium Gd 64 Gallium Ga 31 Germanium Ge 32 Gold Au 79 Hafnium Hf 72 Holmium Ho 67 Hydrogen H 1 Indium In 49 Iodine I 53 Iridium Ir 77 Iron Fe 26 Krypton Kr 36 Lanthanum La 57 Lead Pb 82 Lutetium Lu 71 Magnesium Mg 12 Manganese Mn 25 Mendelevium Md 101 Mercury Hg 80 Molybdenum Mo 42 Neodymium Nd 60 Neptunium Np 93 Nickel Ni 28 Niobium Nb 41 Nitrogen N 7 Osmium Os 76 Oxygen O 8 Palladium Pd 46 Phosphorus P 15 Platinum Pt 78 Plutonium Pu 94 Polonium Po 84 Potassium K 19 Praseodymium Pr 59 Promethium Pm 61 Protactinium Pa 91 Radium Ra 88 Radon Rn 86 Rhenium Re 75 Rhodium Rh 45 Rubidium Rb 37 Ruthenium Ru 44 Samarium Sm 62 Scandium Sc 21 Selenium Se 34 Silicon Si 14 Silver Ag 47 Sodium Na 11 Strontium Sr 38 Sulfur S 16 Tantalum Ta 73 Technetium Tc 43 Tellurium Te 52 Terbium Tb 65 Thallium Tl 81 Thorium Th 90 Thulium Tm 69 Tin Sn 50 Titanium Ti 22 Tungsten W 74 Uranium U 92 Vanadium V 23 Xenon Xe 54 Ytterbium Yb 70 Yttrium Y 39 Zinc Zn 30 Zirconium Zr 40 [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] Appendix C to Part 20—Quantities 1 Radionuclide Quantity (µCi) Hydrogen-3 1,000 Beryllium-7 1,000 Beryllium-10 1 Carbon-11 1,000 Carbon-14 100 Fluorine-18 1,000 Sodium-22 10 Sodium-24 100 Magnesium-28 100 Aluminum-26 10 Silicon-31 1,000 Silicon-32 1 Phosphorus-32 10 Phosphorus-33 100 Sulfur-35 100 Chlorine-36 10 Chlorine-38 1,000 Chlorine-39 1,000 Argon-39 1,000 Argon-41 1,000 Potassium-40 100 Potassium-42 1,000 Potassium-43 1,000 Potassium-44 1,000 Potassium-45 1,000 Calcium-41 100 Calcium-45 100 Calcium-47 100 Scandium-43 1,000 Scandium-44m 100 Scandium-44 100 Scandium-46 10 Scandium-47 100 Scandium-48 100 Scandium-49 1,000 Titanium-44 1 Titanium-45 1,000 Vanadium-47 1,000 Vanadium-48 100 Vanadium-49 1,000 Chromium-48 1,000 Chromium-49 1,000 Chromium-51 1,000 Manganese-51 1,000 Manganese-52m 1,000 Manganese-52 100 Manganese-53 1,000 Manganese-54 100 Manganese-56 1,000 Iron-52 100 Iron-55 100 Iron-59 10 Iron-60 1 Cobalt-55 100 Cobalt-56 10 Cobalt-57 100 Cobalt-58m 1,000 Cobalt-58 100 Cobalt-60m 1,000 Cobalt-60 1 Cobalt-61 1,000 Cobalt-62m 1,000 Nickel-56 100 Nickel-57 100 Nickel-59 100 Nickel-63 100 Nickel-65 1,000 Nickel-66 10 Copper-60 1,000 Copper-61 1,000 Copper-64 1,000 Copper-67 1,000 Zinc-62 100 Zinc-63 1,000 Zinc-65 10 Zinc-69m 100 Zinc-69 1,000 Zinc-71m 1,000 Zinc-72 100 Gallium-65 1,000 Gallium-66 100 Gallium-67 1,000 Gallium-68 1,000 Gallium-70 1,000 Gallium-72 100 Gallium-73 1,000 Germanium-66 1,000 Germanium-67 1,000 Germanium-68 10 Germanium-69 1,000 Germanium-71 1,000 Germanium-75 1,000 Germanium-77 1,000 Germanium-78 1,000 Arsenic-69 1,000 Arsenic-70 1,000 Arsenic-71 100 Arsenic-72 100 Arsenic-73 100 Arsenic-74 100 Arsenic-76 100 Arsenic-77 100 Arsenic-78 1,000 Selenium-70 1,000 Selenium-73m 1,000 Selenium-73 100 Selenium-75 100 Selenium-79 100 Selenium-81m 1,000 Selenium-81 1,000 Selenium-83 1,000 Bromine-74m 1,000 Bromine-74 1,000 Bromine-75 1,000 Bromine-76 100 Bromine-77 1,000 Bromine-80m 1,000 Bromine-80 1,000 Bromine-82 100 Bromine-83 1,000 Bromine-84 1,000 Krypton-74 1,000 Krypton-76 1,000 Krypton-77 1,000 Krypton-79 1,000 Krypton-81 1,000 Krypton-83m 1,000 Krypton-85m 1,000 Krypton-85 1,000 Krypton-87 1,000 Krypton-88 1,000 Rubidium-79 1,000 Rubidium-81m 1,000 Rubidium-81 1,000 Rubidium-82m 1,000 Rubidium-83 100 Rubidium-84 100 Rubidium-86 100 Rubidium-87 100 Rubidium-88 1,000 Rubidium-89 1,000 Strontium-80 100 Strontium-81 1,000 Strontium-83 100 Strontium-85m 1,000 Strontium-85 100 Strontium-87m 1,000 Strontium-89 10 Strontium-90 0.1 Strontium-91 100 Strontium-92 100 Yttrium-86m 1,000 Yttrium-86 100 Yttrium-87 100 Yttrium-88 10 Yttrium-90m 1,000 Yttrium-90 10 Yttrium-91m 1,000 Yttrium-91 10 Yttrium-92 100 Yttrium-93 100 Yttrium-94 1,000 Yttrium-95 1,000 Zirconium-86 100 Zirconium-88 10 Zirconium-89 100 Zirconium-93 1 Zirconium-95 10 Zirconium-97 100 Niobium-88 1,000 Niobium-89m (66 min) 1,000 Niobium-89 (122 min) 1,000 Niobium-90 100 Niobium-93m 10 Niobium-94 1 Niobium-95m 100 Niobium-95 100 Niobium-96 100 Niobium-97 1,000 Niobium-98 1,000 Molybdenum-90 100 Molybdenum-93m 100 Molybdenum-93 10 Molybdenum-99 100 Molybdenum-101 1,000 Technetium-93m 1,000 Technetium-93 1,000 Technetium-94m 1,000 Technetium-94 1,000 Technetium-96m 1,000 Technetium-96 100 Technetium-97m 100 Technetium-97 1,000 Technetium-98 10 Technetium-99m 1,000 Technetium-99 100 Technetium-101 1,000 Technetium-104 1,000 Ruthenium-94 1,000 Ruthenium-97 1,000 Ruthenium-103 100 Ruthenium-105 1,000 Ruthenium-106 1 Rhodium-99m 1,000 Rhodium-99 100 Rhodium-100 100 Rhodium-101m 1,000 Rhodium-101 10 Rhodium-102m 10 Rhodium-102 10 Rhodium-103m 1,000 Rhodium-105 100 Rhodium-106m 1,000 Rhodium-107 1,000 Palladium-100 100 Palladium-101 1,000 Palladium-103 100 Palladium-107 10 Palladium-109 100 Silver-102 1,000 Silver-103 1,000 Silver-104m 1,000 Silver-104 1,000 Silver-105 100 Silver-106m 100 Silver-106 1,000 Silver-108m 1 Silver-110m 10 Silver-111 100 Silver-112 100 Silver-115 1,000 Cadmium-104 1,000 Cadmium-107 1,000 Cadmium-109 1 Cadmium-113m 0.1 Cadmium-113 100 Cadmium-115m 10 Cadmium-115 100 Cadmium-117m 1,000 Cadmium-117 1,000 Indium-109 1,000 Indium-110 (69.1min.) 1,000 Indium-110 (4.9h) 1,000 Indium-111 100 Indium-112 1,000 Indium-113m 1,000 Indium-114m 10 Indium-115m 1,000 Indium-115 100 Indium-116m 1,000 Indium-117m 1,000 Indium-117 1,000 Indium-119m 1,000 Tin-110 100 Tin-111 1,000 Tin-113 100 Tin-117m 100 Tin-119m 100 Tin-121m 100 Tin-121 1,000 Tin-123m 1,000 Tin-123 10 Tin-125 10 Tin-126 10 Tin-127 1,000 Tin-128 1,000 Antimony-115 1,000 Antimony-116m 1,000 Antimony-116 1,000 Antimony-117 1,000 Antimony-118m 1,000 Antimony-119 1,000 Antimony-120 (16min.) 1,000 Antimony-120 (5.76d) 100 Antimony-122 100 Antimony-124m 1,000 Antimony-124 10 Antimony-125 100 Antimony-126m 1,000 Antimony-126 100 Antimony-127 100 Antimony-128 (10.4min.) 1,000 Antimony-128 (9.01h) 100 Antimony-129 100 Antimony-130 1,000 Antimony-131 1,000 Tellurium-116 1,000 Tellurium-121m 10 Tellurium-121 100 Tellurium-123m 10 Tellurium-123 100 Tellurium-125m 10 Tellurium-127m 10 Tellurium-127 1,000 Tellurium-129m 10 Tellurium-129 1,000 Tellurium-131m 10 Tellurium-131 100 Tellurium-132 10 Tellurium-133m 100 Tellurium-133 1,000 Tellurium-134 1,000 Iodine-120m 1,000 Iodine-120 100 Iodine-121 1,000 Iodine-123 100 Iodine-124 10 Iodine-125 1 Iodine-126 1 Iodine-128 1,000 Iodine-129 1 Iodine-130 10 Iodine-131 1 Iodine-132m 100 Iodine-132 100 Iodine-133 10 Iodine-134 1,000 Iodine-135 100 Xenon-120 1,000 Xenon-121 1,000 Xenon-122 1,000 Xenon-123 1,000 Xenon-125 1,000 Xenon-127 1,000 Xenon-129m 1,000 Xenon-131m 1,000 Xenon-133m 1,000 Xenon-133 1,000 Xenon-135m 1,000 Xenon-135 1,000 Xenon-138 1,000 Cesium-125 1,000 Cesium-127 1,000 Cesium-129 1,000 Cesium-130 1,000 Cesium-131 1,000 Cesium-132 100 Cesium-134m 1,000 Cesium-134 10 Cesium-135m 1,000 Cesium-135 100 Cesium-136 10 Cesium-137 10 Cesium-138 1,000 Barium-126 1,000 Barium-128 100 Barium-131m 1,000 Barium-131 100 Barium-133m 100 Barium-133 100 Barium-135m 100 Barium-139 1,000 Barium-140 100 Barium-141 1,000 Barium-142 1,000 Lanthanum-131 1,000 Lanthanum-132 100 Lanthanum-135 1,000 Lanthanum-137 10 Lanthanum-138 100 Lanthanum-140 100 Lanthanum-141 100 Lanthanum-142 1,000 Lanthanum-143 1,000 Cerium-134 100 Cerium-135 100 Cerium-137m 100 Cerium-137 1,000 Cerium-139 100 Cerium-141 100 Cerium-143 100 Cerium-144 1 Praseodymium-136 1,000 Praseodymium-137 1,000 Praseodymium-138m 1,000 Praseodymium-139 1,000 Praseodymium-142m 1,000 Praseodymium-142 100 Praseodymium-143 100 Praseodymium-144 1,000 Praseodymium-145 100 Praseodymium-147 1,000 Neodymium-136 1,000 Neodymium-138 100 Neodymium-139m 1,000 Neodymium-139 1,000 Neodymium-141 1,000 Neodymium-147 100 Neodymium-149 1,000 Neodymium-151 1,000 Promethium-141 1,000 Promethium-143 100 Promethium-144 10 Promethium-145 10 Promethium-146 1 Promethium-147 10 Promethium-148m 10 Promethium-148 10 Promethium-149 100 Promethium-150 1,000 Promethium-151 100 Samarium-141m 1,000 Samarium-141 1,000 Samarium-142 1,000 Samarium-145 100 Samarium-146 1 Samarium-147 100 Samarium-151 10 Samarium-153 100 Samarium-155 1,000 Samarium-156 1,000 Europium-145 100 Europium-146 100 Europium-147 100 Europium-148 10 Europium-149 100 Europium-150 (12.62h) 100 Europium-150 (34.2y) 1 Europium-152m 100 Europium-152 1 Europium-154 1 Europium-155 10 Europium-156 100 Europium-157 100 Europium-158 1,000 Gadolinium-145 1,000 Gadolinium-146 10 Gadolinium-147 100 Gadolinium-148 0.001 Gadolinium-149 100 Gadolinium-151 10 Gadolinium-152 100 Gadolinium-153 10 Gadolinium-159 100 Terbium-147 1,000 Terbium-149 100 Terbium-150 1,000 Terbium-151 100 Terbium-153 1,000 Terbium-154 100 Terbium-155 1,000 Terbium-156m (5.0h) 1,000 Terbium-156m (24.4h) 1,000 Terbium-156 100 Terbium-157 10 Terbium-158 1 Terbium-160 10 Terbium-161 100 Dysprosium-155 1,000 Dysprosium-157 1,000 Dysprosium-159 100 Dysprosium-165 1,000 Dysprosium-166 100 Holmium-155 1,000 Holmium-157 1,000 Holmium-159 1,000 Holmium-161 1,000 Holmium-162m 1,000 Holmium-162 1,000 Holmium-164m 1,000 Holmium-164 1,000 Holmium-166m 1 Holmium-166 100 Holmium-167 1,000 Erbium-161 1,000 Erbium-165 1,000 Erbium-169 100 Erbium-171 100 Erbium-172 100 Thulium-162 1,000 Thulium-166 100 Thulium-167 100 Thulium-170 10 Thulium-171 10 Thulium-172 100 Thulium-173 100 Thulium-175 1,000 Ytterbium-162 1,000 Ytterbium-166 100 Ytterbium-167 1,000 Ytterbium-169 100 Ytterbium-175 100 Ytterbium-177 1,000 Ytterbium-178 1,000 Lutetium-169 100 Lutetium-170 100 Lutetium-171 100 Lutetium-172 100 Lutetium-173 10 Lutetium-174m 10 Lutetium-174 10 Lutetium-176m 1,000 Lutetium-176 100 Lutetium-177m 10 Lutetium-177 100 Lutetium-178m 1,000 Lutetium-178 1,000 Lutetium-179 1,000 Hafnium-170 100 Hafnium-172 1 Hafnium-173 1,000 Hafnium-175 100 Hafnium-177m 1,000 Hafnium-178m 0.1 Hafnium-179m 10 Hafnium-180m 1,000 Hafnium-181 10 Hafnium-182m 1,000 Hafnium-182 0.1 Hafnium-183 1,000 Hafnium-184 100 Tantalum-172 1,000 Tantalum-173 1,000 Tantalum-174 1,000 Tantalum-175 1,000 Tantalum-176 100 Tantalum-177 1,000 Tantalum-178 1,000 Tantalum-179 100 Tantalum-180m 1,000 Tantalum-180 100 Tantalum-182m 1,000 Tantalum-182 10 Tantalum-183 100 Tantalum-184 100 Tantalum-185 1,000 Tantalum-186 1,000 Tungsten-176 1,000 Tungsten-177 1,000 Tungsten-178 1,000 Tungsten-179 1,000 Tungsten-181 1,000 Tungsten-185 100 Tungsten-187 100 Tungsten-188 10 Rhenium-177 1,000 Rhenium-178 1,000 Rhenium-181 1,000 Rhenium-182 (12.7h) 1,000 Rhenium-182 (64.0h) 100 Rhenium-184m 10 Rhenium-184 100 Rhenium-186m 10 Rhenium-186 100 Rhenium-187 1,000 Rhenium-188m 1,000 Rhenium-188 100 Rhenium-189 100 Osmium-180 1,000 Osmium-181 1,000 Osmium-182 100 Osmium-185 100 Osmium-189m 1,000 Osmium-191m 1,000 Osmium-191 100 Osmium-193 100 Osmium-194 1 Iridium-182 1,000 Iridium-184 1,000 Iridium-185 1,000 Iridium-186 100 Iridium-187 1,000 Iridium-188 100 Iridium-189 100 Iridium-190m 1,000 Iridium-190 100 Iridium-192 (73.8d) 1 Iridium-192m (1.4min.) 10 Iridium-194m 10 Iridium-194 100 Iridium-195m 1,000 Iridium-195 1,000 Platinum-186 1,000 Platinum-188 100 Platinum-189 1,000 Platinum-191 100 Platinum-193m 100 Platinum-193 1,000 Platinum-195m 100 Platinum-197m 1,000 Platinum-197 100 Platinum-199 1,000 Platinum-200 100 Gold-193 1,000 Gold-194 100 Gold-195 10 Gold-198m 100 Gold-198 100 Gold-199 100 Gold-200m 100 Gold-200 1,000 Gold-201 1,000 Mercury-193m 100 Mercury-193 1,000 Mercury-194 1 Mercury-195m 100 Mercury-195 1,000 Mercury-197m 100 Mercury-197 1,000 Mercury-199m 1,000 Mercury-203 100 Thallium-194m 1,000 Thallium-194 1,000 Thallium-195 1,000 Thallium-197 1,000 Thallium-198m 1,000 Thallium-198 1,000 Thallium-199 1,000 Thallium-200 1,000 Thallium-201 1,000 Thallium-202 100 Thallium-204 100 Lead-195m 1,000 Lead-198 1,000 Lead-199 1,000 Lead-200 100 Lead-201 1,000 Lead-202m 1,000 Lead-202 10 Lead-203 1,000 Lead-205 100 Lead-209 1,000 Lead-210 0.01 Lead-211 100 Lead-212 1 Lead-214 100 Bismuth-200 1,000 Bismuth-201 1,000 Bismuth-202 1,000 Bismuth-203 100 Bismuth-205 100 Bismuth-206 100 Bismuth-207 10 Bismuth-210m 0.1 Bismuth-210 1 Bismuth-212 10 Bismuth-213 10 Bismuth-214 100 Polonium-203 1,000 Polonium-205 1,000 Polonium-207 1,000 Polonium-210 0.1 Astatine-207 100 Astatine-211 10 Radon-220 1 Radon-222 1 Francium-222 100 Francium-223 100 Radium-223 0.1 Radium-224 0.1 Radium-225 0.1 Radium-226 0.1 Radium-227 1,000 Radium-228 0.1 Actinium-224 1 Actinium-225 0.01 Actinium-226 0.1 Actinium-227 0.001 Actinium-228 1 Thorium-226 10 Thorium-227 0.01 Thorium-228 0.001 Thorium-229 0.001 Thorium-230 0.001 Thorium-231 100 Thorium-232 100 Thorium-234 10 Thorium-natural 100 Protactinium-227 10 Protactinium-228 1 Protactinium-230 0.1 Protactinium-231 0.001 Protactinium-232 1 Protactinium-233 100 Protactinium-234 100 Uranium-230 0.01 Uranium-231 100 Uranium-232 0.001 Uranium-233 0.001 Uranium-234 0.001 Uranium-235 0.001 Uranium-236 0.001 Uranium-237 100 Uranium-238 100 Uranium-239 1,000 Uranium-240 100 Uranium-natural 100 Neptunium-232 100 Neptunium-233 1,000 Neptunium-234 100 Neptunium-235 100 Neptunium-236 (1.15 × 10 5 0.001 Neptunium-236 (22.5h) 1 Neptunium-237 0.001 Neptunium-238 10 Neptunium-239 100 Neptunium-240 1,000 Plutonium-234 10 Plutonium-235 1,000 Plutonium-236 0.001 Plutonium-237 100 Plutonium-238 0.001 Plutonium-239 0.001 Plutonium-240 0.001 Plutonium-241 0.01 Plutonium-242 0.001 Plutonium-243 1,000 Plutonium-244 0.001 Plutonium-245 100 Americium-237 1,000 Americium-238 100 Americium-239 1,000 Americium-240 100 Americium-241 0.001 Americium-242m 0.001 Americium-242 10 Americium-243 0.001 Americium-244m 100 Americium-244 10 Americium-245 1,000 Americium-246m 1,000 Americium-246 1,000 Curium-238 100 Curium-240 0.1 Curium-241 1 Curium-242 0.01 Curium-243 0.001 Curium-244 0.001 Curium-245 0.001 Curium-246 0.001 Curium-247 0.001 Curium-248 0.001 Curium-249 1,000 Berkelium-245 100 Berkelium-246 100 Berkelium-247 0.001 Berkelium-249 0.1 Berkelium-250 10 Californium-244 100 Californium-246 1 Californium-248 0.01 Californium-249 0.001 Californium-250 0.001 Californium-251 0.001 Californium-252 0.001 Californium-253 0.1 Californium-254 0.001 Any alpha emitting radionuclide not listed above or mixtures of alpha emitters of unknown composition 0.001 Einsteinium-250 100 Einsteinium-251 100 Einsteinium-253 0.1 Einsteinium-254m 1 Einsteinium-254 0.01 Fermium-252 1 Fermium-253 1 Fermium-254 10 Fermium-255 1 Fermium-257 0.01 Mendelevium-257 10 Mendelevium-258 0.01 Any radionuclide other than alpha emitting radionuclides not listed above, or mixtures of beta emitters of unknown composition 0.01 1 1 10 9 Note: i.e. [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] Appendix D to Part 20—United States Nuclear Regulatory Commission Regional Offices Address Telephone (24 hour) E-Mail NRC Headquarters Operations Center USNRC, Division of Preparedness and Response, Washington, DC 20555-0001 (301) 816-5100 [email protected] Region I: Connecticut, Delaware, District of Columbia, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont USNRC, Region I, 475 Allendale Road, Suite 102, King of Prussia, PA 19406-1415 (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 Virginia USNRC, Region II, 245 Peachtree Center Avenue, NE., Suite 1200, Atlanta, GA 30303-1257. (404) 997-4000 [email protected] Region III: Illinois, Indiana, Iowa, Michigan, Minnesota, Missouri, Ohio and Wisconsin USNRC, Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352 (630) 829-9500 [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 Pacific US NRC, Region IV, 1600 E Lamar Blvd., Arlington, TX 76011-4511 (817) 200-1100, (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; 85 FR 65661, Oct. 16, 2020; 87 FR 20696, Apr. 8, 2022; 87 FR 68030, Nov. 14, 2022] 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 Category 1 Category 2 Category 2 Actinium-227 20 540 0.2 5.4 Americium-241 60 1,600 0.6 16 Americium-241/Be 60 1,600 0.6 16 Californium-252 20 540 0.2 5.4 Cobalt-60 30 810 0.3 8.1 Curium-244 50 1,400 0.5 14 Cesium-137 100 2,700 1 27 Gadolinium-153 1,000 27,000 10 270 Iridium-192 80 2,200 0.8 22 Plutonium-238 60 1,600 0.6 16 Plutonium-239/Be 60 1,600 0.6 16 Polonium-210 60 1,600 0.6 16 Promethium-147 40,000 1,100,000 400 11,000 Radium-226 40 1,100 0.4 11 Selenium-75 200 5,400 2 54 Strontium-90 1,000 27,000 10 270 Thorium-228 20 540 0.2 5.4 Thorium-229 20 540 0.2 5.4 Thulium-170 20,000 540,000 200 5,400 Ytterbium-169 300 8,100 3 81 [71 FR 65708, Nov. 8, 2006] 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. (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 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 Chemical description Computer-readable medium Consignee Decontamination facility Disposal container EPA identification number Generator High integrity container Land disposal facility NRC Forms 540, 540A, 541, 541A, 542, and 542A Package Physical description Residual waste Shipper i.e. Shipping paper Source material Special nuclear material Uniform Low-Level Radioactive Waste Manifest uniform manifest Waste collector Waste description Waste generator Waste processor Waste type i.e. 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. 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. (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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