{"database": "openregs", "table": "cfr_sections", "is_view": false, "human_description_en": "where part_number = 20 and title_number = 10 sorted by section_id", "rows": [["10:10:1.0.1.1.16.1.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "A", "Subpart A\u2014General Provisions", "", "\u00a7 20.1001 Purpose.", "NRC", "", "", "", "(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.\n\n(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."], ["10:10:1.0.1.1.16.1.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "A", "Subpart A\u2014General Provisions", "", "\u00a7 20.1002 Scope.", "NRC", "", "", "[72 FR 49485, Aug. 28, 2007]", "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, 39, 40, 50, 52, 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 \u00a7 35.75, or to exposure from voluntary participation in medical research programs."], ["10:10:1.0.1.1.16.1.76.3", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "A", "Subpart A\u2014General Provisions", "", "\u00a7 20.1003 Definitions.", "NRC", "", "", "[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]", "As used in this part:\n\nAbsorbed dose  means the energy imparted by ionizing radiation per unit mass of irradiated material. The units of absorbed dose are the rad and the gray (Gy).\n\nAccelerator-produced radioactive material  means any material made radioactive by a particle accelerator.\n\nAct  means the Atomic Energy Act of 1954 (42 U.S.C. 2011  et seq. ), as amended.\n\nActivity  is the rate of disintegration (transformation) or decay of radioactive material. The units of activity are the curie (Ci) and the becquerel (Bq).\n\nAdult  means an individual 18 or more years of age.\n\nAirborne radioactive material  means radioactive material dispersed in the air in the form of dusts, fumes, particulates, mists, vapors, or gases.\n\nAirborne radioactivity area  means a room, enclosure, or area in which airborne radioactive materials, composed wholly or partly of licensed material, exist in concentrations\u2014\n\n(1) In excess of the derived air concentrations (DACs) specified in appendix B, to \u00a7\u00a7 20.1001-20.2401, or\n\n(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.\n\nAir-purifying respirator  means a respirator with an air-purifying filter, cartridge, or canister that removes specific air contaminants by passing ambient air through the air-purifying element.\n\nALARA  (acronym for \u201cas low as is reasonably achievable\u201d) means making every reasonable effort to maintain exposures to radiation as far below the dose limits in this part as is practical consistent with the purpose for which the licensed activity is undertaken, taking into account the state of technology, the economics of improvements in relation to state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and licensed materials in the public interest.\n\nAnnual limit on intake  (ALI) means the derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by the reference man that would result in a committed effective dose equivalent of 5 rems (0.05 Sv) or a committed dose equivalent of 50 rems (0.5 Sv) to any individual organ or tissue. (ALI values for intake by ingestion and by inhalation of selected radionuclides are given in table 1, columns 1 and 2, of appendix B to \u00a7\u00a7 20.1001-20.2401).\n\nAssigned protection factor (APF)  means the expected workplace level of respiratory protection that would be provided by a properly functioning respirator or a class of respirators to properly fitted and trained users. Operationally, the inhaled concentration can be estimated by dividing the ambient airborne concentration by the APF.\n\nAtmosphere-supplying respirator  means a respirator that supplies the respirator user with breathing air from a source independent of the ambient atmosphere, and includes supplied-air respirators (SARs) and self-contained breathing apparatus (SCBA) units.\n\nBackground radiation  means radiation from cosmic sources; naturally occurring radioactive material, including radon (except as a decay product of source or special nuclear material); and global fallout as it exists in the environment from the testing of nuclear explosive devices or from past nuclear accidents such as Chernobyl that contribute to background radiation and are not under the control of the licensee.  \u201cBackground radiation\u201d  does not include radiation from source, byproduct, or special nuclear materials regulated by the Commission.\n\nBioassay  (radiobioassay) means the determination of kinds, quantities or concentrations, and, in some cases, the locations of radioactive material in the human body, whether by direct measurement (in vivo counting) or by analysis and evaluation of materials excreted or removed from the human body.\n\nByproduct material  means\u2014\n\n(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;\n\n(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 \u201cbyproduct material\u201d within this definition;\n\n(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\n\n(ii) Any material that\u2014\n\n(A) Has been made radioactive by use of a particle accelerator; and\n\n(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\n\n(4) Any discrete source of naturally occurring radioactive material, other than source material, that\u2014\n\n(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\n\n(ii) Before, on, or after August 8, 2005, is extracted or converted after extraction for use in a commercial, medical, or research activity.\n\nClass  (or  lung class  or  inhalation class ) means a classification scheme for inhaled material according to its rate of clearance from the pulmonary region of the lung. Materials are classified as D, W, or Y, which applies to a range of clearance half-times: for Class D (Days) of less than 10 days, for Class W (Weeks) from 10 to 100 days, and for Class Y (Years) of greater than 100 days.\n\nCollective dose  is the sum of the individual doses received in a given period of time by a specified population from exposure to a specified source of radiation.\n\nCommission  means the Nuclear Regulatory Commission or its duly authorized representatives.\n\nCommitted dose equivalent  (H T,50 ) means the dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.\n\nCommitted effective dose equivalent  (H E,50 ) is the sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues (H E,50  = \u03a3 w T  H T,50 ).\n\nConstraint (dose constraint)  means a value above which specified licensee actions are required.\n\nControlled area  means an area, outside of a restricted area but inside the site boundary, access to which can be limited by the licensee for any reason.\n\nCritical Group  means the group of individuals reasonably expected to receive the greatest exposure to residual radioactivity for any applicable set of circumstances.\n\nDeclared pregnant woman  means a woman who has voluntarily informed the licensee, in writing, of her pregnancy and the estimated date of conception. The declaration remains in effect until the declared pregnant woman withdraws the declaration in writing or is no longer pregnant.\n\nDecommission  means to remove a facility or site safely from service and reduce residual radioactivity to a level that permits\u2014\n\n(1) Release of the property for unrestricted use and termination of the license; or\n\n(2) Release of the property under restricted conditions and the termination of the license.\n\nDeep-dose equivalent  (H d ), which applies to external whole-body exposure, is the dose equivalent at a tissue depth of 1 cm (1000 mg/cm\n 2 ).\n\nDemand respirator  means an atmosphere-supplying respirator that admits breathing air to the facepiece only when a negative pressure is created inside the facepiece by inhalation.\n\nDepartment  means the Department of Energy established by the Department of Energy Organization Act (Pub. L. 95-91, 91 Stat. 565, 42 U.S.C. 7101  et seq. ) to the extent that the Department, or its duly authorized representatives, exercises functions formerly vested in the U.S. Atomic Energy Commission, its Chairman, members, officers, and components and transferred to the U.S. Energy Research and Development Administration and to the Administrator thereof pursuant to sections 104 (b), (c), and (d) of the Energy Reorganization Act of 1974 (Pub. L. 93-438, 88 Stat. 1233 at 1237, 42 U.S.C. 5814) and retransferred to the Secretary of Energy pursuant to section 301(a) of the Department of Energy Organization Act (Pub. L. 95-91, 91 Stat 565 at 577-578, 42 U.S.C. 7151).\n\nDerived air concentration  (DAC) means the concentration of a given radionuclide in air which, if breathed by the reference man for a working year of 2,000 hours under conditions of light work (inhalation rate 1.2 cubic meters of air per hour), results in an intake of one ALI. DAC values are given in table 1, column 3, of appendix B to \u00a7\u00a7 20.1001-20.2401.\n\nDerived air concentration-hour  (DAC-hour) is the product of the concentration of radioactive material in air (expressed as a fraction or multiple of the derived air concentration for each radionuclide) and the time of exposure to that radionuclide, in hours. A licensee may take 2,000 DAC-hours to represent one ALI, equivalent to a committed effective dose equivalent of 5 rems (0.05 Sv).\n\nDiscrete source  means a radionuclide that has been processed so that its concentration within a material has been purposely increased for use for commercial, medical, or research activities.\n\nDisposable respirator  means a respirator for which maintenance is not intended and that is designed to be discarded after excessive breathing resistance, sorbent exhaustion, physical damage, or end-of-service-life renders it unsuitable for use. Examples of this type of respirator are a disposable half-mask respirator or a disposable escape-only self-contained breathing apparatus (SCBA).\n\nDistinguishable from background  means that the detectable concentration of a radionuclide is statistically different from the background concentration of that radionuclide in the vicinity of the site or, in the case of structures, in similar materials using adequate measurement technology, survey, and statistical techniques.\n\nDose  or  radiation dose  is a generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equivalent, committed effective dose equivalent, or total effective dose equivalent, as defined in other paragraphs of this section.\n\nDose equivalent  (H T ) means the product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest. The units of dose equivalent are the rem and sievert (Sv).\n\nDosimetry processor  means an individual or organization that processes and evaluates individual monitoring equipment in order to determine the radiation dose delivered to the equipment.\n\nEffective dose equivalent  (H E ) is the sum of the products of the dose equivalent to the organ or tissue (H T ) and the weighting factors (w T ) applicable to each of the body organs or tissues that are irradiated (H E  = \u03a3 w T  H T ).\n\nEmbryo/fetus  means the developing human organism from conception until the time of birth.\n\nEntrance or access point  means any location through which an individual could gain access to radiation areas or to radioactive materials. This includes entry or exit portals of sufficient size to permit human entry, irrespective of their intended use.\n\nExposure  means being exposed to ionizing radiation or to radioactive material.\n\nExternal dose  means that portion of the dose equivalent received from radiation sources outside the body.\n\nExtremity  means hand, elbow, arm below the elbow, foot, knee, or leg below the knee.\n\nFiltering facepiece (dust mask)  means a negative pressure particulate respirator with a filter as an integral part of the facepiece or with the entire facepiece composed of the filtering medium, not equipped with elastomeric sealing surfaces and adjustable straps.\n\nFit factor  means a quantitative estimate of the fit of a particular respirator to a specific individual, and typically estimates the ratio of the concentration of a substance in ambient air to its concentration inside the respirator when worn.\n\nFit test  means the use of a protocol to qualitatively or quantitatively evaluate the fit of a respirator on an individual.\n\nGenerally applicable environmental radiation standards  means standards issued by the Environmental Protection Agency (EPA) under the authority of the Atomic Energy Act of 1954, as amended, that impose limits on radiation exposures or levels, or concentrations or quantities of radioactive material, in the general environment outside the boundaries of locations under the control of persons possessing or using radioactive material.\n\nGovernment agency  means any executive department, commission, independent establishment, corporation wholly or partly owned by the United States of America, which is an instrumentality of the United States, or any board, bureau, division, service, office, officer, authority, administration, or other establishment in the executive branch of the Government.\n\nGray  [See \u00a7 20.1004].\n\nHelmet  means a rigid respiratory inlet covering that also provides head protection against impact and penetration.\n\nHigh radiation area  means an area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 0.1 rem (1 mSv) in 1 hour at 30 centimeters from the radiation source or 30 centimeters from any surface that the radiation penetrates.\n\nHood  means a respiratory inlet covering that completely covers the head and neck and may also cover portions of the shoulders and torso.\n\nIndividual  means any human being.\n\nIndividual monitoring  means\u2014\n\n(1) The assessment of dose equivalent by the use of devices designed to be worn by an individual;\n\n(2) The assessment of committed effective dose equivalent by bioassay (see  Bioassay ) or by determination of the time-weighted air concentrations to which an individual has been exposed, i.e., DAC-hours; or\n\n(3) The assessment of dose equivalent by the use of survey data.\n\nIndividual monitoring devices  (individual monitoring equipment) means devices designed to be worn by a single individual for the assessment of dose equivalent such as film badges, thermoluminescence dosimeters (TLDs), pocket ionization chambers, and personal (\u201clapel\u201d) air sampling devices.\n\nInternal dose  means that portion of the dose equivalent received from radioactive material taken into the body.\n\nLens dose equivalent (LDE)  applies to the external exposure of the lens of the eye and is taken as the dose equivalent at a tissue depth of 0.3 centimeter (300 mg/cm\n 2 ).\n\nLicense  means a license issued under the regulations in parts 30 through 36, 39, 40, 50, 60, 61, 63, 70, or 72 of this chapter.\n\nLicensed material  means source material, special nuclear material, or byproduct material received, possessed, used, transferred or disposed of under a general or specific license issued by the Commission.\n\nLicensee  means the holder of a license.\n\nLimits  (dose limits) means the permissible upper bounds of radiation doses.\n\nLoose-fitting facepiece  means a respiratory inlet covering that is designed to form a partial seal with the face.\n\nLost or missing licensed material  means licensed material whose location is unknown. It includes material that has been shipped but has not reached its destination and whose location cannot be readily traced in the transportation system.\n\nMember of the public  means any individual except when that individual is receiving an occupational dose.\n\nMinor  means an individual less than 18 years of age.\n\nMonitoring  (radiation monitoring, radiation protection monitoring) means the measurement of radiation levels, concentrations, surface area concentrations or quantities of radioactive material and the use of the results of these measurements to evaluate potential exposures and doses.\n\nNationally tracked source  is a sealed source containing a quantity equal to or greater than Category 1 or Category 2 levels of any radioactive material listed in Appendix E of this part. In this context a sealed source is defined as radioactive material that is sealed in a capsule or closely bonded, in a solid form and which is not exempt from regulatory control. It does not mean material encapsulated solely for disposal, or nuclear material contained in any fuel assembly, subassembly, fuel rod, or fuel pellet. Category 1 nationally tracked sources are those containing radioactive material at a quantity equal to or greater than the Category 1 threshold. Category 2 nationally tracked sources are those containing radioactive material at a quantity equal to or greater than the Category 2 threshold but less than the Category 1 threshold.\n\nNegative pressure respirator (tight fitting)  means a respirator in which the air pressure inside the facepiece is negative during inhalation with respect to the ambient air pressure outside the respirator.\n\nNonstochastic effect  means health effects, the severity of which varies with the dose and for which a threshold is believed to exist. Radiation-induced cataract formation is an example of a nonstochastic effect (also called a deterministic effect).\n\nNRC  means the Nuclear Regulatory Commission or its duly authorized representatives.\n\nOccupational dose  means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under \u00a7 35.75, from voluntary participation in medical research programs, or as a member of the public.\n\nParticle accelerator  means any machine capable of accelerating electrons, protons, deuterons, or other charged particles in a vacuum and of discharging the resultant particulate or other radiation into a medium at energies usually in excess of 1 megaelectron volt. For purposes of this definition, \u201caccelerator\u201d is an equivalent term.\n\nPerson  means\u2014\n\n(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\n\n(2) Any legal successor, representative, agent, or agency of the foregoing.\n\nPlanned special exposure  means an infrequent exposure to radiation, separate from and in addition to the annual dose limits.\n\nPositive pressure respirator  means a respirator in which the pressure inside the respiratory inlet covering exceeds the ambient air pressure outside the respirator.\n\nPowered air-purifying respirator (PAPR)  means an air-purifying respirator that uses a blower to force the ambient air through air-purifying elements to the inlet covering.\n\nPressure demand respirator  means a positive pressure atmosphere-supplying respirator that admits breathing air to the facepiece when the positive pressure is reduced inside the facepiece by inhalation.\n\nPublic dose  means the dose received by a member of the public from exposure to radiation or to radioactive material released by a licensee, or to any other source of radiation under the control of a licensee. Public dose does not include occupational dose or doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under \u00a7 35.75, or from voluntary participation in medical research programs.\n\nQualitative fit test (QLFT)  means a pass/fail fit test to assess the adequacy of respirator fit that relies on the individual's response to the test agent.\n\nQuality Factor (Q)  means the modifying factor (listed in tables 1004(b).1 and 1004(b).2 of \u00a7 20.1004) that is used to derive dose equivalent from absorbed dose.\n\nQuantitative fit test (QNFT)  means an assessment of the adequacy of respirator fit by numerically measuring the amount of leakage into the respirator.\n\nQuarter  means a period of time equal to one-fourth of the year observed by the licensee (approximately 13 consective weeks), providing that the beginning of the first quarter in a year coincides with the starting date of the year and that no day is omitted or duplicated in consecutive quarters.\n\nRad  (See \u00a7 20.1004).\n\nRadiation  (ionizing radiation) means alpha particles, beta particles, gamma rays, x-rays, neutrons, high-speed electrons, high-speed protons, and other particles capable of producing ions. Radiation, as used in this part, does not include non-ionizing radiation, such as radio- or microwaves, or visible, infrared, or ultraviolet light.\n\nRadiation area  means an area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 0.005 rem (0.05 mSv) in 1 hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates.\n\nReference man  means a hypothetical aggregation of human physical and physiological characteristics arrived at by international consensus. These characteristics may be used by researchers and public health workers to standardize results of experiments and to relate biological insult to a common base.\n\nRem  (See \u00a7 20.1004).\n\nResidual radioactivity  means radioactivity in structures, materials, soils, groundwater, and other media at a site resulting from activities under the licensee's control. This includes radioactivity from all licensed and unlicensed sources used by the licensee, but excludes background radiation. It also includes radioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site and previous burials at the site, even if those burials were made in accordance with the provisions of 10 CFR part 20.\n\nRespiratory protective device  means an apparatus, such as a respirator, used to reduce the individual's intake of airborne radioactive materials.\n\nRestricted area  means an area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials. Restricted area does not include areas used as residential quarters, but separate rooms in a residential building may be set apart as a restricted area.\n\nSanitary sewerage  means a system of public sewers for carrying off waste water and refuse, but excluding sewage treatment facilities, septic tanks, and leach fields owned or operated by the licensee.\n\nSelf-contained breathing apparatus (SCBA)  means an atmosphere-supplying respirator for which the breathing air source is designed to be carried by the user.\n\nShallow-dose equivalent (H s ),  which applies to the external exposure of the skin of the whole body or the skin of an extremity, is taken as the dose equivalent at a tissue depth of 0.007 centimeter (7 mg/cm\n 2 ).\n\nSite boundary  means that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.\n\nSource material  means\u2014\n\n(1) Uranium or thorium or any combination of uranium and thorium in any physical or chemical form; or\n\n(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.\n\nSpecial nuclear material  means\u2014\n\n(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\n\n(2) Any material artificially enriched by any of the foregoing but does not include source material.\n\nStochastic effects  means health effects that occur randomly and for which the probability of the effect occurring, rather than its severity, is assumed to be a linear function of dose without threshold. Hereditary effects and cancer incidence are examples of stochastic effects.\n\nSupplied-air respirator (SAR)  or  airline respirator  means an atmosphere-supplying respirator for which the source of breathing air is not designed to be carried by the user.\n\nSurvey  means an evaluation of the radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of radioactive material or other sources of radiation. When appropriate, such an evaluation includes a physical survey of the location of radioactive material and measurements or calculations of levels of radiation, or concentrations or quantities of radioactive material present.\n\nTight-fitting facepiece  means a respiratory inlet covering that forms a complete seal with the face.\n\nTotal Effective Dose Equivalent  (TEDE) means the sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).\n\nUnrestricted area  means an area, access to which is neither limited nor controlled by the licensee.\n\nUranium fuel cycle  means the operations of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel to the extent that these activities directly support the production of electrical power for public use. Uranium fuel cycle does not include mining operations, operations at waste disposal sites, transportation of radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and byproduct materials from the cycle.\n\nUser seal check (fit check)  means an action conducted by the respirator user to determine if the respirator is properly seated to the face. Examples include negative pressure check, positive pressure check, irritant smoke check, or isoamyl acetate check.\n\nVery high radiation area  means an area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving an absorbed dose in excess of 500 rads (5 grays) in 1 hour at 1 meter from a radiation source or 1 meter from any surface that the radiation penetrates.\n\nAt 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)).\n\nWaste  means those low-level radioactive wastes containing source, special nuclear, or byproduct material that are acceptable for disposal in a land disposal facility. For the purposes of this definition, low-level radioactive waste means radioactive waste not classified as high-level radioactive waste, transuranic waste, spent nuclear fuel, or byproduct material as defined in paragraphs (2), (3), and (4) of the definition of Byproduct material set forth in this section.\n\nWeek  means 7 consecutive days starting on Sunday.\n\nWeighting factor  w T , for an organ or tissue (T) is the proportion of the risk of stochastic effects resulting from irradiation of that organ or tissue to the total risk of stochastic effects when the whole body is irradiated uniformly. For calculating the effective dose equivalent, the values of w T  are:\n\nOrgan Dose Weighting Factors\n\n1  0.30 results from 0.06 for each of 5 \u201cremainder\u201d organs (excluding the skin and the lens of the eye) that receive the highest doses.\n\n2  For the purpose of weighting the external whole body dose (for adding it to the internal dose), a single weighting factor, w T  = 1.0, has been specified. The use of other weighting factors for external exposure will be approved on a case-by-case basis until such time as specific guidance is issued.\n\nWhole body  means, for purposes of external exposure, head, trunk (including male gonads), arms above the elbow, or legs above the knee.\n\nWorking level  (WL) is any combination of short-lived radon daughters (for radon-222: polonium-218, lead-214, bismuth-214, and polonium-214; and for radon-220: polonium-216, lead-212, bismuth-212, and polonium-212) in 1 liter of air that will result in the ultimate emission of 1.3 \u00d7 10\n 5  MeV of potential alpha particle energy.\n\nWorking level month  (WLM) means an exposure to 1 working level for 170 hours (2,000 working hours per year/12 months per year = approximately 170 hours per month).\n\nYear  means the period of time beginning in January used to determine compliance with the provisions of this part. The licensee may change the starting date of the year used to determine compliance by the licensee provided that the change is made at the beginning of the year and that no day is omitted or duplicated in consecutive years."], ["10:10:1.0.1.1.16.1.76.4", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "A", "Subpart A\u2014General Provisions", "", "\u00a7 20.1004 Units of radiation dose.", "NRC", "", "", "", "(a)  Definitions.  As used in this part, the units of radiation dose are:\n\nGray  (Gy) is the SI unit of absorbed dose. One gray is equal to an absorbed dose of 1 Joule/kilogram (100 rads).\n\nRad  is the special unit of absorbed dose. One rad is equal to an absorbed dose of 100 ergs/gram or 0.01 joule/kilogram (0.01 gray).\n\nRem  is the special unit of any of the quantities expressed as dose equivalent. The dose equivalent in rems is equal to the absorbed dose in rads multiplied by the quality factor (1 rem = 0.01 sievert).\n\nSievert  is the SI unit of any of the quantities expressed as dose equivalent. The dose equivalent in sieverts is equal to the absorbed dose in grays multiplied by the quality factor (1 Sv = 100 rems).\n\n(b) As used in this part, the quality factors for converting absorbed dose to dose equivalent are shown in table 1004(b).1.\n\nTable 1004( b ).1\u2014Quality Factors and Absorbed Dose Equivalencies\n\na  Absorbed dose in rad equal to 1 rem or the absorbed dose in gray equal to 1 sievert.\n\n(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.\n\nTable 1004( b ).2\u2014Mean Quality Factors, Q, and Fluence per Unit Dose Equivalent for Monoenergetic Neutrons\n\na  Value of quality factor (Q) at the point where the dose equivalent is maximum in a 30-cm diameter cylinder tissue-equivalent phantom.\n\nb  Monoenergetic neutrons incident normally on a 30-cm diameter cylinder tissue-equivalent phantom."], ["10:10:1.0.1.1.16.1.76.5", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "A", "Subpart A\u2014General Provisions", "", "\u00a7 20.1005 Units of radioactivity.", "NRC", "", "", "[56 FR 23391, May 21, 1991; 56 FR 61352, Dec. 3, 1991]", "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.\n\n(a) One becquerel = 1 disintegration per second (s \u22121 ).\n\n(b) One curie = 3.7 \u00d7 10 \n 10  disintegrations per second = 3.7 \u00d7 10 \n 10  becquerels = 2.22 \u00d7 10 \n 12  disintegrations per minute."], ["10:10:1.0.1.1.16.1.76.6", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "A", "Subpart A\u2014General Provisions", "", "\u00a7 20.1006 Interpretations.", "NRC", "", "", "[56 FR 23391, May 21, 1991, as amended at 90 FR 55628, Dec. 3, 2025]", "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  announcing its determination and revising or removing this section accordingly."], ["10:10:1.0.1.1.16.1.76.7", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "A", "Subpart A\u2014General Provisions", "", "\u00a7 20.1007 Communications.", "NRC", "", "", "[68 FR 58801, Oct. 10, 2003, as amended at 74 FR 62680, Dec. 1, 2009; 80 FR 74979, Dec. 1, 2015]", "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;  by e-mail to  MSHD.Resource@nrc.gov;  or by writing the Office of the Chief Information Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. The guidance discusses, among other topics, the formats the NRC can accept, the use of electronic signatures, and the treatment of nonpublic information."], ["10:10:1.0.1.1.16.1.76.8", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "A", "Subpart A\u2014General Provisions", "", "\u00a7 20.1008 Implementation.", "NRC", "", "", "[59 FR 41643, Aug. 15, 1994]", "(a) [Reserved]\n\n(b) The applicable section of \u00a7\u00a7 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 \n 1 \n   that are cited in license conditions or technical specifications, except as specified in paragraphs (c), (d), and (e) of this section. If the requirements of this part are more restrictive than the existing license condition, then the licensee shall comply with this part unless exempted by paragraph (d) of this section.\n\n1  See \u00a7\u00a7 20.1-20.602 codified as of January 1, 1993.\n\n(c) Any existing license condition or technical specification that is more restrictive than a requirement in \u00a7\u00a7 20.1001-20.2402 remains in force until there is a technical specification change, license amendment, or license renewal.\n\n(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, \n 1  it continues to exempt a licensee from the corresponding provision of \u00a7\u00a7 20.1001-20.2402.\n\n(e) If a license condition cites provisions in requirements in the standards for protection against radiation in effect prior to January 1, 1994 \n 1  and there are no corresponding provisions in \u00a7\u00a7 20.1001-20.2402, then the license condition remains in force until there is a technical specification change, license amendment, or license renewal that modifies or removes this condition."], ["10:10:1.0.1.1.16.1.76.9", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "A", "Subpart A\u2014General Provisions", "", "\u00a7 20.1009 Information collection requirements: OMB approval.", "NRC", "", "", "[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]", "(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. ). The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. OMB has approved the information collection requirements contained in this part under control number 3150-0014.\n\n(b) The approved information collection requirements contained in this part appear in \u00a7\u00a7 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.\n\n(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:\n\n(1) In \u00a7 20.2104, NRC Form 4 is approved under control number 3150-0005.\n\n(2) In \u00a7\u00a7 20.2106 and 20.2206, NRC Form 5 is approved under control number 3150-0006.\n\n(3) In \u00a7 20.2006 and appendix G to 10 CFR part 20, NRC Form 540 and 540A is approved under control number 3150-0164.\n\n(4) In \u00a7 20.2006 and appendix G to 10 CFR part 20, NRC Form 541 and 541A is approved under control number 3150-0166.\n\n(5) In \u00a7 20.2006 and appendix G to 10 CFR part 20, NRC Form 542 and 542A is approved under control number 3150-0165.\n\n(6) In \u00a7 20.2207, NRC Form 748 is approved under control number 3150-0202."], ["10:10:1.0.1.1.16.10.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "J", "Subpart J\u2014Precautionary Procedures", "", "\u00a7 20.1901 Caution signs.", "NRC", "", "", "", "(a)  Standard radiation symbol.  Unless otherwise authorized by the Commission, the symbol prescribed by this part shall use the colors magenta, or purple, or black on yellow background. The symbol prescribed by this part is the three-bladed design:\n\n(1) Cross-hatched area is to be magenta, or purple, or black, and\n\n(2) The background is to be yellow.\n\n(b)  Exception to color requirements for standard radiation symbol.  Notwithstanding the requirements of paragraph (a) of this section, licensees are authorized to label sources, source holders, or device components containing sources of licensed materials that are subjected to high temperatures, with conspicuously etched or stamped radiation caution symbols and without a color requirement.\n\n(c)  Additional information on signs and labels.  In addition to the contents of signs and labels prescribed in this part, the licensee may provide, on or near the required signs and labels, additional information, as appropriate, to make individuals aware of potential radiation exposures and to minimize the exposures."], ["10:10:1.0.1.1.16.10.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "J", "Subpart J\u2014Precautionary Procedures", "", "\u00a7 20.1902 Posting requirements.", "NRC", "", "", "[56 FR 23401, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995]", "(a)  Posting of radiation areas.  The licensee shall post each radiation area with a conspicuous sign or signs bearing the radiation symbol and the words \u201cCAUTION, RADIATION AREA.\u201d\n\n(b)  Posting of high radiation areas.  The licensee shall post each high radiation area with a conspicuous sign or signs bearing the radiation symbol and the words \u201cCAUTION, HIGH RADIATION AREA\u201d or \u201cDANGER, HIGH RADIATION AREA.\u201d\n\n(c)  Posting of very high radiation areas.  The licensee shall post each very high radiation area with a conspicuous sign or signs bearing the radiation symbol and words \u201cGRAVE DANGER, VERY HIGH RADIATION AREA.\u201d\n\n(d)  Posting of airborne radioactivity areas.  The licensee shall post each airborne radioactivity area with a conspicuous sign or signs bearing the radiation symbol and the words \u201cCAUTION, AIRBORNE RADIOACTIVITY AREA\u201d or \u201cDANGER, AIRBORNE RADIOACTIVITY AREA.\u201d\n\n(e)  Posting of areas or rooms in which licensed material is used or stored.  The licensee shall post each area or room in which there is used or stored an amount of licensed material exceeding 10 times the quantity of such material specified in appendix C to part 20 with a conspicuous sign or signs bearing the radiation symbol and the words \u201cCAUTION, RADIOACTIVE MATERIAL(S)\u201d or \u201cDANGER, RADIOACTIVE MATERIAL(S).\u201d"], ["10:10:1.0.1.1.16.10.76.3", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "J", "Subpart J\u2014Precautionary Procedures", "", "\u00a7 20.1903 Exceptions to posting requirements.", "NRC", "", "", "[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]", "(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:\n\n(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\n\n(2) The area or room is subject to the licensee's control.\n\n(b) Rooms or other areas in hospitals that are occupied by patients are not required to be posted with caution signs pursuant to \u00a7 20.1902 provided that the patient could be released from licensee control pursuant to \u00a7 35.75 of this chapter.\n\n(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.\n\n(d) Rooms in hospitals or clinics that are used for teletherapy are exempt from the requirement to post caution signs under \u00a7 20.1902 if\u2014\n\n(1) Access to the room is controlled pursuant to 10 CFR 35.615; and\n\n(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."], ["10:10:1.0.1.1.16.10.76.4", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "J", "Subpart J\u2014Precautionary Procedures", "", "\u00a7 20.1904 Labeling containers.", "NRC", "", "", "", "(a) The licensee shall ensure that each container of licensed material bears a durable, clearly visible label bearing the radiation symbol and the words \u201cCAUTION, RADIOACTIVE MATERIAL\u201d or \u201cDANGER, RADIOACTIVE MATERIAL.\u201d 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.\n\n(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."], ["10:10:1.0.1.1.16.10.76.5", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "J", "Subpart J\u2014Precautionary Procedures", "", "\u00a7 20.1905 Exemptions to labeling requirements.", "NRC", "", "", "[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]", "A licensee is not required to label\u2014\n\n(a) Containers holding licensed material in quantities less than the quantities listed in appendix C to part 20; or\n\n(b) Containers holding licensed material in concentrations less than those specified in table 3 of appendix B to part 20; or\n\n(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\n\n(d) Containers when they are in transport and packaged and labeled in accordance with the regulations of the Department of Transportation, \n 3 \n   or\n\n3  Labeling of packages containing radioactive materials is required by the Department of Transportation (DOT) if the amount and type of radioactive material exceeds the limits for an excepted quantity or article as defined and limited by DOT regulations 49 CFR 173.403 (m) and (w) and 173.421-424.\n\n(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\n\n(f) Installed manufacturing or process equipment, such as reactor components, piping, and tanks; or\n\n(g) Containers holding licensed material (other than sealed sources that are either specifically or generally licensed) at a facility licensed under Parts 50 or 52 of this chapter, not including non-power production or utilization facilities, that are within an area posted under the requirements in \u00a7 20.1902 if the containers are:\n\n(1) Conspicuously marked (such as by providing a system of color coding of containers) commensurate with the radiological hazard;\n\n(2) Accessible only to individuals who have sufficient instruction to minimize radiation exposure while handling or working in the vicinity of the containers; and\n\n(3) Subject to plant procedures to ensure they are appropriately labeled, as specified at \u00a7 20.1904 before being removed from the posted area."], ["10:10:1.0.1.1.16.10.76.6", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "J", "Subpart J\u2014Precautionary Procedures", "", "\u00a7 20.1906 Procedures for receiving and opening packages.", "NRC", "", "", "[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]", "(a) Each licensee who expects to receive a package containing quantities of radioactive material in excess of a Type A quantity, as defined in \u00a7 71.4 and appendix A to part 71 of this chapter, shall make arrangements to receive\u2014\n\n(1) The package when the carrier offers it for delivery; or\n\n(2) Notification of the arrival of the package at the carrier's terminal and to take possession of the package expeditiously.\n\n(b) Each licensee shall\u2014\n\n(1) Monitor the external surfaces of a labeled \n 3a \n   package for radioactive contamination unless the package contains only radioactive material in the form of a gas or in special form as defined in 10 CFR 71.4;\n\n3a  Labeled with a Radioactive White I, Yellow II, or Yellow III label as specified in U.S. Department of Transportation regulations, 49 CFR 172.403 and 172.436-440.\n\n(2) Monitor the external surfaces of a labeled \n 3a  package for radiation levels unless the package contains quantities of radioactive material that are less than or equal to the Type A quantity, as defined in \u00a7 71.4 and appendix A to part 71 of this chapter; and\n\n(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.\n\n(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.\n\n(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\u2014\n\n(1) Removable radioactive surface contamination exceeds the limits of \u00a7 71.87(i) of this chapter; or\n\n(2) External radiation levels exceed the limits of \u00a7 71.47 of this chapter.\n\n(e) Each licensee shall\u2014\n\n(1) Establish, maintain, and retain written procedures for safely opening packages in which radioactive material is received; and\n\n(2) Ensure that the procedures are followed and that due consideration is given to special instructions for the type of package being opened.\n\n(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."], ["10:10:1.0.1.1.16.11.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "K", "Subpart K\u2014Waste Disposal", "", "\u00a7 20.2001 General requirements.", "NRC", "", "", "[56 FR 23403, May 21, 1991, as amended at 66 FR 55789, Nov. 2, 2001; 72 FR 55922, Oct. 1, 2007]", "(a) A licensee shall dispose of licensed material only\u2014\n\n(1) By transfer to an authorized recipient as provided in \u00a7 20.2006 or in the regulations in parts 30, 40, 60, 61, 63, 70, and 72 of this chapter;\n\n(2) By decay in storage; or\n\n(3) By release in effluents within the limits in \u00a7 20.1301; or\n\n(4) As authorized under \u00a7\u00a7 20.2002, 20.2003, 20.2004, 20.2005, or 20.2008.\n\n(b) A person must be specifically licensed to receive waste containing licensed material from other persons for:\n\n(1) Treatment prior to disposal; or\n\n(2) Treatment or disposal by incineration; or\n\n(3) Decay in storage; or\n\n(4) Disposal at a land disposal facility licensed under part 61 of this chapter; or\n\n(5) Disposal at a geologic repository under part 60 or part 63 of this chapter."], ["10:10:1.0.1.1.16.11.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "K", "Subpart K\u2014Waste Disposal", "", "\u00a7 20.2002 Method for obtaining approval of proposed disposal procedures.", "NRC", "", "", "", "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:\n\n(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\n\n(b) An analysis and evaluation of pertinent information on the nature of the environment; and\n\n(c) The nature and location of other potentially affected licensed and unlicensed facilities; and\n\n(d) Analyses and procedures to ensure that doses are maintained ALARA and within the dose limits in this part."], ["10:10:1.0.1.1.16.11.76.3", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "K", "Subpart K\u2014Waste Disposal", "", "\u00a7 20.2003 Disposal by release into sanitary sewerage.", "NRC", "", "", "[56 FR 23403, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995]", "(a) A licensee may discharge licensed material into sanitary sewerage if each of the following conditions is satisfied:\n\n(1) The material is readily soluble (or is readily dispersible biological material) in water; and\n\n(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\n\n(3) If more than one radionuclide is released, the following conditions must also be satisfied:\n\n(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\n\n(ii) The sum of the fractions for each radionuclide required by paragraph (a)(3)(i) of this section does not exceed unity; and\n\n(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.\n\n(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."], ["10:10:1.0.1.1.16.11.76.4", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "K", "Subpart K\u2014Waste Disposal", "", "\u00a7 20.2004 Treatment or disposal by incineration.", "NRC", "", "", "[57 FR 57656, Dec. 7, 1992]", "(a) A licensee may treat or dispose of licensed material by incineration only:\n\n(1) As authorized by paragraph (b) of this section; or\n\n(2) If the material is in a form and concentration specified in \u00a7 20.2005; or\n\n(3) As specifically approved by the Commission pursuant to \u00a7 20.2002.\n\n(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 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 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 \u00a7\u00a7 50.34 and 50.34a of this chapter associated with this incineration pursuant to \u00a7 50.71 of this chapter, as appropriate. The licensee shall also follow the procedures of \u00a7 50.59 of this chapter with respect to such changes to the facility or procedures.\n\n(2) Solid residues produced in the process of incinerating waste oils must be disposed of as provided by \u00a7 20.2001.\n\n(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."], ["10:10:1.0.1.1.16.11.76.5", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "K", "Subpart K\u2014Waste Disposal", "", "\u00a7 20.2005 Disposal of specific wastes.", "NRC", "", "", "", "(a) A licensee may dispose of the following licensed material as if it were not radioactive:\n\n(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\n\n(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.\n\n(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.\n\n(c) The licensee shall maintain records in accordance with \u00a7 20.2108."], ["10:10:1.0.1.1.16.11.76.6", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "K", "Subpart K\u2014Waste Disposal", "", "\u00a7 20.2006 Transfer for disposal and manifests.", "NRC", "", "", "[63 FR 50128, Sept. 21, 1998, as amended at 72 FR 55922, Oct. 1, 2007]", "(a) The requirements of this section and appendix G to 10 CFR part 20 are designed to\u2014\n\n(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);\n\n(2) Establish a manifest tracking system; and\n\n(3) Supplement existing requirements concerning transfers and recordkeeping for those wastes.\n\n(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.\n\n(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.\n\n(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.\n\n(e) Any licensee shipping byproduct material as defined in paragraphs (3) and (4) of the definition of  Byproduct material  set forth in \u00a7 20.1003 intended for ultimate disposal at a land disposal facility licensed under part 61 of this chapter must document the information required on the NRC's Uniform Low-Level Radioactive Waste Manifest and transfer this recorded manifest information to the intended consignee in accordance with appendix G to this part."], ["10:10:1.0.1.1.16.11.76.7", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "K", "Subpart K\u2014Waste Disposal", "", "\u00a7 20.2007 Compliance with environmental and health protection regulations.", "NRC", "", "", "", "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."], ["10:10:1.0.1.1.16.11.76.8", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "K", "Subpart K\u2014Waste Disposal", "", "\u00a7 20.2008 Disposal of certain byproduct material.", "NRC", "", "", "[72 FR 55922, Oct. 1, 2007]", "(a) Licensed material as defined in paragraphs (3) and (4) of the definition of  Byproduct material  set forth in \u00a7 20.1003 may be disposed of in accordance with part 61 of this chapter, even though it is not defined as low-level radioactive waste. Therefore, any licensed byproduct material being disposed of at a facility, or transferred for ultimate disposal at a facility licensed under part 61 of this chapter, must meet the requirements of \u00a7 20.2006.\n\n(b) A licensee may dispose of byproduct material, as defined in paragraphs (3) and (4) of the definition of  Byproduct material  set forth in \u00a7 20.1003, at a disposal facility authorized to dispose of such material in accordance with any Federal or State solid or hazardous waste law, including the Solid Waste Disposal Act, as authorized under the Energy Policy Act of 2005."], ["10:10:1.0.1.1.16.12.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2101 General provisions.", "NRC", "", "", "[56 FR 23404, May 21, 1991, as amended at 60 FR 15663, Mar. 27, 1995; 63 FR 39483, July 23, 1998]", "(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.\n\n(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.\n\n(c) Not withstanding the requirements of paragraph (a) of this section, when recording information on shipment manifests, as required in \u00a7 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.\n\n(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)."], ["10:10:1.0.1.1.16.12.76.10", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2110 Form of records.", "NRC", "", "", "", "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."], ["10:10:1.0.1.1.16.12.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2102 Records of radiation protection programs.", "NRC", "", "", "", "(a) Each licensee shall maintain records of the radiation protection program, including:\n\n(1) The provisions of the program; and\n\n(2) Audits and other reviews of program content and implementation.\n\n(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."], ["10:10:1.0.1.1.16.12.76.3", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2103 Records of surveys.", "NRC", "", "", "[56 FR 23404, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995; 66 FR 64737, Dec. 14, 2001]", "(a) Each licensee shall maintain records showing the results of surveys and calibrations required by \u00a7\u00a7 20.1501 and 20.1906(b). The licensee shall retain these records for 3 years after the record is made.\n\n(b) The licensee shall retain each of the following records until the Commission terminates each pertinent license requiring the record:\n\n(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\n\n(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\n\n(3) Records showing the results of air sampling, surveys, and bioassays required pursuant to \u00a7 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\n\n(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."], ["10:10:1.0.1.1.16.12.76.4", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2104 Determination of prior occupational dose.", "NRC", "", "", "[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]", "(a) For each individual who is likely to receive an annual occupational dose requiring monitoring under \u00a7 20.1502, the licensee shall determine the occupational radiation dose received during the current year.\n\n(b) Prior to permitting an individual to participate in a planned special exposure, the licensee shall determine\u2014\n\n(1) The internal and external doses from all previous planned special exposures; and\n\n(2) All doses in excess of the limits (including doses received during accidents and emergencies) received during the lifetime of the individual.\n\n(c) In complying with the requirements of paragraphs (a) or (b) of this section, a licensee may\u2014\n\n(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;\n\n(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\n\n(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.\n\n(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. \n 4 \n   The form or record must show each period in which the individual received occupational exposure to radiation or radioactive material and must be signed by the individual who received the exposure. For each period for which the licensee obtains reports, the licensee shall use the dose shown in the report in preparing the NRC Form 4. For any period in which the licensee does not obtain a report, the licensee shall place a notation on the NRC Form 4 indicating the periods of time for which data are not available.\n\n4  Licensees are not required to partition historical dose between external dose equivalent(s) and internal committed dose equivalent(s). Further, occupational exposure histories obtained and recorded on NRC Form 4 before January 1, 1994, might not have included effective dose equivalent, but may be used in the absence of specific information on the intake of radionuclides by the individual.\n\n(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\u2014\n\n(1) In establishing administrative controls under \u00a7 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\n\n(2) That the individual is not available for planned special exposures.\n\n(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."], ["10:10:1.0.1.1.16.12.76.5", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2105 Records of planned special exposures.", "NRC", "", "", "", "(a) For each use of the provisions of \u00a7 20.1206 for planned special exposures, the licensee shall maintain records that describe\u2014\n\n(1) The exceptional circumstances requiring the use of a planned special exposure; and\n\n(2) The name of the management official who authorized the planned special exposure and a copy of the signed authorization; and\n\n(3) What actions were necessary; and\n\n(4) Why the actions were necessary; and\n\n(5) How doses were maintained ALARA; and\n\n(6) What individual and collective doses were expected to result, and the doses actually received in the planned special exposure.\n\n(b) The licensee shall retain the records until the Commission terminates each pertinent license requiring these records."], ["10:10:1.0.1.1.16.12.76.6", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2106 Records of individual monitoring results.", "NRC", "", "", "[56 FR 23404, May 21, 1991, as amended at 60 FR 20186, Apr. 25, 1995; 63 FR 39483, July 23, 1998]", "(a)  Recordkeeping requirement.  Each licensee shall maintain records of doses received by all individuals for whom monitoring was required pursuant to \u00a7 20.1502, and records of doses received during planned special exposures, accidents, and emergency conditions. These records \n 5 \n   must include, when applicable\u2014\n\n5  Assessments of dose equivalent and records made using units in effect before the licensee's adoption of this part need not be changed.\n\n(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;\n\n(2) The estimated intake of radionuclides (see \u00a7 20.1202);\n\n(3) The committed effective dose equivalent assigned to the intake of radionuclides;\n\n(4) The specific information used to assess the committed effective dose equivalent pursuant to \u00a7 20.1204 (a) and (c), and when required by \u00a7 20.1502;\n\n(5) The total effective dose equivalent when required by \u00a7 20.1202; and\n\n(6) The total of the deep-dose equivalent and the committed dose to the organ receiving the highest total dose.\n\n(b)  Recordkeeping frequency.  The licensee shall make entries of the records specified in paragraph (a) of this section at least annually.\n\n(c)  Recordkeeping format.  The licensee shall maintain the records specified in paragraph (a) of this section on NRC Form 5, in accordance with the instructions for NRC Form 5, or in clear and legible records containing all the information required by NRC Form 5.\n\n(d)  Privacy protection.  The records required under this section should be protected from public disclosure because of their personal privacy nature. These records are protected by most State privacy laws and, when transferred to the NRC, are protected by the Privacy Act of 1974, Public Law 93-579, 5 U.S.C. 552a, and the Commission's regulations in 10 CFR part 9.\n\n(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.\n\n(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."], ["10:10:1.0.1.1.16.12.76.7", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2107 Records of dose to individual members of the public.", "NRC", "", "", "", "(a) Each licensee shall maintain records sufficient to demonstrate compliance with the dose limit for individual members of the public (see \u00a7 20.1301).\n\n(b) The licensee shall retain the records required by paragraph (a) of this section until the Commission terminates each pertinent license requiring the record."], ["10:10:1.0.1.1.16.12.76.8", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2108 Records of waste disposal.", "NRC", "", "", "[56 FR 23404, May 21, 1991, as amended at 60 FR 20186, Apr. 25, 1995; 61 FR 24673, May 16, 1996]", "(a) Each licensee shall maintain records of the disposal of licensed materials made under \u00a7\u00a7 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. \n 6\n\n6  A previous \u00a7 20.304 permitted burial of small quantities of licensed materials in soil before January 28, 1981, without specific Commission authorization.\n\n(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 \u00a7\u00a7 30.51, 40.61, 70.51, and 72.80 for activities licensed under these parts."], ["10:10:1.0.1.1.16.12.76.9", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "L", "Subpart L\u2014Records", "", "\u00a7 20.2109 [Reserved]", "NRC", "", "", "", ""], ["10:10:1.0.1.1.16.13.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "M", "Subpart M\u2014Reports", "", "\u00a7 20.2201 Reports of theft or loss of licensed material.", "NRC", "", "", "[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]", "(a)  Telephone reports.  (1) Each licensee shall report by telephone as follows:\n\n(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\n\n(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.\n\n(2) Reports must be made as follows:\n\n(i) Licensees having an installed Emergency Notification System shall make the reports to the NRC Operations Center in accordance with \u00a7 50.72 of this chapter, and\n\n(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.\n\n(b)  Written reports.  (1) Each licensee required to make a report under paragraph (a) of this section shall, within 30 days after making the telephone report, make a written report setting forth the following information:\n\n(i) A description of the licensed material involved, including kind, quantity, and chemical and physical form; and\n\n(ii) A description of the circumstances under which the loss or theft occurred; and\n\n(iii) A statement of disposition, or probable disposition, of the licensed material involved; and\n\n(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\n\n(v) Actions that have been taken, or will be taken, to recover the material; and\n\n(vi) Procedures or measures that have been, or will be, adopted to ensure against a recurrence of the loss or theft of licensed material.\n\n(2) Reports must be made as follows:\n\n(i) For holders of an operating license for a nuclear power plant, the events included in paragraph (b) of this section must be reported in accordance with the procedures described in \u00a7 50.73(b), (c), (d), (e), and (g) of this chapter and must include the information required in paragraph (b)(1) of this section, and\n\n(ii) All other licensees shall make reports to the Administrator of the appropriate NRC Regional Office listed in appendix D to part 20.\n\n(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 \u00a7\u00a7 30.55(c), 37.57, 37.81, 40.64(c), 50.72, 50.73, 70.52, 73.27(b), 73.67(e)(3)(vii), 73.67(g)(3)(iii), 73.1205, or 150.19(c) of this chapter.\n\n(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.\n\n(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."], ["10:10:1.0.1.1.16.13.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "M", "Subpart M\u2014Reports", "", "\u00a7 20.2202 Notification of incidents.", "NRC", "", "", "[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]", "(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\u2014\n\n(1) An individual to receive\u2014\n\n(i) A total effective dose equivalent of 25 rems (0.25 Sv) or more; or\n\n(ii) A lens dose equivalent of 75 rems (0.75 Sv) or more; or\n\n(iii) A shallow-dose equivalent to the skin or extremities of 250 rads (2.5 Gy) or more; or\n\n(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).\n\n(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:\n\n(1) An individual to receive, in a period of 24 hours\u2014\n\n(i) A total effective dose equivalent exceeding 5 rems (0.05 Sv); or\n\n(ii) A lens dose equivalent exceeding 15 rems (0.15 Sv); or\n\n(iii) A shallow-dose equivalent to the skin or extremities exceeding 50 rems (0.5 Sv); or\n\n(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).\n\n(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.\n\n(d) Reports made by licensees in response to the requirements of this section must be made as follows:\n\n(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 10 CFR 50.72; and\n\n(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.\n\n(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 \u00a7 20.2204."], ["10:10:1.0.1.1.16.13.76.3", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "M", "Subpart M\u2014Reports", "", "\u00a7 20.2203 Reports of exposures, radiation levels, and concentrations of radioactive material exceeding the constraints or limits.", "NRC", "", "", "[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]", "(a)  Reportable events.  In addition to the notification required by \u00a7 20.2202, each licensee shall submit a written report within 30 days after learning of any of the following occurrences:\n\n(1) Any incident for which notification is required by \u00a7 20.2202; or\n\n(2) Doses in excess of any of the following:\n\n(i) The occupational dose limits for adults in \u00a7 20.1201; or\n\n(ii) The occupational dose limits for a minor in \u00a7 20.1207; or\n\n(iii) The limits for an embryo/fetus of a declared pregnant woman in \u00a7 20.1208; or\n\n(iv) The limits for an individual member of the public in \u00a7 20.1301; or\n\n(v) Any applicable limit in the license; or\n\n(vi) The ALARA constraints for air emissions established under \u00a7 20.1101(d); or\n\n(3) Levels of radiation or concentrations of radioactive material in\u2014\n\n(i) A restricted area in excess of any applicable limit in the license; or\n\n(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 \u00a7 20.1301); or\n\n(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.\n\n(b)  Contents of reports.  (1) Each report required by paragraph (a) of this section must describe the extent of exposure of individuals to radiation and radioactive material, including, as appropriate:\n\n(i) Estimates of each individual's dose; and\n\n(ii) The levels of radiation and concentrations of radioactive material involved; and\n\n(iii) The cause of the elevated exposures, dose rates, or concentrations; and\n\n(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.\n\n(2) Each report filed pursuant to paragraph (a) of this section must include for each occupationally overexposed \n 1 \n   individual: the name, Social Security account number, and date of birth. The report must be prepared so that this information is stated in a separate and detachable part of the report and must be clearly labeled \u201cPrivacy Act Information: Not for Public Disclosure.\u201d\n\n1  With respect to the limit for the embryo/fetus (\u00a7 20.1208), the identifiers should be those of the declared pregnant woman.\n\n(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 in accordance with the procedures described in \u00a7\u00a7 50.73(b), (c), (d), (e), and (g) of this chapter, and must include the information required by paragraph (b) of this section. Occurrences reported in accordance with \u00a7 50.73 of this chapter need not be reported by a duplicate report under paragraph (a) of this section.\n\n(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;  by e-mail to  MSHD.Resource@nrc.gov;  or by writing the Office of the Chief Information Officer, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. A copy should be sent to the appropriate NRC Regional Office listed in appendix D to this part."], ["10:10:1.0.1.1.16.13.76.4", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "M", "Subpart M\u2014Reports", "", "\u00a7 20.2204 Reports of planned special exposures.", "NRC", "", "", "[56 FR 23406, May 21, 1991, as amended at 60 FR 20186, Apr. 25, 1995]", "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 \u00a7 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 \u00a7 20.2105."], ["10:10:1.0.1.1.16.13.76.5", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "M", "Subpart M\u2014Reports", "", "\u00a7 20.2205 Reports to individuals of exceeding dose limits.", "NRC", "", "", "[72 FR 68059, Dec. 4, 2007]", "When a licensee is required by \u00a7\u00a7 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."], ["10:10:1.0.1.1.16.13.76.6", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "M", "Subpart M\u2014Reports", "", "\u00a7 20.2206 Reports of individual monitoring.", "NRC", "", "", "[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]", "(a) This section applies to each person licensed by the Commission to\u2014\n\n(1) Operate a nuclear reactor designed to produce electrical or heat energy pursuant to \u00a7 50.21(b) or \u00a7 50.22 of this chapter or a testing facility as defined in \u00a7 50.2 of this chapter; or\n\n(2) Possess or use byproduct material for purposes of radiography pursuant to parts 30 and 34 of this chapter; or\n\n(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\n\n(4) Possess high-level radioactive waste at a geologic repository operations area pursuant to part 60 or 63 of this chapter; or\n\n(5) Possess spent fuel in an independent spent fuel storage installation (ISFSI) pursuant to part 72 of this chapter; or\n\n(6) Receive radioactive waste from other persons for disposal under part 61 of this chapter; or\n\n(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:\n\n1  The Commission may require as a license condition, or by rule, regulation, or order pursuant to \u00a7 20.2302, reports from licensees who are licensed to use radionuclides not on this list, in quantities sufficient to cause comparable radiation levels.\n\n(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 \u00a7 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.\n\n(c) The licensee shall file the report required by \u00a7 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 \u00a7 20.1007 or via the REIRS Web site at  http://www.reirs.com."], ["10:10:1.0.1.1.16.13.76.7", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "M", "Subpart M\u2014Reports", "", "\u00a7 20.2207 Reports of transactions involving nationally tracked sources.", "NRC", "", "", "[71 FR 65707, Nov. 8, 2006, as amended at 72 FR 59163, Oct. 19, 2007; 86 FR 43401, Aug. 9, 2021]", "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.\n\n(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:\n\n(1) The name, address, and license number of the reporting licensee;\n\n(2) The name of the individual preparing the report;\n\n(3) The manufacturer, model, and serial number of the source;\n\n(4) The radioactive material in the source;\n\n(5) The initial source strength in becquerels (curies) at the time of manufacture; and\n\n(6) The manufacture date of the source.\n\n(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:\n\n(1) The name, address, and license number of the reporting licensee;\n\n(2) The name of the individual preparing the report;\n\n(3) The name and license number of the recipient facility and the shipping address;\n\n(4) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;\n\n(5) The radioactive material in the source;\n\n(6) The initial or current source strength in becquerels (curies);\n\n(7) The date for which the source strength is reported;\n\n(8) The shipping date;\n\n(9) The estimated arrival date; and\n\n(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.\n\n(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:\n\n(1) The name, address, and license number of the reporting licensee;\n\n(2) The name of the individual preparing the report;\n\n(3) The name, address, and license number of the person that provided the source;\n\n(4) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;\n\n(5) The radioactive material in the source;\n\n(6) The initial or current source strength in becquerels (curies);\n\n(7) The date for which the source strength is reported;\n\n(8) The date of receipt; and\n\n(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.\n\n(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:\n\n(1) The name, address, and license number of the reporting licensee;\n\n(2) The name of the individual preparing the report;\n\n(3) The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;\n\n(4) The radioactive material in the source;\n\n(5) The initial or current source strength in becquerels (curies);\n\n(6) The date for which the source strength is reported;\n\n(7) The disassemble date of the source.\n\n(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:\n\n(1) The name, address, and license number of the reporting licensee;\n\n(2) The name of the individual preparing the report;\n\n(3) The waste manifest number;\n\n(4) The container identification with the nationally tracked source.\n\n(5) The date of disposal; and\n\n(6) The method of disposal.\n\n(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:\n\n(1) The on-line National Source Tracking System;\n\n(2) Electronically using a computer-readable format;\n\n(3) By facsimile;\n\n(4) By mail to the address on the National Source Tracking Transaction Report Form (NRC Form 748); or\n\n(5) By telephone with followup by facsimile or mail.\n\n(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."], ["10:10:1.0.1.1.16.14.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "N", "Subpart N\u2014Exemptions and Additional Requirements", "", "\u00a7 20.2301 Applications for exemptions.", "NRC", "", "", "", "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."], ["10:10:1.0.1.1.16.14.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "N", "Subpart N\u2014Exemptions and Additional Requirements", "", "\u00a7 20.2302 Additional requirements.", "NRC", "", "", "", "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."], ["10:10:1.0.1.1.16.15.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "O", "Subpart O\u2014Enforcement", "", "\u00a7 20.2401 Violations.", "NRC", "", "", "[56 FR 23408, May 21, 1991; 56 FR 61352, Dec. 3, 1991, as amended at 57 FR 55071, Nov. 24, 1992]", "(a) The Commission may obtain an injunction or other court order to prevent a violation of the provisions of\u2014\n\n(1) The Atomic Energy Act of 1954, as amended;\n\n(2) Title II of the Energy Reorganization Act of 1974, as amended; or\n\n(3) A regulation or order issued pursuant to those Acts.\n\n(b) The Commission may obtain a court order for the payment of a civil penalty imposed under section 234 of the Atomic Energy Act:\n\n(1) For violations of\u2014\n\n(i) Sections 53, 57, 62, 63, 81, 82, 101, 103, 104, 107 or 109 of the Atomic Energy Act of 1954, as amended;\n\n(ii) Section 206 of the Energy Reorganization Act;\n\n(iii) Any rule, regulation, or order issued pursuant to the sections specified in paragraph (b)(1)(i) of this section; and\n\n(iv) Any term, condition, or limitation of any license issued under the sections specified in paragraph (b)(1)(i) of this section.\n\n(2) For any violation for which a license may be revoked under Section 186 of the Atomic Energy Act of 1954, as amended."], ["10:10:1.0.1.1.16.15.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "O", "Subpart O\u2014Enforcement", "", "\u00a7 20.2402 Criminal penalties.", "NRC", "", "", "[57 FR 55071, Nov. 24, 1992, as amended at 62 FR 39089, July 21, 1997]", "(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 \u00a7\u00a7 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.\n\n(b) The regulations in \u00a7\u00a7 20.1001 through 20.2402 that are not issued under Sections 161b, 161i, or 161o for the purposes of Section 223 are as follows: \u00a7\u00a7 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."], ["10:10:1.0.1.1.16.2.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "B", "Subpart B\u2014Radiation Protection Programs", "", "\u00a7 20.1101 Radiation protection programs.", "NRC", "", "", "[56 FR 23396, May 21, 1991, as amended at 61 FR 65127, Dec. 10, 1996; 63 FR 39482, July 23, 1998]", "(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 \u00a7 20.2102 for recordkeeping requirements relating to these programs.)\n\n(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).\n\n(c) The licensee shall periodically (at least annually) review the radiation protection program content and implementation.\n\n(d) To implement the ALARA requirements of \u00a7 20.1101 (b), and notwithstanding the requirements in \u00a7 20.1301 of this part, 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 \u00a7 50.34a, 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 \u00a7 20.2203 and promptly take appropriate corrective action to ensure against recurrence."], ["10:10:1.0.1.1.16.3.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "C", "Subpart C\u2014Occupational Dose Limits", "", "\u00a7 20.1201 Occupational dose limits for adults.", "NRC", "", "", "[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]", "(a) The licensee shall control the occupational dose to individual adults, except for planned special exposures under \u00a7 20.1206, to the following dose limits.\n\n(1) An annual limit, which is the more limiting of\u2014\n\n(i) The total effective dose equivalent being equal to 5 rems (0.05 Sv); or\n\n(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).\n\n(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:\n\n(i) A lens dose equivalent of 15 rems (0.15 Sv), and\n\n(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.\n\n(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 \u00a7 20.1206(e)(1)) and during the individual's lifetime (see \u00a7 20.1206(e)(2)).\n\n(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.\n\n(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 \u00a7 20.2106) and to demonstrate compliance with the occupational dose limits.\n\n(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).\n\n(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 \u00a7 20.2104(e))."], ["10:10:1.0.1.1.16.3.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "C", "Subpart C\u2014Occupational Dose Limits", "", "\u00a7 20.1202 Compliance with requirements for summation of external and internal doses.", "NRC", "", "", "[56 FR 23396, May 21, 1991, as amended at 57 FR 57878, Dec. 8, 1992]", "(a) If the licensee is required to monitor under both \u00a7\u00a7 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 \u00a7 20.1502(a) or only under \u00a7 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.\n\nThe 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.)\n\n(b)  Intake by inhalation.  If the only intake of radionuclides is by inhalation, the total effective dose equivalent limit is not exceeded if the sum of the deep-dose equivalent divided by the total effective dose equivalent limit, and one of the following, does not exceed unity:\n\n(1) The sum of the fractions of the inhalation ALI for each radionuclide, or\n\n(2) The total number of derived air concentration-hours (DAC-hours) for all radionuclides divided by 2,000, or\n\n(3) The sum of the calculated committed effective dose equivalents to all significantly irradiated \n 1 \n   organs or tissues (T) calculated from bioassay data using appropriate biological models and expressed as a fraction of the annual limit.\n\n1  An organ or tissue is deemed to be significantly irradiated if, for that organ or tissue, the product of the weighting factor, w T , and the committed dose equivalent, H T,50 , per unit intake is greater than 10 percent of the maximum weighted value of H T,50 , ( i.e. , W T  H T,50 ) per unit intake for any organ or tissue.\n\n(c)  Intake by oral ingestion.  If the occupationally exposed individual also receives an intake of radionuclides by oral ingestion greater than 10 percent of the applicable oral ALI, the licensee shall account for this intake and include it in demonstrating compliance with the limits.\n\n(d)  Intake through wounds or absorption through skin.  The licensee shall evaluate and, to the extent practical, account for intakes through wounds or skin absorption.\n\nThe intake through intact skin has been included in the calculation of DAC for hydrogen-3 and does not need to be further evaluated."], ["10:10:1.0.1.1.16.3.76.3", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "C", "Subpart C\u2014Occupational Dose Limits", "", "\u00a7 20.1203 Determination of external dose from airborne radioactive material.", "NRC", "", "", "[56 FR 23396, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995; 63 FR 39482, July 23, 1998]", "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).\n\nAirborne 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."], ["10:10:1.0.1.1.16.3.76.4", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "C", "Subpart C\u2014Occupational Dose Limits", "", "\u00a7 20.1204 Determination of internal exposure.", "NRC", "", "", "[56 FR 23396, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995]", "(a) For purposes of assessing dose used to determine compliance with occupational dose equivalent limits, the licensee shall, when required under \u00a7 20.1502, take suitable and timely measurements of\u2014\n\n(1) Concentrations of radioactive materials in air in work areas; or\n\n(2) Quantities of radionuclides in the body; or\n\n(3) Quantities of radionuclides excreted from the body; or\n\n(4) Combinations of these measurements.\n\n(b) Unless respiratory protective equipment is used, as provided in \u00a7 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.\n\n(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\u2014\n\n(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\n\n(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\n\n(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.\n\n(d) If the licensee chooses to assess intakes of Class Y material using the measurements given in \u00a7 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 \u00a7\u00a7 20.2202 or 20.2203, in order to permit the licensee to make additional measurements basic to the assessments.\n\n(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\u2014\n\n(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\n\n(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.\n\n(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.\n\n(g) When a mixture of radionuclides in air exists, licensees may disregard certain radionuclides in the mixture if\u2014\n\n(1) The licensee uses the total activity of the mixture in demonstrating compliance with the dose limits in \u00a7 20.1201 and in complying with the monitoring requirements in \u00a7 20.1502(b), and\n\n(2) The concentration of any radionuclide disregarded is less than 10 percent of its DAC, and\n\n(3) The sum of these percentages for all of the radionuclides disregarded in the mixture does not exceed 30 percent.\n\n(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.\n\n(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 \u00a7 20.1201(a)(1)(ii) is met."], ["10:10:1.0.1.1.16.3.76.5", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "C", "Subpart C\u2014Occupational Dose Limits", "", "\u00a7 20.1205 [Reserved]", "NRC", "", "", "", ""], ["10:10:1.0.1.1.16.3.76.6", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "C", "Subpart C\u2014Occupational Dose Limits", "", "\u00a7 20.1206 Planned special exposures.", "NRC", "", "", "[56 FR 23396, May 21, 1991, as amended at 63 FR 39482, July 23, 1998]", "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 \u00a7 20.1201 provided that each of the following conditions is satisfied\u2014\n\n(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.\n\n(b) The licensee (and employer if the employer is not the licensee) specifically authorizes the planned special exposure, in writing, before the exposure occurs.\n\n(c) Before a planned special exposure, the licensee ensures that the individuals involved are\u2014\n\n(1) Informed of the purpose of the planned operation;\n\n(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\n\n(3) Instructed in the measures to be taken to keep the dose ALARA considering other risks that may be present.\n\n(d) Prior to permitting an individual to participate in a planned special exposure, the licensee ascertains prior doses as required by \u00a7 20.2104(b) during the lifetime of the individual for each individual involved.\n\n(e) Subject to \u00a7 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\u2014\n\n(1) The numerical values of any of the dose limits in \u00a7 20.1201(a) in any year; and\n\n(2) Five times the annual dose limits in \u00a7 20.1201(a) during the individual's lifetime.\n\n(f) The licensee maintains records of the conduct of a planned special exposure in accordance with \u00a7 20.2105 and submits a written report in accordance with \u00a7 20.2204.\n\n(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 \u00a7 20.1201(a) but is to be included in evaluations required by \u00a7 20.1206 (d) and (e)."], ["10:10:1.0.1.1.16.3.76.7", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "C", "Subpart C\u2014Occupational Dose Limits", "", "\u00a7 20.1207 Occupational dose limits for minors.", "NRC", "", "", "", "The annual occupational dose limits for minors are 10 percent of the annual dose limits specified for adult workers in \u00a7 20.1201."], ["10:10:1.0.1.1.16.3.76.8", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "C", "Subpart C\u2014Occupational Dose Limits", "", "\u00a7 20.1208 Dose equivalent to an embryo/fetus.", "NRC", "", "", "[56 FR 23396, May 21, 1991, as amended at 63 FR 39482, July 23, 1998]", "(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 \u00a7 20.2106.)\n\n(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.\n\n(c) The dose equivalent to the embryo/fetus is the sum of\u2014\n\n(1) The deep-dose equivalent to the declared pregnant woman; and\n\n(2) The dose equivalent to the embryo/fetus resulting from radionuclides in the embryo/fetus and radionuclides in the declared pregnant woman.\n\n(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."], ["10:10:1.0.1.1.16.4.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "D", "Subpart D\u2014Radiation Dose Limits for Individual Members of the Public", "", "\u00a7 20.1301 Dose limits for individual members of the public.", "NRC", "", "", "[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]", "(a) Each licensee shall conduct operations so that\u2014\n\n(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 \u00a7 35.75, from voluntary participation in medical research programs, and from the licensee's disposal of radioactive material into sanitary sewerage in accordance with \u00a7 20.2003, and\n\n(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 \u00a7 35.75, does not exceed 0.002 rem (0.02 millisievert) in any one hour.\n\n(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.\n\n(c) Notwithstanding paragraph (a)(1) of this section, a licensee may permit visitors to an individual who cannot be released, under \u00a7 35.75, to receive a radiation dose greater than 0.1 rem (1 mSv) if\u2014\n\n(1) The radiation dose received does not exceed 0.5 rem (5 mSv); and\n\n(2) The authorized user, as defined in 10 CFR Part 35, has determined before the visit that it is appropriate.\n\n(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:\n\n(1) Demonstration of the need for and the expected duration of operations in excess of the limit in paragraph (a) of this section;\n\n(2) The licensee's program to assess and control dose within the 0.5 rem (5 mSv) annual limit; and\n\n(3) The procedures to be followed to maintain the dose as low as is reasonably achievable.\n\n(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.\n\n(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."], ["10:10:1.0.1.1.16.4.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "D", "Subpart D\u2014Radiation Dose Limits for Individual Members of the Public", "", "\u00a7 20.1302 Compliance with dose limits for individual members of the public.", "NRC", "", "", "[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]", "(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 \u00a7 20.1301.\n\n(b) A licensee shall show compliance with the annual dose limit in \u00a7 20.1301 by\u2014\n\n(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\n\n(2) Demonstrating that\u2014\n\n(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\n\n(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.\n\n(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)."], ["10:10:1.0.1.1.16.5.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "E", "Subpart E\u2014Radiological Criteria for License Termination", "", "\u00a7 20.1401 General provisions and scope.", "NRC", "", "", "[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]", "(a) The criteria in this subpart apply to the decommissioning of facilities licensed under parts 30, 40, 50, 52, 60, 61, 63, 70, and 72 of this chapter, and release of part of a facility or site for unrestricted use in accordance with \u00a7 50.83 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.\n\n(b) The criteria in this subpart do not apply to sites which:\n\n(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);\n\n(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\n\n(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.\n\n(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 \u00a7 50.83 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.\n\n(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."], ["10:10:1.0.1.1.16.5.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "E", "Subpart E\u2014Radiological Criteria for License Termination", "", "\u00a7 20.1402 Radiological criteria for unrestricted use.", "NRC", "", "", "", "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."], ["10:10:1.0.1.1.16.5.76.3", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "E", "Subpart E\u2014Radiological Criteria for License Termination", "", "\u00a7 20.1403 Criteria for license termination under restricted conditions.", "NRC", "", "", "[62 FR 39088, July 21, 1997, as amended at 76 FR 35564, July 17, 2011]", "A site will be considered acceptable for license termination under restricted conditions if:\n\n(a) The licensee can demonstrate that further reductions in residual radioactivity necessary to comply with the provisions of \u00a7 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;\n\n(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;\n\n(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\u2014\n\n(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;\n\n(2) A statement of intent in the case of Federal, State, or local Government licensees, as described in \u00a7 30.35(f)(4) of this chapter; or\n\n(3) When a government entity is assuming custody and ownership of a site, an arrangement that is deemed acceptable by such governmental entity.\n\n(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 \u00a7\u00a7 30.36(d), 40.42(d), 50.82 (a) and (b), 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.\n\n(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\u2014\n\n(i) Whether provisions for institutional controls proposed by the licensee:\n\n(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;\n\n(B) Will be enforceable; and\n\n(C) Will not impose undue burdens on the local community or other affected parties.\n\n(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;\n\n(2) In seeking advice on the issues identified in \u00a7 20.1403(d)(1), the licensee shall provide for:\n\n(i) Participation by representatives of a broad cross section of community interests who may be affected by the decommissioning;\n\n(ii) An opportunity for a comprehensive, collective discussion on the issues by the participants represented; and\n\n(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\n\n(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\u2014\n\n(1) 100 mrem (1 mSv) per year; or\n\n(2) 500 mrem (5 mSv) per year provided that the licensee\u2014\n\n(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;\n\n(ii) Makes provisions for durable institutional controls;\n\n(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 \u00a7 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."], ["10:10:1.0.1.1.16.5.76.4", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "E", "Subpart E\u2014Radiological Criteria for License Termination", "", "\u00a7 20.1404 Alternate criteria for license termination.", "NRC", "", "", "[62 FR 39088, July 21, 1997, as amended at 76 FR 35564, July 17, 2011]", "(a) The Commission may terminate a license using alternate criteria greater than the dose criterion of \u00a7\u00a7 20.1402, 20.1403(b), and 20.1403(d)(1)(i)(A), if the licensee\u2014\n\n(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;\n\n(2) Has employed to the extent practical restrictions on site use according to the provisions of \u00a7 20.1403 in minimizing exposures at the site; and\n\n(3) Reduces doses to ALARA levels, taking into consideration any detriments such as traffic accidents expected to potentially result from decontamination and waste disposal.\n\n(4) Has submitted a decommissioning plan or License Termination Plan (LTP) to the Commission indicating the licensee's intent to decommission in accordance with \u00a7\u00a7 30.36(d), 40.42(d), 50.82 (a) and (b), 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:\n\n(i) Participation by representatives of a broad cross section of community interests who may be affected by the decommissioning;\n\n(ii) An opportunity for a comprehensive, collective discussion on the issues by the participants represented; and\n\n(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.\n\n(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.\n\n(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 \u00a7 20.1405."], ["10:10:1.0.1.1.16.5.76.5", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "E", "Subpart E\u2014Radiological Criteria for License Termination", "", "\u00a7 20.1405 Public notification and public participation.", "NRC", "", "", "", "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 \u00a7\u00a7 20.1403 or 20.1404, or whenever the Commission deems such notice to be in the public interest, the Commission shall:\n\n(a) Notify and solicit comments from:\n\n(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\n\n(2) The Environmental Protection Agency for cases where the licensee proposes to release a site pursuant to \u00a7 20.1404.\n\n(b) Publish a notice in the  Federal Register  and in a forum. such as local newspapers, letters to State of local organizations, or other appropriate forum, that is readily accessible to individuals in the vicinity of the site, and solicit comments from affected parties."], ["10:10:1.0.1.1.16.5.76.6", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "E", "Subpart E\u2014Radiological Criteria for License Termination", "", "\u00a7 20.1406 Minimization of contamination.", "NRC", "", "", "[72 FR 49485, Aug. 28, 2007, as amended at 76 FR 35564, June 17, 2011]", "(a) Applicants for licenses, other than early site permits and manufacturing licenses under part 52 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.\n\n(b) Applicants for standard design certifications, standard design approvals, and manufacturing licenses under part 52 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.\n\n(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."], ["10:10:1.0.1.1.16.6.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "F", "Subpart F\u2014Surveys and Monitoring", "", "\u00a7 20.1501 General.", "NRC", "", "", "[56 FR 23398, May 21, 1991, as amended at 63 FR 39482, July 23, 1998; 76 FR 35564, June 17, 2011]", "(a) Each licensee shall make or cause to be made, surveys of areas, including the subsurface, that\u2014\n\n(1) May be necessary for the licensee to comply with the regulations in this part; and\n\n(2) Are reasonable under the circumstances to evaluate\u2014\n\n(i) The magnitude and extent of radiation levels; and\n\n(ii) Concentrations or quantities of residual radioactivity; and\n\n(iii) The potential radiological hazards of the radiation levels and residual radioactivity detected.\n\n(b) Notwithstanding \u00a7 20.2103(a) of this part, 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 \u00a7\u00a7 30.35(g), 40.36(f), 50.75(g), 70.25(g), or 72.30(d), as applicable.\n\n(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.\n\n(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 \u00a7 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\u2014\n\n(1) Holding current personnel dosimetry accreditation from the National Voluntary Laboratory Accreditation Program (NVLAP) of the National Institute of Standards and Technology; and\n\n(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."], ["10:10:1.0.1.1.16.6.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "F", "Subpart F\u2014Surveys and Monitoring", "", "\u00a7 20.1502 Conditions requiring individual monitoring of external and internal occupational dose.", "NRC", "", "", "[56 FR 23398, May 21, 1991, as amended at 60 FR 20185, Apr. 25, 1995; 63 FR 39482, July 23, 1998]", "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\u2014\n\n(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\u2014\n\n(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 \u00a7 20.1201(a),\n\n(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);\n\n(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); \n 2 \n   and\n\n2  All of the occupational doses in \u00a7 20.1201 continue to be applicable to the declared pregnant worker as long as the embryo/fetus dose limit is not exceeded.\n\n(4) Individuals entering a high or very high radiation area.\n\n(b) Each licensee shall monitor (see \u00a7 20.1204) the occupational intake of radioactive material by and assess the committed effective dose equivalent to\u2014\n\n(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 \u00a7\u00a7 20.1001-20.2402;\n\n(2) Minors likely to receive, in 1 year, a committed effective dose equivalent in excess of 0.1 rem (1 mSv); and\n\n(3) Declared pregnant women likely to receive, during the entire pregnancy, a committed effective dose equivalent in excess of 0.1 rem (1 mSv)."], ["10:10:1.0.1.1.16.7.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "G", "Subpart G\u2014Control of Exposure From External Sources in Restricted Areas", "", "\u00a7 20.1601 Control of access to high radiation areas.", "NRC", "", "", "", "(a) The licensee shall ensure that each entrance or access point to a high radiation area has one or more of the following features\u2014\n\n(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;\n\n(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\n\n(3) Entryways that are locked, except during periods when access to the areas is required, with positive control over each individual entry.\n\n(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.\n\n(c) A licensee may apply to the Commission for approval of alternative methods for controlling access to high radiation areas.\n\n(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.\n\n(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\u2014\n\n(1) The packages do not remain in the area longer than 3 days; and\n\n(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.\n\n(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."], ["10:10:1.0.1.1.16.7.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "G", "Subpart G\u2014Control of Exposure From External Sources in Restricted Areas", "", "\u00a7 20.1602 Control of access to very high radiation areas.", "NRC", "", "", "", "In addition to the requirements in \u00a7 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."], ["10:10:1.0.1.1.16.8.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "H", "Subpart H\u2014Respiratory Protection and Controls To Restrict Internal Exposure in Restricted Areas", "", "\u00a7 20.1701 Use of process or other engineering controls.", "NRC", "", "", "[64 FR 54556, Oct. 7, 1999]", "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."], ["10:10:1.0.1.1.16.8.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "H", "Subpart H\u2014Respiratory Protection and Controls To Restrict Internal Exposure in Restricted Areas", "", "\u00a7 20.1702 Use of other controls.", "NRC", "", "", "[64 FR 54556, Oct. 7, 1999]", "(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\u2014\n\n(1) Control of access;\n\n(2) Limitation of exposure times;\n\n(3) Use of respiratory protection equipment; or\n\n(4) Other controls.\n\n(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."], ["10:10:1.0.1.1.16.8.76.3", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "H", "Subpart H\u2014Respiratory Protection and Controls To Restrict Internal Exposure in Restricted Areas", "", "\u00a7 20.1703 Use of individual respiratory protection equipment.", "NRC", "", "", "[64 FR 54557, Oct. 7, 1999, as amended at 67 FR 77652, Dec. 19, 2002]", "If the licensee assigns or permits the use of respiratory protection equipment to limit the intake of radioactive material,\n\n(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.\n\n(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.\n\n(c) The licensee shall implement and maintain a respiratory protection program that includes:\n\n(1) Air sampling sufficient to identify the potential hazard, permit proper equipment selection, and estimate doses;\n\n(2) Surveys and bioassays, as necessary, to evaluate actual intakes;\n\n(3) Testing of respirators for operability (user seal check for face sealing devices and functional check for others) immediately prior to each use;\n\n(4) Written procedures regarding\u2014\n\n(i) Monitoring, including air sampling and bioassays;\n\n(ii) Supervision and training of respirator users;\n\n(iii) Fit testing;\n\n(iv) Respirator selection;\n\n(v) Breathing air quality;\n\n(vi) Inventory and control;\n\n(vii) Storage, issuance, maintenance, repair, testing, and quality assurance of respiratory protection equipment;\n\n(viii) Recordkeeping; and\n\n(ix) Limitations on periods of respirator use and relief from respirator use;\n\n(5) Determination by a physician that the individual user is medically fit to use respiratory protection equipment:\n\n(i) Before the initial fitting of a face sealing respirator;\n\n(ii) Before the first field use of non-face sealing respirators, and\n\n(iii) Either every 12 months thereafter, or periodically at a frequency determined by a physician.\n\n(6) Fit testing, with fit factor \u226510 times the APF for negative pressure devices, and a fit factor \u2265500 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.\n\n(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.\n\n(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.\n\n(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.\n\n(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, \u201cCommodity Specification for Air,\u201d 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\u2014\n\n(1) Oxygen content (v/v) of 19.5-23.5%;\n\n(2) Hydrocarbon (condensed) content of 5 milligrams per cubic meter of air or less;\n\n(3) Carbon monoxide (CO) content of 10 ppm or less;\n\n(4) Carbon dioxide content of 1,000 ppm or less; and\n\n(5) Lack of noticeable odor.\n\n(h) The licensee shall ensure that no objects, materials or substances, such as facial hair, or any conditions that interfere with the face\u2014facepiece 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.\n\n(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."], ["10:10:1.0.1.1.16.8.76.4", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "H", "Subpart H\u2014Respiratory Protection and Controls To Restrict Internal Exposure in Restricted Areas", "", "\u00a7 20.1704 Further restrictions on the use of respiratory protection equipment.", "NRC", "", "", "[64 FR 54557, Oct. 7, 1999]", "The Commission may impose restrictions in addition to the provisions of \u00a7\u00a7 20.1702, 20.1703, and Appendix A to Part 20, in order to:\n\n(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\n\n(b) Limit the extent to which a licensee may use respiratory protection equipment instead of process or other engineering controls."], ["10:10:1.0.1.1.16.8.76.5", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "H", "Subpart H\u2014Respiratory Protection and Controls To Restrict Internal Exposure in Restricted Areas", "", "\u00a7 20.1705 Application for use of higher assigned protection factors.", "NRC", "", "", "[64 FR 54557, Oct. 7, 1999]", "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\u2014\n\n(a) Describes the situation for which a need exists for higher protection factors; and\n\n(b) Demonstrates that the respiratory protection equipment provides these higher protection factors under the proposed conditions of use."], ["10:10:1.0.1.1.16.9.76.1", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "I", "Subpart I\u2014Storage and Control of Licensed Material", "", "\u00a7 20.1801 Security of stored material.", "NRC", "", "", "", "The licensee shall secure from unauthorized removal or access licensed materials that are stored in controlled or unrestricted areas."], ["10:10:1.0.1.1.16.9.76.2", 10, "Energy", "I", "", "20", "PART 20\u2014STANDARDS FOR PROTECTION AGAINST RADIATION", "I", "Subpart I\u2014Storage and Control of Licensed Material", "", "\u00a7 20.1802 Control of material not in storage.", "NRC", "", "", "", "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."]], "truncated": false, "filtered_table_rows_count": 72, "expanded_columns": [], "expandable_columns": [], "columns": ["section_id", "title_number", "title_name", "chapter", "subchapter", "part_number", "part_name", "subpart", "subpart_name", "section_number", "section_heading", "agency", "authority", "source_citation", "amendment_citations", "full_text"], "primary_keys": ["section_id"], "units": {}, "query": {"sql": "select section_id, title_number, title_name, chapter, subchapter, part_number, part_name, subpart, subpart_name, section_number, section_heading, agency, authority, source_citation, amendment_citations, full_text from cfr_sections where \"part_number\" = :p0 and \"title_number\" = :p1 order by section_id limit 101", "params": {"p0": "20", "p1": "10"}}, "facet_results": {"title_number": {"name": "title_number", "type": "column", "hideable": false, "toggle_url": "/openregs/cfr_sections.json?part_number=20&title_number=10", "results": [{"value": 10, "label": 10, "count": 72, "toggle_url": "https://www.pawtectors.org/openregs/cfr_sections.json?part_number=20", "selected": true}], "truncated": false}, "agency": {"name": "agency", "type": "column", "hideable": false, "toggle_url": "/openregs/cfr_sections.json?part_number=20&title_number=10", "results": [{"value": "NRC", "label": "NRC", "count": 72, "toggle_url": "https://www.pawtectors.org/openregs/cfr_sections.json?part_number=20&title_number=10&agency=NRC", "selected": false}], "truncated": false}, "part_number": {"name": "part_number", "type": "column", "hideable": false, "toggle_url": "/openregs/cfr_sections.json?part_number=20&title_number=10", "results": [{"value": "20", "label": "20", "count": 72, "toggle_url": "https://www.pawtectors.org/openregs/cfr_sections.json?title_number=10", "selected": true}], "truncated": false}}, "suggested_facets": [{"name": "subpart", "toggle_url": "https://www.pawtectors.org/openregs/cfr_sections.json?part_number=20&title_number=10&_facet=subpart"}, {"name": "subpart_name", "toggle_url": "https://www.pawtectors.org/openregs/cfr_sections.json?part_number=20&title_number=10&_facet=subpart_name"}], "next": null, "next_url": null, "private": false, "allow_execute_sql": true, "query_ms": 237.59563802741468, "source": "Federal Register API & Regulations.gov API", "source_url": "https://www.federalregister.gov/developers/api/v1", "license": "Public Domain (U.S. Government data)", "license_url": "https://www.regulations.gov/faq"}