R313.  Environmental Quality, Waste Management and Radiation Control, Radiation.
R313-15.  Standards for Protection Against Radiation.
R313-15-1.  Purpose, Authority and Scope.
	(1)  Rule R313-15 establishes standards for protection against ionizing radiation resulting from activities conducted pursuant to licenses issued by the Director.  These rules are issued pursuant to Subsections 19-3-104(4) and 19-3-104(7).
	(2)  The requirements of Rule R313-15 are designed to control the receipt, possession, use, transfer, and disposal of sources of radiation by any licensee or registrant so the total dose to an individual, including doses resulting from all sources of radiation other than background radiation, does not exceed the standards for protection against radiation prescribed in Rule R313-15.  However, nothing in Rule R313-15 shall be construed as limiting actions that may be necessary to protect health and safety.
	(3)  Except as specifically provided in other sections of these rules, Rule R313-15 applies to persons licensed or registered by the Director to receive, possess, use, transfer, or dispose of sources of radiation.  The limits in Rule R313-15 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 in accordance with Rule R313-32 (incorporating 10 CFR 35.75 by reference), or to exposure from voluntary participation in medical research programs.

R313-15-2.  Definitions.
	"Annual 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 0.05 Sv (5 rem) or a committed dose equivalent of 0.5 Sv (50 rem) to any individual organ or tissue. ALI values for intake by ingestion and by inhalation of selected radionuclides are given in Table I, Columns 1 and 2, of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference.
	"Air-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.
	"Assigned 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.
	"Atmosphere-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.
	"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 ten days, for Class W, Weeks, from ten to 100 days , and for Class Y, Years, of greater than 100 days.  For purposes of these rules, "lung class" and "inhalation class" are equivalent terms.
	"Constraint (dose constraint)" in accordance with 10 CFR 20.1003, (2010), means a value above which specified licensee actions are required.
	"Declared pregnant woman" means a woman who has voluntarily informed her employer, 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.
	"Demand 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.
	"Derived 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, results in an intake of one ALI.  For purposes of these rules, the condition of light work is an inhalation rate of 1.2 cubic meters of air per hour for 2,000 hours in a year.  DAC values are given in Table I, Column 3, of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference.
	"Derived air concentration-hour" (DAC-hour) means 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 or registrant may take 2,000 DAC-hours to represent one ALI, equivalent to a committed effective dose equivalent of 0.05 Sv (5 rem).
	"Disposable 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).
	"Dosimetry processor" means an individual or an organization that processes and evaluates individual monitoring devices in order to determine the radiation dose delivered to the monitoring devices.
	"Filtering 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.
	"Fit 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.
	"Fit test" means the use of a protocol to qualitatively or quantitatively evaluate the fit of a respirator on an individual.
	"Helmet" means a rigid respiratory inlet covering that also provides head protection against impact and penetration.
	"Hood" means a respiratory inlet covering that completely covers the head and neck and may also cover portions of the shoulders and torso.
	"Inhalation class", refer to "Class".
	"Labeled package" means a package 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 49 CFR 172.436 through 440, (2009).  Labeling of packages containing radioactive materials is required by the U.S. Department of Transportation if the amount and type of radioactive material exceeds the limits for an excepted quantity or article as defined and limited by U.S. Department of Transportation regulations 49 CFR 173.403 and 49 CFR 173.421 through 424, (2009).
	"Loose-fitting facepiece" means a respiratory inlet covering that is designed to form a partial seal with the face.
	"Lung class", refer to "Class".
	"Nationally 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 10 CFR 20.1001 to 20.2402 (2010), which is incorporated by reference.  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.
	"Negative 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.
	"Nonstochastic effect" means a health effect, 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.  For purposes of these rules, "deterministic effect" is an equivalent term.
	"Planned special exposure" means an infrequent exposure to radiation, separate from and in addition to the annual occupational dose limits.
	"Positive pressure respirator" means a respirator in which the pressure inside the respiratory inlet covering exceeds the ambient air pressure outside the respirator.
	"Powered 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.
	"Pressure 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.
	"Qualitative 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.
	"Quantitative fit test" (QNFT) means an assessment of the adequacy of respirator fit by numerically measuring the amount of leakage into the respirator.
	"Quarter" means a period of time equal to one-fourth of the year observed by the licensee, approximately 13 consecutive 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.
	"Reference Man" means a hypothetical aggregation of human physical and physiological characteristics determined by international consensus.  These characteristics may be used by researchers and public health employees to standardize results of experiments and to relate biological insult to a common base.  A description of the Reference Man is contained in the International Commission on Radiological Protection report, ICRP Publication 23, "Report of the Task Group on Reference Man."
	"Respiratory protective equipment" means an apparatus, such as a respirator, used to reduce an individual's intake of airborne radioactive materials.
	"Sanitary 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 or registrant.
	"Self-contained breathing apparatus" (SCBA) means an atmosphere-supplying respirator for which the breathing air source is designed to be carried by the user.
	"Stochastic effect" means a health effect that occurs 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.  For purposes of these rules, "probabilistic effect" is an equivalent term.
	"Supplied-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.
	"Tight-fitting facepiece" means a respiratory inlet covering that forms a complete seal with the face.
	"User 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.
	"Very 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 five Gy (500 rad) in one hour at one meter from a radiation source or one meter from any surface that the radiation penetrates.
	"Weighting factor" wT for an organ or tissue (T) means 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 wT are:

	TABLE

	ORGAN DOSE WEIGHTING FACTORS

             Organ or Tissue                  wT
               Gonads                         0.25
               Breast                         0.15
               Red bone marrow                0.12
               Lung                           0.12
               Thyroid                        0.03
               Bone surfaces                  0.03
               Remainder                      0.30(1)
               Whole Body                     1.00(2)

(1)  0.30 results from 0.06 for each of five "remainder"
organs, excluding the skin and the lens of the eye, that
receive the highest doses.
(2)  For the purpose of weighting the external whole body
dose, for adding it to the internal dose, a single weighting
factor, wT = 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.
	
R313-15-3.  Implementation.
	(1)  Any existing license or registration condition that is more restrictive than Rule R313-15 remains in force until there is an amendment or renewal of the license or registration.
	(2)  If a license or registration condition exempts a licensee or registrant from a provision of Rule R313-15 in effect on or before January 1, 1994, it also exempts the licensee or registrant from the corresponding provision of Rule R313-15.
	(3)  If a license or registration condition cites provisions of Rule R313-15 in effect prior to January 1, 1994, which do not correspond to any provisions of Rule R313-15, the license or registration condition remains in force until there is an amendment or renewal of the license or registration that modifies or removes this condition.

R313-15-101.  Radiation Protection Programs.
	(1)  Each licensee or registrant shall develop, document, and implement a radiation protection program sufficient to ensure compliance with the provisions of Rule R313-15.  See Section R313-15-1102 for recordkeeping requirements relating to these programs.
	(2)  The licensee or registrant 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).
	(3)  The licensee or registrant shall, at intervals not to exceed 12 months, review the radiation protection program content and implementation.
	(4)  To implement the ALARA requirements of Subsection R313-15-101(2), and notwithstanding the requirements in Section R313-15-301, a constraint on air emissions of radioactive material to the environment, excluding radon-222 and its decay products, shall be established by licensees or registrants 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 0.1 mSv (0.01 rem) per year from these emissions.  If a licensee or registrant subject to this requirement exceeds this dose constraint, the licensee or registrant shall report the exceedance as provided in Section R313-15-1203 and promptly take appropriate corrective action to ensure against recurrence.

R313-15-201.  Occupational Dose Limits for Adults.
	(1)  The licensee or registrant shall control the occupational dose to individual adults, except for planned special exposures pursuant to Section R313-15-206, to the following dose limits:
	(a)  An annual limit, which is the more limiting of:
	(i)  The total effective dose equivalent being equal to 0.05 Sv (5 rem); or
	(ii)  The sum of the deep dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye being equal to 0.50 Sv (50 rem).
	(b)  The annual limits to the lens of the eye, to the skin of the whole body, and to the skin of the extremities which are:
	(i)  A lens dose equivalent of 0.15 Sv (15 rem), and
	(ii)  A shallow dose equivalent of 0.50 Sv (50 rem) to the skin of the whole body or to the skin of any extremity.
	(2)  Doses received in excess of the annual limits, including doses received during accidents, emergencies, and planned special exposures, shall be subtracted from the limits for planned special exposures that the individual may receive during the current year and during the individual's lifetime. See Subsections R313-15-206(5)(a) and R313-15-206(5)(b).
	(3)  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 Director, U.S. Nuclear Regulatory Commission, or an Agreement State.  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 ten square centimeters of skin receiving the highest exposure.
	(a)  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; or
	(b)  When a protective apron is worn while working with medical fluoroscopic equipment and monitoring is conducted as specified in Subsection R313-15-502(1)(d), the effective dose equivalent for external radiation shall be determined as follows:
	(i)  When only one individual monitoring device is used and it is located at the neck outside the protective apron, and the reported dose exceeds 25 percent of the limit specified in Subsection R313-15-201(1), the reported deep dose equivalent value multiplied by 0.3 shall be the effective dose equivalent for external radiation; or
	(ii)  When individual monitoring devices are worn, both under the protective apron at the waist and outside the protective apron at the neck, the effective dose equivalent for external radiation shall be assigned the value of the sum of the deep dose equivalent reported for the individual monitoring device located at the waist under the protective apron multiplied by 1.5 and the deep dose equivalent reported for the individual monitoring device located at the neck outside the protective apron multiplied by 0.04.
	(4)  Derived air concentration (DAC) and annual limit on intake (ALI) values are specified in Table I of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference, and may be used to determine the individual's dose and to demonstrate compliance with the occupational dose limits.  See Section R313-15-1107.
	(5)  Notwithstanding the annual dose limits, the licensee shall limit the soluble uranium intake by an individual to ten milligrams in a week in consideration of chemical toxicity. See footnote 3, of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference.
	(6)  The licensee or registrant 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 Subsection R313-15-205(5).

R313-15-202.  Compliance with Requirements for Summation of External and Internal Doses.
	(1)  If the licensee or registrant is required to monitor pursuant to both Subsections R313-15-502(1) and R313-15-502(2), the licensee or registrant shall demonstrate compliance with the dose limits by summing external and internal doses.  If the licensee or registrant is required to monitor only pursuant to Subsection R313-15-502(1) or only pursuant to Subsection R313-15-502(2), then summation is not required to demonstrate compliance with the dose limits.  The licensee or registrant may demonstrate compliance with the requirements for summation of external and internal doses pursuant to Subsections R313-15-202(2), R313-15-202(3) and R313-15-202(4).  The dose equivalents for the lens of the eye, the skin, and the extremities are not included in the summation, but are subject to separate limits.
	(2)  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:
	(a)  The sum of the fractions of the inhalation ALI for each radionuclide, or
	(b)  The total number of derived air concentration-hours (DAC-hours) for all radionuclides divided by 2,000, or
	(c)  The sum of the calculated committed effective dose equivalents to all significantly irradiated organs or tissues (T) calculated from bioassay data using appropriate biological models and expressed as a fraction of the annual limit.  For purposes of this requirement, an organ or tissue is deemed to be significantly irradiated if, for that organ or tissue, the product of the weighting factors, wT, and the committed dose equivalent, HT,50, per unit intake is greater than ten percent of the maximum weighted value of HT,50, that is, wTHT,50, per unit intake for any organ or tissue.
	(3)  Intake by Oral Ingestion. If the occupationally exposed individual receives an intake of radionuclides by oral ingestion greater than ten percent of the applicable oral ALI, the licensee or registrant shall account for this intake and include it in demonstrating compliance with the limits.
	(4)  Intake through Wounds or Absorption through Skin.  The licensee or registrant shall evaluate and, to the extent practical, account for intakes through wounds or skin absorption.  The intake through intact skin has been included in the calculation of DAC for hydrogen-3 and does not need to be evaluated or accounted for pursuant to Subsection R313-15-202(4).

R313-15-203.  Determination of External Dose from Airborne Radioactive Material.
	(1)  Licensees or registrants 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 footnotes 1 and 2 of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference.
	(2)  Airborne radioactivity measurements and DAC values shall 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 shall be based upon measurements using instruments or individual monitoring devices.

R313-15-204.  Determination of Internal Exposure.
	(1)  For purposes of assessing dose used to determine compliance with occupational dose equivalent limits, the licensee or registrant shall, when required pursuant to Section R313-15-502, take suitable and timely measurements of:
	(a)  Concentrations of radioactive materials in air in work areas; or
	(b)  Quantities of radionuclides in the body; or
	(c)  Quantities of radionuclides excreted from the body; or
	(d)  Combinations of these measurements.
	(2)  Unless respiratory protective equipment is used, as provided in Section R313-15-703, or the assessment of intake is based on bioassays, the licensee or registrant shall assume that an individual inhales radioactive material at the airborne concentration in which the individual is present.
	(3)  When specific information on the physical and biochemical properties of the radionuclides taken into the body or the behavior of the material in an individual is known, the licensee or registrant may:
	(a)  Use that information to calculate the committed effective dose equivalent, and, if used, the licensee or registrant shall document that information in the individual's record; and
	(b)  Upon prior approval of the Director, adjust the DAC or ALI values to reflect the actual physical and chemical characteristics of airborne radioactive material, for example, aerosol size distribution or density; and
	(c)  Separately assess the contribution of fractional intakes of Class D, W, or Y compounds of a given radionuclide to the committed effective dose equivalent.  See Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference.
	(4)  If the licensee or registrant chooses to assess intakes of Class Y material using the measurements given in Subsections R313-15-204(1)(b) or R313-15-204(1)(c), the licensee or registrant may delay the recording and reporting of the assessments for periods up to seven months, unless otherwise required by Section R313-15-1202 or Section R313-15-1203.  This delay permits the licensee or registrant to make additional measurements basic to the assessments.
	(5)  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 shall be either:
	(a)  The sum of the ratios of the concentration to the appropriate DAC value, that is, D, W, or Y, from Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference, for each radionuclide in the mixture; or
	(b)  The ratio of the total concentration for all radionuclides in the mixture to the most restrictive DAC value for any radionuclide in the mixture.
	(6)  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 shall be the most restrictive DAC of any radionuclide in the mixture.
	(7)  When a mixture of radionuclides in air exists, a licensee or registrant may disregard certain radionuclides in the mixture if:
	(a)  The licensee or registrant uses the total activity of the mixture in demonstrating compliance with the dose limits in Section R313-15-201 and in complying with the monitoring requirements in Subsection R313-15-502(2), and
	(b)  The concentration of any radionuclide disregarded is less than ten percent of its DAC, and
	(c)  The sum of these percentages for all of the radionuclides disregarded in the mixture does not exceed 30 percent.
	(8)  When determining the committed effective dose equivalent, the following information may be considered:
	(a)  In order to calculate the committed effective dose equivalent, the licensee or registrant may assume that the inhalation of one ALI, or an exposure of 2,000 DAC-hours, results in a committed effective dose equivalent of 0.05 Sv (5 rem) for radionuclides that have their ALIs or DACs based on the committed effective dose equivalent.
	(b)  For an ALI and the associated DAC determined by the nonstochastic organ dose limit of 0.50 Sv (50 rem), the intake of radionuclides that would result in a committed effective dose equivalent of 0.05 Sv (5 rem), that is, the stochastic ALI, is listed in parentheses in Table I of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference.  The licensee or registrant may, as a simplifying assumption, use the stochastic ALI to determine committed effective dose equivalent.  However, if the licensee or registrant uses the stochastic ALI, the licensee or registrant shall also demonstrate that the limit in Subsection R313-15-201(1)(a)(ii) is met.

R313-15-205.  Determination of Prior Occupational Dose.
	(1)  For each individual likely to receive, in a year, an occupational dose requiring monitoring pursuant to Section R313-15-502, the licensee or registrant shall Determine the occupational radiation dose received during the current year; and
	(2)  Prior to permitting an individual to participate in a planned special exposure, the licensee or registrant shall determine:
	(a)  The internal and external doses from all previous planned special exposures; and
	(b)  All doses in excess of the limits, including doses received during accidents and emergencies, received during the lifetime of the individual.
	(3)  In complying with the requirements of Subsections R313-15-205(1) or (2), a licensee or registrant may:
	(a)  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 received during the current year;
	(b)  Attempt to obtain the records of cumulative occupational radiation dose.  A licensee or registrant may accept, as the record of cumulative radiation dose, an up-to-date form DWMRC-05 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 or registrant; and
	(c)  Obtain reports of the individual's dose equivalents 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 or registrant, by telephone, telegram, facsimile, other electronic media or letter.  The licensee or registrant shall request a written verification of the dose data if the authenticity of the transmitted report cannot be established.
	(4)  The licensee or registrant shall record the exposure history, as required by Subsection R313-15-205(1) or (2), on form DWMRC-05, or other clear and legible record, of all the information required on form DWMRC-05.  The form or record shall show each period in which the individual received occupational exposure to radiation or radioactive material and shall be signed by the individual who received the exposure.  For each period for which the licensee or registrant obtains reports, the licensee or registrant shall use the dose shown in the report in preparing form DWMRC-05 or equivalent. For any period in which the licensee or registrant does not obtain a report, the licensee or registrant shall place a notation on form DWMRC-05 or equivalent indicating the periods of time for which data are not available.
	(5)  For the purpose of complying with this requirement, licensees or registrants are not required to reevaluate the separate external dose equivalents and internal committed dose equivalents or intakes of radionuclides assessed pursuant to the rules in Rule R313-15 in effect before January 1, 1994.  Further, occupational exposure histories obtained and recorded on form DWMRC-05 or equivalent before January 1, 1994, would not have included effective dose equivalent, but may be used in the absence of specific information on the intake of radionuclides by the individual.
	(6)  If the licensee or registrant is unable to obtain a complete record of an individual's current and previously accumulated occupational dose, the licensee or registrant shall assume:
	(a)  In establishing administrative controls under Subsection R313-15-201(6) for the current year, that the allowable dose limit for the individual is reduced by 12.5 mSv (1.25 rem) for each quarter for which records were unavailable and the individual was engaged in activities that could have resulted in occupational radiation exposure; and
	(b)  That the individual is not available for planned special exposures.
	(7)  The licensee or registrant shall retain the records on form DWMRC-05 or equivalent until the Director terminates each pertinent license or registration requiring this record. The licensee or registrant shall retain records used in preparing form DWMRC-05 or equivalent for three years after the record is made.  This includes records required under the standards for protection against radiation in effect prior to January 1, 1994.

R313-15-206.  Planned Special Exposures.
	A licensee or registrant may authorize an adult worker to receive doses in addition to and accounted for separately from the doses received under the limits specified in Section R313-15-201 provided that each of the following conditions is satisfied:
	(1)  The licensee or registrant 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.
	(2)  The licensee or registrant, and employer if the employer is not the licensee or registrant, specifically authorizes the planned special exposure, in writing, before the exposure occurs.
	(3)  Before a planned special exposure, the licensee or registrant ensures that each individual involved is:
	(a)  Informed of the purpose of the planned operation; and
	(b)  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
	(c)  Instructed in the measures to be taken to keep the dose ALARA considering other risks that may be present.
	(4)  Prior to permitting an individual to participate in a planned special exposure, the licensee or registrant ascertains prior doses as required by Subsection R313-15-205(2) during the lifetime of the individual for each individual involved.
	(5)  Subject to Subsection R313-15-201(2), the licensee or registrant shall 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:
	(a)  The numerical values of any of the dose limits in Subsection R313-15-201(1) in any year; and
	(b)  Five times the annual dose limits in Subsection R313-15-201(1) during the individual's lifetime.
	(6)  The licensee or registrant maintains records of the conduct of a planned special exposure in accordance with Section R313-15-1106 and submits a written report in accordance with Section R313-15-1204.
	(7)  The licensee or registrant 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 shall not be considered in controlling future occupational dose of the individual pursuant to Subsection R313-15-201(1) but shall be included in evaluations required by Subsections R313-15-206(4) and R313-15-206(5).

R313-15-207.  Occupational Dose Limits for Minors.
	The annual occupational dose limits for minors are ten percent of the annual occupational dose limits specified for adult workers in Section R313-15-201.

R313-15-208.  Dose to an Embryo/Fetus.
	(1)  The licensee or registrant shall ensure that the dose equivalent to the embryo/fetus during the entire pregnancy, due to occupational exposure of a declared pregnant woman, does not exceed five mSv (0.5 rem).  See Section R313-15-1107 for recordkeeping requirements.
	(2)  The licensee or registrant 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 Subsection R313-15-208(1).
	(3)  The dose equivalent to an embryo/fetus is the sum of:
	(a)  The deep dose equivalent to the declared pregnant woman; and
	(b)  The dose equivalent resulting from radionuclides in the embryo/fetus and radionuclides in the declared pregnant woman.
	(4)  If the dose equivalent to the embryo/fetus is found to have exceeded five mSv (0.5 rem) or is within 0.5 mSv (0.05 rem) of this dose by the time the woman declares the pregnancy to the licensee or registrant, the licensee or registrant shall be deemed to be in compliance with Subsection R313-15-208(1) if the additional dose equivalent to the embryo/fetus does not exceed 0.50 mSv (0.05 rem) during the remainder of the pregnancy.

R313-15-301.  Dose Limits for Individual Members of the Public.
	(1)  Each licensee or registrant shall conduct operations so that:
	(a)  The total effective dose equivalent to individual members of the public from the licensed or registered operation does not exceed one mSv (0.1 rem) 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 Rule R313-32 (incorporating 10 CFR 35.75 by reference), from voluntary participation in medical research programs, and from the licensee's or registrant's disposal of radioactive material into sanitary sewerage in accordance with Section R313-15-1003; and
	(b)  The dose in any unrestricted area from external sources, exclusive of the dose contributions from patients administered radioactive material and released in accordance with Rule R313-32 (incorporating 10 CFR 35.75 by reference), does not exceed 0.02 mSv (0.002 rem) in any one hour; and
	(c)  Notwithstanding Subsection R313-15-301(1)(a), a licensee may permit visitors to an individual who cannot be released, under R313-32 (incorporating 10 CFR 35.75 by reference), to receive a radiation dose greater than one mSv (0.1 rem) if:
	(i)  The radiation dose received does not exceed five mSv (0.5 rem); and
	(ii)  The authorized user, as defined in R313-32, has determined before the visit that it is appropriate.; and
	(d)  The total effective dose equivalent to individual members of the public from infrequent exposure to radiation from radiation machines does not exceed 5 mSv (0.5 rem) in a year.
	(2)  If the licensee or registrant permits members of the public to have access to controlled areas, the limits for members of the public continue to apply to those individuals.
	(3)  A licensee, registrant, or an applicant for a license or registration may apply for prior Director authorization to operate up to an annual dose limit for an individual member of the public of five mSv (0.5 rem).  This application shall include the following information:
	(a)  Demonstration of the need for and the expected duration of operations in excess of the limit in Subsection R313-15-301(1); and
	(b)  The licensee's or registrant's program to assess and control dose within the five mSv (0.5 rem) annual limit; and
	(c)  The procedures to be followed to maintain the dose ALARA.
	(4)  In addition to the requirements of R313-15, a licensee subject to the provisions of the United States Environmental Protection Agency's generally applicable environmental radiation standards in 40 CFR 190 shall comply with those standards.
	(5)  The Director may impose additional restrictions on radiation levels in unrestricted areas and on the total quantity of radionuclides that a licensee or registrant may release in effluents in order to restrict the collective dose.

R313-15-302.  Compliance with Dose Limits for Individual Members of the Public.
	(1)  The licensee or registrant shall make or cause to be made 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 Section R313-15-301.
	(2)  A licensee or registrant shall show compliance with the annual dose limit in Section R313-15-301 by:
	(a)  Demonstrating by measurement or calculation that the total effective dose equivalent to the individual likely to receive the highest dose from the licensed or registered operation does not exceed the annual dose limit; or
	(b)  Demonstrating that:
	(i)  The annual average concentrations of radioactive material released in gaseous and liquid effluents at the boundary of the unrestricted area do not exceed the values specified in Table II of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference; and
	(ii)  If an individual were continuously present in an unrestricted area, the dose from external sources would not exceed 0.02 mSv (0.002 rem) in an hour and 0.50 mSv (0.05 rem) in a year.
	(3)  Upon approval from the Director, the licensee or registrant may adjust the effluent concentration values in Appendix B, Table II of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference, for members of the public, to take into account the actual physical and chemical characteristics of the effluents, such as, aerosol size distribution, solubility, density, radioactive decay equilibrium, and chemical form.

R313-15-401.  Radiological Criteria for License Termination - General Provisions.
	(1)  The criteria in Sections R313-15-401 through R313-15-406 apply to the decommissioning of facilities licensed under Rules R313-22 and R313-25, as well as other facilities subject to the Act.  For low-level waste disposal facilities (Rule R313-25), the criteria apply only to ancillary surface facilities that support radioactive waste disposal activities.
	(2)  The criteria in Sections R313-15-401 through R313-15-406 do not apply to sites which:
	(a)  Have been decommissioned prior to the effective date of the rule in accordance with criteria approved by the Director;
	(b)  Have previously submitted and received Director approval on a license termination plan or decommissioning plan; or
	(c)  Submit a sufficient license termination plan or decommissioning plan before the effective date of the rule with criteria approved by the Director.
	(3)  After a site has been decommissioned and the license terminated in accordance with the criteria in Sections R313-15-401 through R313-15-406, the Director will require additional cleanup only if, based on new information, the Director determines that the criteria in Sections R313-15-401 through R313-15-406 was not met and residual radioactivity remaining at the site could result in significant threat to public health and safety.
	(4)  When calculating the total effective dose equivalent to the average member of the critical group, the licensee shall determine the peak annual total effective dose equivalent dose expected within the first 1000 years after decommissioning.

R313-15-402.  Radiological Criteria for Unrestricted Use.
	A site will be considered acceptable for unrestricted use if the residual radioactivity that is distinguishable from background radiation results in a total effective dose equivalent to an average member of the critical group that does not exceed 0.25 mSv (0.025 rem) per year, including no greater than 0.04 mSv (0.004 rem) committed effective dose equivalent or total effective dose equivalent to an average member of the critical group from groundwater sources, and 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.

R313-15-403.  Criteria for License Termination Under Restricted Conditions.
	A site will be considered acceptable for license termination under restricted conditions if:
	(1)  The licensee can demonstrate that further reductions in residual radioactivity necessary to comply with the provisions of Section R313-15-402 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; and
	(2)  The licensee has made provisions for legally enforceable institutional controls that provide reasonable assurance that the total effective dose equivalent from residual radioactivity distinguishable from background to the average member of the critical group will not exceed 0.25 mSv (0.025 rem)per year; and
	(3)  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:
	(a)  Funds placed into an account segregated from the licensee's assets outside the licensee's administrative control, and in which the adequacy of the trust funds is to be assessed based on an assumed annual one percent real rate of return on investment;
	(b)  A statement of intent in the case of Federal, State, or local Government licensees, as described in Subsection R313-22-35(6)(d); or
	(c)  When a governmental entity is assuming custody and ownership of a site, an arrangement that is deemed acceptable by such governmental entity; and
	(4)  The licensee has submitted a decommissioning plan or license termination plan to the Director indicating the licensee's intent to decommission in accordance with Subsection R313-22-36(4) and specifying that the licensee intends to decommission by restricting use of the site.  The licensee shall document in the license termination plan 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;
	(a)  Licensees proposing to decommission by restricting use of the site shall seek advice from such affected parties regarding the following matters concerning the proposed decommissioning:
	(i)  Whether provisions for institutional controls proposed by the licensee;
	(A)  Will provide reasonable assurance that the total effective dose equivalent from residual radioactivity distinguishable from background to the average member of the critical group will not exceed 0.25 mSv (0.025 rem) total effective dose equivalent per year;
	(B)  Will be enforceable; and
	(C)  Will not impose undue burdens on the local community or other affected parties; and
	(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; and
	(b)  In seeking advice on the issues identified in Subsection R313-15-403(4)(a), the licensee shall provide for:
	(i)  Participation by representatives of a broad cross section of community interests who may be affected by the decommissioning;
	(ii)  An opportunity for a comprehensive, collective discussion on the issues by the participants represented; and
	(iii)  A publicly available summary of the results of all such discussions, including a description of the individual viewpoints of the participants on the issues and the extent of agreement and disagreement among the participants on the issues; and
	(5)  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 total effective dose equivalent 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:
	(a)  one mSv (0.1 rem) per year; or
	(b)  five mSv (0.5 rem) per year provided the licensee:
	(i)  Demonstrates that further reductions in residual radioactivity necessary to comply with the one mSv (0.1 rem) per year value of Subsection R313-15-403(5)(a) are not technically achievable, would be prohibitively expensive, or would result in net public or environmental harm;
	(ii)  Makes provisions for durable institutional controls; and
	(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 five years to assure that the institutional controls remain in place as necessary to meet the criteria of Subsection R313-15-403(2) and to assume and carry out responsibilities for any necessary control and maintenance of those controls.  Acceptable financial assurance mechanisms are those in Subsection R313-15-403(3).

R313-15-404.  Alternate Criteria for License Termination.
	(1)  The Director may terminate a license using alternative criteria greater than the dose criterion of Section R313-15-402, and Subsections R313-15-403(2) and R313-15-403(4)(a)(i)(A), if the licensee:
	(a)  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 one mSv (0.1 rem) per year limit of Subsection R313-15-301(1)(a), by submitting an analysis of possible sources of exposure; and
	(b)  Has employed, to the extent practical, restrictions on site use according to the provisions of Section R313-15-403 in minimizing exposures at the site; and
	(c)  Reduces doses to ALARA levels, taking into consideration any detriments such as traffic accidents expected to potentially result from decontamination and waste disposal; and
	(d)  Has submitted a decommissioning plan or license termination plan to the Director indicating the licensee's intent to decommission in accordance with Subsection R313-22-36(4), and specifying that the licensee proposes to decommission by use of alternate criteria.  The licensee shall document in the decommissioning plan or license termination plan how the advice of individuals and institutions in the community who may be affected by the decommissioning has been sought and addressed, as appropriate, following analysis of that advice.  In seeking such advice, the licensee shall provide for:
	(i)  Participation by representatives of a broad cross section of community interests who may be affected by the decommissioning; and
	(ii)  An opportunity for a comprehensive, collective discussion on the issues by the participants represented; and
	(iii)  A publicly available summary of the results of all such discussions, including a description of the individual viewpoints of the participants on the issues and the extent of agreement and disagreement among the participants on the issues.
	(e)  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.
	(2)  The use of alternate criteria to terminate a license requires the approval of the Director after consideration of recommendations from the Division's staff, comments provided by federal, state and local governments, and any public comments submitted pursuant to Section R313-15-405.

R313-15-405.  Public Notification and Public Participation.
	Upon the receipt of a license termination plan or decommissioning plan from the licensee, or a proposal by the licensee for release of a site pursuant to Sections R313-15-403 or R313-15-404, or whenever the Director deems such notice to be in the public interest, the Director shall:
	(1)  Notify and solicit comments from:
	(a)  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
	(b)  Federal, state and local governments for cases where the licensee proposes to release a site pursuant to Section R313-15-404.
	(2)  Publish a notice in a forum, such as local newspapers, letters to State or local organizations, or other appropriate forum, that is readily accessible to individuals in the vicinity of the site, and solicit comments from affected parties.

R313-15-406.  Minimization of Contamination.
	(1)  Applicants for licenses, other than renewals, 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 waste.
	(2)  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 Section R313-15-101 and radiological criteria for license termination in Sections R313-15-1401 through R313-15-1406.

R313-15-501.  Surveys and Monitoring - General.
	(1)  Each licensee or registrant shall make, or cause to be made, surveys of areas, including the subsurface, that:
	(a)  May be necessary for the licensee or registrant to comply with Rule R313-15; and
	(b)  Are reasonable under the circumstances to evaluate:
	(i)  The magnitude and the extent of radiation levels; and
	(ii)  Concentrations or quantities of residual radioactive material; and
	(iii)  The potential radiological hazards of the radiation levels and residual radioactivity detected.
	(2)  Notwithstanding R313-15-1103(1), records from surveys describing the location and amount of subsurface residual radioactivity identified at the site shall be kept with records important for decommissioning, and such records shall be retained in accordance with R313-22-35(7), as applicable.
	(3)  The licensee or registrant shall ensure that instruments and equipment used for quantitative radiation measurements, for example, dose rate and effluent monitoring, are calibrated at intervals not to exceed 12 months for the radiation measured, except when a more frequent interval is specified in another applicable part of these rules or a license condition.
	(4)  All personnel dosimeters, except for direct and indirect reading pocket ionization chambers and those dosimeters used to measure the dose to any extremity, that require processing to determine the radiation dose and that are used by licensees and registrants to comply with Section R313-15-201, with other applicable provisions of these rules, or with conditions specified in a license or registration shall be processed and evaluated by a dosimetry processor:
	(a)  Holding current personnel dosimetry accreditation from the National Voluntary Laboratory Accreditation Program (NVLAP) of the National Institute of Standards and Technology; and
	(b)  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.
	(5)  The licensee or registrant shall ensure that adequate precautions are taken to prevent a deceptive exposure of an individual monitoring device.

R313-15-502.  Conditions Requiring Individual Monitoring of External and Internal Occupational Dose.
	Each licensee or registrant shall monitor exposures from sources of radiation at levels sufficient to demonstrate compliance with the occupational dose limits of Rule R313-15.  As a minimum:
	(1)  Each licensee or registrant shall monitor occupational exposure to radiation from licensed, unlicensed, and registered radiation sources under the control of the licensee and shall supply and require the use of individual monitoring devices by:
	(a)  Adults likely to receive, in one year from sources external to the body, a dose in excess of ten percent of the limits in Subsection R313-15-201(1); and
	(b)  Minors likely to receive, in one year, from radiation sources external to the body, a deep dose equivalent in excess of one mSv (0.1 rem), a lens dose equivalent in excess of 1.5 mSv (0.15 rem), or a shallow dose equivalent to the skin or to the extremities in excess of five mSv (0.5 rem); and
	(c) Declared pregnant women likely to receive during the entire pregnancy, from radiation sources external to the body, a deep dose equivalent in excess of one mSv (0.1 rem); and
	(d)  Individuals entering a high or very high radiation area; and
	(e)  Individuals working with medical fluoroscopic equipment.
	(i)  An individual monitoring device used for the dose to an embryo/fetus of a declared pregnant woman, pursuant to Subsection R313-15-208(1), shall be located under the protective apron at the waist.
	(A)  If an individual monitoring device worn by a declared pregnant woman has a monthly reported dose equivalent value in excess of 0.5 mSv (50 mrem), the value to be used for determining the dose to the embryo/fetus, pursuant to Subsection R313-15-208(3)(a) for radiation from medical fluoroscopy, may be the value reported by the individual monitoring device worn at the waist underneath the protective apron which has been corrected for the potential overestimation of dose recorded by the monitoring device because of the overlying tissue of the pregnant individual.  This correction shall be performed by a radiation safety officer of an institutional radiation safety committee, a qualified expert approved by the Director.
	(ii)  An individual monitoring device used for lens dose equivalent shall be located at the neck, or an unshielded location closer to the eye, outside the protective apron.
	(iii)  When only one individual monitoring device is used to determine the effective dose equivalent for external radiation pursuant to Subsection R313-15-201(3)(b), it shall be located at the neck outside the protective apron.  When a second individual monitoring device is used, for the same purpose, it shall be located under the protective apron at the waist.  Note:  The second individual monitoring device is required for a declared pregnant woman.
	(iv)  A registrant is not required to supply and require the use of individual monitoring devices provided the registrant has conducted a survey, pursuant to Section R313-15-501, that demonstrates that the working environment the individual encounters will not likely result in a dose in excess of ten percent of the limits in Subsection R313-15-201(1), and that the individual is neither a minor nor a declared pregnant woman.
	(2)  Each licensee or registrant shall monitor, to determine compliance with Section R313-15-204, the occupational intake of radioactive material by and assess the committed effective dose equivalent to:
	(a)  Adults likely to receive, in one year, an intake in excess of ten percent of the applicable ALI(s) in Table I, Columns 1 and 2, of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference; and
	(b)  Minors likely to receive, in one year, a committed effective dose equivalent in excess of one mSv (0.1 rem); and
	(c) Declared pregnant women likely to receive, during the entire pregnancy, a committed effective dose equivalent in excess of one mSv (0.1 rem).
	Note: All of the occupational doses in Section R313-15-201 continue to be applicable to the declared pregnant worker as long as the embryo/fetus dose limit is not exceeded.

R313-15-503.  Location of Individual Monitoring Devices.
	Each licensee or registrant shall ensure that individuals who are required to monitor occupational doses in accordance with Subsection R313-15-502(1) wear individual monitoring devices as follows:
	(1)  An individual monitoring device used for monitoring the dose to the whole body shall be worn at the unshielded location of the whole body likely to receive the highest exposure.  When a protective apron is worn, the location of the individual monitoring device is typically at the neck (collar).
	(2)  An individual monitoring device used for monitoring the dose to an embryo/fetus of a declared pregnant woman, pursuant to Subsection R313-15-208(1), shall be located at the waist under any protective apron being worn by the woman.
	(3)  An individual monitoring device used for monitoring the lens dose equivalent, to demonstrate compliance with Subsection R313-15-201(1)(b)(i), shall be located at the neck (collar), outside any protective apron being worn by the monitored individual, or at an unshielded location closer to the eye.
	(4)  An individual monitoring device used for monitoring the dose to the extremities, to demonstrate compliance with Subsection R313-15-201(1)(b)(ii), shall be worn on the extremity likely to receive the highest exposure.  Each individual monitoring device shall be oriented to measure the highest dose to the extremity being monitored.

R313-15-601.  Control of Access to High Radiation Areas.
	(1)  The licensee or registrant shall ensure that each entrance or access point to a high radiation area has one or more of the following features:
	(a)  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 one mSv (0.1 rem) in one hour at 30 centimeters from the source of radiation or from any surface that the radiation penetrates; or
	(b)  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
	(c)  Entryways that are locked, except during periods when access to the areas is required, with positive control over each individual entry.
	(2)  In place of the controls required by Subsection R313-15-601(1) for a high radiation area, the licensee or registrant may substitute continuous direct or electronic surveillance that is capable of preventing unauthorized entry.
	(3)  The licensee or registrant may apply to the Director for approval of alternative methods for controlling access to high radiation areas.
	(4)  The licensee or registrant shall establish the controls required by Subsections R313-15-601(1) and R313-15-601(3) in a way that does not prevent individuals from leaving a high radiation area.
	(5)  The licensee or registrant is not required to control 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 rules of the U.S. Department of Transportation provided that:
	(a)  The packages do not remain in the area longer than three days; and
	(b)  The dose rate at one meter from the external surface of any package does not exceed 0.1 mSv (0.01 rem) per hour.
	(6)  The licensee or registrant is not required to control entrance or access to rooms or other areas in hospitals solely because of the presence of patients containing radioactive material, provided that there are personnel in attendance who are taking the necessary precautions to prevent the exposure of individuals to radiation or radioactive material in excess of the established limits in Rule R313-15 and to operate within the ALARA provisions of the licensee's or registrant's radiation protection program.
	(7)  The registrant is not required to control entrance or access to rooms or other areas containing sources of radiation capable of producing a high radiation area as described in Section R313-15-601 if the registrant has met all the specific requirements for access and control specified in other applicable sections of these rules, such as, Rule R313-36 for industrial radiography, Rule R313-28 for x rays in the healing arts, Rule R313-30 for therapeutic radiation machines, and Rule R313-35 for industrial use of x-ray systems.

R313-15-602.  Control of Access to Very High Radiation Areas.
	(1)  In addition to the requirements in Section R313-15-601, the licensee or registrant shall institute 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 five Gy (500 rad) or more in one hour at one meter from a source of radiation or any surface through which the radiation penetrates.  This requirement does not apply to rooms or areas in which diagnostic x-ray systems are the only source of radiation, or to non-self-shielded irradiators.
	(2)  The registrant is not required to control entrance or access to rooms or other areas containing sources of radiation capable of producing a very high radiation area as described in Subsection R313-15-602(1) if the registrant has met all the specific requirements for access and control specified in other applicable sections of these rules, such as, Rule R313-36 for industrial radiography, Rule R313-28 for x rays in the healing arts, Rule R313-30 for therapeutic radiation machines, and Rule R313-35 for industrial use of x-ray systems.

R313-15-603.  Control of Access to Very High Radiation Areas -- Irradiators.
	(1)  Section R313-15-603 applies to licensees or registrants with sources of radiation in non-self-shielded irradiators.  Section R313-15-603 does not apply to sources of radiation that are used in teletherapy, in industrial radiography, or in completely self-shielded irradiators in which the source of radiation is both stored and operated within the same shielding radiation barrier and, in the designed configuration of the irradiator, is always physically inaccessible to any individual and cannot create a high levels of radiation in an area that is accessible to any individual.
	(2)  Each area in which there may exist radiation levels in excess of five Gy (500 rad) in one hour at one meter from a source of radiation that is used to irradiate materials shall meet the following requirements:
	(a)  Each entrance or access point shall be equipped with entry control devices which:
	(i)  Function automatically to prevent any individual from inadvertently entering a very high radiation area; and
	(ii)  Permit deliberate entry into the area only after a control device is actuated that causes the radiation level within the area, from the source of radiation, to be reduced below that at which it would be possible for an individual to receive a deep dose equivalent in excess of one mSv (0.1 rem) in one hour; and
	(iii)  Prevent operation of the source of radiation if it would produce radiation levels in the area that could result in a deep dose equivalent to an individual in excess of one mSv (0.1 rem) in one hour.
	(b)  Additional control devices shall be provided so that, upon failure of the entry control devices to function as required by Subsection R313-15-603(2)(a):
	(i)  The radiation level within the area, from the source of radiation, is reduced below that at which it would be possible for an individual to receive a deep dose equivalent in excess of one mSv (0.1 rem) in one hour; and
	(ii)  Conspicuous visible and audible alarm signals are generated to make an individual attempting to enter the area aware of the hazard and at least one other authorized individual, who is physically present, familiar with the activity, and prepared to render or summon assistance, aware of the failure of the entry control devices.
	(c)  The licensee or registrant shall provide control devices so that, upon failure or removal of physical radiation barriers other than the sealed source's shielded storage container:
	(i)  The radiation level from the source of radiation is reduced below that at which it would be possible for an individual to receive a deep dose equivalent in excess of one mSv (0.1 rem) in one hour; and
	(ii)  Conspicuous visible and audible alarm signals are generated to make potentially affected individuals aware of the hazard and the licensee or registrant or at least one other individual, who is familiar with the activity and prepared to render or summon assistance, aware of the failure or removal of the physical barrier.
	(d)  When the shield for stored sealed sources is a liquid, the licensee or registrant shall provide means to monitor the integrity of the shield and to signal, automatically, loss of adequate shielding.
	(e)  Physical radiation barriers that comprise permanent structural components, such as walls, that have no credible probability of failure or removal in ordinary circumstances need not meet the requirements of Subsections R313-15-603(2)(c) and R313-15-603(2)(d).
	(f)  Each area shall be equipped with devices that will automatically generate conspicuous visible and audible alarm signals to alert personnel in the area before the source of radiation can be put into operation and in time for any individual in the area to operate a clearly identified control device, which shall be installed in the area and which can prevent the source of radiation from being put into operation.
	(g)  Each area shall be controlled by use of such administrative procedures and such devices as are necessary to ensure that the area is cleared of personnel prior to each use of the source of radiation.
	(h)  Each area shall be checked by a radiation measurement to ensure that, prior to the first individual's entry into the area after any use of the source of radiation, the radiation level from the source of radiation in the area is below that at which it would be possible for an individual to receive a deep dose equivalent in excess of one mSv (0.1 rem) in one hour.
	(i)  The entry control devices required in Subsection R313-15-603(2)(a) shall be tested for proper functioning. See Section R313-15-1110 for recordkeeping requirements.
	(i)  Testing shall be conducted prior to initial operation with the source of radiation on any day, unless operations were continued uninterrupted from the previous day; and
	(ii)  Testing shall be conducted prior to resumption of operation of the source of radiation after any unintentional interruption; and
	(iii)  The licensee or registrant shall submit and adhere to a schedule for periodic tests of the entry control and warning systems.
	(j)  The licensee or registrant shall not conduct operations, other than those necessary to place the source of radiation in safe condition or to effect repairs on controls, unless control devices are functioning properly.
	(k)  Entry and exit portals that are used in transporting materials to and from the irradiation area, and that are not intended for use by individuals, shall be controlled by such devices and administrative procedures as are necessary to physically protect and warn against inadvertent entry by any individual through these portals.  Exit portals for irradiated materials shall be equipped to detect and signal the presence of any loose radioactive material that is carried toward such an exit and automatically to prevent loose radioactive material from being carried out of the area.
	(3)  Licensees, registrants, or applicants for licenses or registrations for sources of radiation within the purview of Subsection R313-15-603(2) which will be used in a variety of positions or in locations, such as open fields or forests, that make it impractical to comply with certain requirements of Subsection R313-15-603(2), such as those for the automatic control of radiation levels, may apply to the Director for approval of alternative safety measures.  Alternative safety measures shall provide personnel protection at least equivalent to those specified in Subsection R313-15-603(2).  At least one of the alternative measures shall include an entry-preventing interlock control based on a measurement of the radiation that ensures the absence of high radiation levels before an individual can gain access to the area where such sources of radiation are used.
	(4)  The entry control devices required by Subsections R313-15-603(2) and R313-15-603(3) shall be established in such a way that no individual will be prevented from leaving the area.

R313-15-701.  Use of Process or Other Engineering Controls.
	The licensee or registrant shall use, to the extent practical, process or other engineering controls, such as, containment, decontamination, or ventilation, to control the concentration of radioactive material in air.

R313-15-702.  Use of Other Controls.
	(1)  When it is not practical to apply process or other engineering controls to control the concentration of radioactive material in the air to values below those that define an airborne radioactivity area, the licensee or registrant shall, consistent with maintaining the total effective dose equivalent ALARA, increase monitoring and limit intakes by one or more of the following means:
	(a)  Control of access; or
	(b)  Limitation of exposure times; or
	(c)  Use of respiratory protection equipment; or
	(d)  Other controls.
	(2)  If the licensee or registrant 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 or registrant should also consider the impact of respirator use on workers' industrial health and safety.

R313-15-703.  Use of Individual Respiratory Protection Equipment.
	If the licensee or registrant uses respiratory protection equipment to limit the intake of radioactive material:
	(1)  Except as provided in Subsection R313-15-703(2), the licensee or registrant shall use only respiratory protection equipment that is tested and certified by the National Institute for Occupational Safety and Health.
	(2)  The licensee or registrant may use equipment that has not been tested or certified by the National Institute for Occupational Safety and Health or for which there is no schedule for testing or certification, provided the licensee or registrant has submitted to the Director and the Director has approved an application for authorized use of that equipment.  The application must include a demonstration by testing, or a demonstration on the basis of reliable test information, that the material and performance characteristics of the equipment are capable of providing the proposed degree of protection under anticipated conditions of use.
	(3)  The licensee or registrant shall implement and maintain a respiratory protection program that includes:
	(a)  Air sampling sufficient to identify the potential hazard, permit proper equipment selection, and estimate doses; and
	(b)  Surveys and bioassays, as necessary, to evaluate actual intakes; and
	(c)  Testing of respirators for operability, user seal check for face sealing devices and functional check for others, immediately prior to each use; and
	(d)  Written procedures regarding
	(i)  Monitoring, including air sampling and bioassays;
	(ii)  Supervision and training of respirator users;
	(iii)  Fit testing;
	(iv)  Respirator selection;
	(v)  Breathing air quality;
	(vi)  Inventory and control;
	(vii)  Storage, issuance, maintenance, repair, testing, and quality assurance of respiratory protection equipment;
	(viii)  Recordkeeping; and
	(ix)  Limitations on periods of respirator use and relief from respirator use; and
	(e)  Determination by a physician prior to initial fitting of respirators, before the first field use of non-face sealing respirators, and either every 12 months thereafter or periodically at a frequency determined by a physician, that the individual user is medically fit to use the respiratory protection equipment; and
	(f)  Fit testing, with fit factor greater than or equal to ten times the APF for negative pressure devices, and a fit factor greater than or equal to 500 for 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 one year.  Fit testing must be performed with the facepiece operating in the negative pressure mode.
	(4)  The licensee or registrant 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.
	(5)  The licensee or registrant 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 or registrant shall use equipment in such a way as not to interfere with the proper operation of the respirator.
	(6) 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.
	(7) Atmosphere-supplying respirators must be supplied with respirable air of grade D quality or better as defined by the Compressed Gas Association in publication G-7.1, "Commodity Specification for Air," 1997 ed. and included in 29 CFR 1910.134(i)(1)(ii)(A) through (E), (2010).  Grade D quality air criteria include:
	(a) Oxygen content (v/v) of 19.5 to 23.5%;
	(b) Hydrocarbon (condensed) content of five milligrams per cubic meter of air or less;
	(c) Carbon monoxide (CO) content of ten ppm or less;
	(d) Carbon dioxide content of 1,000 ppm or less; and
	(e) Lack of noticeable odor.
	(8) The licensee shall ensure that no objects, materials or substances, such as facial hair, or any conditions that interfere with the face and facepiece seal or valve function, and that are under the control of the respirator wearer, are present between the skin of the wearer's face and the sealing surface of a tight-fitting respirator facepiece.
	(9) 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.

R313-15-704.  Further Restrictions on the Use of Respiratory Protection Equipment.
	The Director may impose restrictions in addition to the provisions of Section R313-15-702, Section R313-15-703, and Appendix A of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference to:
	(1) Ensure that the respiratory protection program of the licensee or registrant is adequate to limit doses to individuals from intakes of airborne radioactive materials consistent with maintaining total effective dose equivalent ALARA; and
	(2) Limit the extent to which a licensee or registrant may use respiratory protection equipment instead of process or other engineering controls.

R313-15-705.  Application for Use of Higher Assigned Protection Factors.
	The licensee or registrant shall obtain authorization from the Director before using assigned protection factors in excess of those specified in Appendix A of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference. The Director may authorize a licensee or registrant to use higher assigned protection factors on receipt of an application that:
	(1) Describes the situation for which a need exists for higher protection factors; and
	(2) Demonstrates that the respiratory protection equipment provides these higher protection factors under the proposed conditions of use.

R313-15-801.  Security and Control of Licensed or Registered Sources of Radiation.
	(1) The licensee or registrant shall secure licensed or registered radioactive material from unauthorized removal or access.
	(2)  The licensee or registrant shall maintain constant surveillance, and use devices or administrative procedures to prevent unauthorized use of licensed or registered radioactive material that is in an unrestricted area and that is not in storage.
	(3)  The registrant shall secure registered radiation machines from unauthorized removal.
	(4)  The registrant shall use devices or administrative procedures to prevent unauthorized use of registered radiation machines.

R313-15-901.  Caution Signs.
	(1)  Standard Radiation Symbol.  Unless otherwise authorized by the Director, the symbol prescribed by 10 CFR 20.1901, (2010), which is incorporated by reference, shall use the colors magenta, or purple, or black on yellow background.  The symbol prescribed is the three-bladed design as follows:
	(a)  Cross-hatched area is to be magenta, or purple, or black, and
	(b)  The background is to be yellow.
	(2) Exception to Color Requirements for Standard Radiation Symbol.  Notwithstanding the requirements of 10 CFR 20.1901(a), (2010), which is incorporated by reference, licensees or registrants are authorized to label sources, source holders, or device components containing sources of radiation that are subjected to high temperatures, with conspicuously etched or stamped radiation caution symbols and without a color requirement.
	(3)  Additional Information on Signs and Labels.  In addition to the contents of signs and labels prescribed in Rule R313-15, the licensee or registrant shall 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.

R313-15-902.  Posting Requirements.
	(1)  Posting of Radiation Areas.  The licensee or registrant shall post each radiation area with a conspicuous sign or signs bearing the radiation symbol and the words "CAUTION, RADIATION AREA."
	(2)  Posting of High Radiation Areas.  The licensee or registrant shall post each high radiation area with a conspicuous sign or signs bearing the radiation symbol and the words "CAUTION, HIGH RADIATION AREA" or "DANGER, HIGH RADIATION AREA."
	(3)  Posting of Very High Radiation Areas.  The licensee or registrant shall post each very high radiation area with a conspicuous sign or signs bearing the radiation symbol and words "GRAVE DANGER, VERY HIGH RADIATION AREA."
	(4)  Posting of Airborne Radioactivity Areas.  The licensee or registrant shall post each airborne radioactivity area with a conspicuous sign or signs bearing the radiation symbol and the words "CAUTION, AIRBORNE RADIOACTIVITY AREA" or "DANGER, AIRBORNE RADIOACTIVITY AREA."
	(5)  Posting of Areas or Rooms in which Licensed or Registered Material is Used or Stored.  The licensee or registrant shall post each area or room in which there is used or stored an amount of licensed or registered material exceeding ten times the quantity of such material specified in Appendix C of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference, with a conspicuous sign or signs bearing the radiation symbol and the words "CAUTION, RADIOACTIVE MATERIAL" or "DANGER, RADIOACTIVE MATERIAL."

R313-15-903.  Exceptions to Posting Requirements.
	(1)  A licensee or registrant is not required to post caution signs in areas or rooms containing sources of radiation for periods of less than eight hours, if each of the following conditions is met:
	(a)  The sources of radiation are constantly attended during these periods by an individual who takes the precautions necessary to prevent the exposure of individuals to sources of radiation in excess of the limits established in Rule R313-15; and
	(b)  The area or room is subject to the licensee's or registrant's control.
	(2)  Rooms or other areas in hospitals that are occupied by patients are not required to be posted with caution signs pursuant to Section R313-15-902 provided that the patient could be released from licensee control pursuant to Rule R313-32.
	(3)  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 sealed source container or housing does not exceed 0.05 mSv (0.005 rem) per hour.
	(4)  A room or area is not required to be posted with a caution sign because of the presence of radiation machines used solely for diagnosis in the healing arts.
	(5)  Rooms in hospitals or clinics that are used for teletherapy are exempt from the requirement to post caution signs under Section R313-15-902 if:
	(a)  Access to the room is controlled pursuant to Section R313-32; and
	(b)  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 Rule R313-15.

R313-15-904.  Labeling Containers and Radiation Machines.
	(1)  The licensee or registrant shall ensure that each container of licensed or registered material bears a durable, clearly visible label bearing the radiation symbol and the words "CAUTION, RADIOACTIVE MATERIAL" or "DANGER, RADIOACTIVE MATERIAL." The label shall also provide information, such as the radionuclides 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.
	(2)  Each licensee or registrant 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.
	(3)  Each registrant shall ensure that each radiation machine is labeled in a conspicuous manner which cautions individuals that radiation is produced when it is energized.

R313-15-905.  Exemptions to Labeling Requirements.
	A licensee or registrant is not required to label:
	(1)  Containers holding licensed or registered material in quantities less than the quantities listed in Appendix C of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference; or
	(2)  Containers holding licensed or registered material in concentrations less than those specified in Table III of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference; or
	(3)  Containers attended by an individual who takes the precautions necessary to prevent the exposure of individuals in excess of the limits established by Rule R313-15; or
	(4)  Containers when they are in transport and packaged and labeled in accordance with the rules of the U.S. Department of Transportation; or
	(5)  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 shall be retained as long as the containers are in use for the purpose indicated on the record; or
	(6)  Installed manufacturing or process equipment, such as piping and tanks.

R313-15-906.  Procedures for Receiving and Opening Packages.
	(1)  Each licensee or registrant who expects to receive a package containing quantities of radioactive material in excess of a Type A quantity, as used in Section R313-19-100, which incorporates 10 CFR 71.4 by reference, shall make arrangements to receive:
	(a)  The package when the carrier offers it for delivery; or
	(b)  The notification of the arrival of the package at the carrier's terminal and to take possession of the package expeditiously.
	(2)  Each licensee or registrant shall:
	(a)  Monitor the external surfaces of a labeled package for radioactive contamination unless the package contains only radioactive material in the form of gas or in special form as defined in Section R313-12-3; and
	(b)  Monitor the external surfaces of a labeled package for radiation levels unless the package contains quantities of radioactive material that are less than or equal to the Type A quantity, as used in Section R313-19-100, which incorporates 10 CFR 71.4 by reference; and
	(c)  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.
	(3)  The licensee or registrant shall perform the monitoring required by Subsection R313-15-906(2) as soon as practical after receipt of the package, but not later than three hours after the package is received at the licensee's or registrant's facility if it is received during the licensee's or registrant's normal working hours or if there is evidence of degradation of package integrity, such as a package that is crushed, wet, or damaged.  If a package is received after working hours, and has no evidence of degradation of package integrity, the package shall be monitored no later than three hours from the beginning of the next working day.
	(4)  The licensee or registrant shall immediately notify the final delivery carrier and, by telephone and telegram, mailgram, or facsimile, the Director when:
	(a)  Removable radioactive surface contamination exceeds the limits of Section R313-19-100 which incorporates 10 CFR 71.87(i) by reference; or
	(b)  External radiation levels exceed the limits of Section R313-19-100 which incorporates 10 CFR 71.47 by reference.
	(5)  Each licensee or registrant shall:
	(a)  Establish, maintain, and retain written procedures for safely opening packages in which radioactive material is received; and
	(b)  Ensure that the procedures are followed and that due consideration is given to special instructions for the type of package being opened.
	(6)  Licensees or registrants transferring special form sources in vehicles owned or operated by the licensee or registrant to and from a work site are exempt from the contamination monitoring requirements of Subsection R313-15-906(2), but are not exempt from the monitoring requirement in Subsection R313-15-906(2) for measuring radiation levels that ensures that the source is still properly lodged in its shield.

R313-15-1001.  Waste Disposal - General Requirements.
	(1)  A licensee or registrant shall dispose of licensed or registered material only:
	(a)  By transfer to an authorized recipient as provided in Section R313-15-1006 or in Rules R313-21, R313-22, R313-24, or R313-25, or to the U.S. Department of Energy; or
	(b)  By decay in storage; or
	(c)  By release in effluents within the limits in Section R313-15-301; or
	(d)  As authorized pursuant to Sections R313-15-1002, R313-15-1003, R313-15-1004, R313-15-1005, or R313-15-1008.
	(2)  A person shall be specifically licensed or registered to receive waste containing licensed or registered material from other persons for:
	(a)  Treatment prior to disposal; or
	(b)  Treatment or disposal by incineration; or
	(c)  Decay in storage; or
	(d)  Disposal at a land disposal facility licensed pursuant to Rule R313-25; or
	(e)  Storage until transferred to a storage or disposal facility authorized to receive the waste.

R313-15-1002.  Method for Obtaining Approval of Proposed Disposal Procedures.
	A licensee or registrant or applicant for a license or registration may apply to the Director for approval of proposed procedures, not otherwise authorized in these rules, to dispose of licensed or registered material generated in the licensee's or registrant's operations.  Each application shall include:
	(1)  A description of the waste containing licensed or registered material to be disposed of, including the physical and chemical properties that have an impact on risk evaluation, and the proposed manner and conditions of waste disposal; and
	(2)  An analysis and evaluation of pertinent information on the nature of the environment; and
	(3)  The nature and location of other potentially affected facilities; and
	(4)  Analyses and procedures to ensure that doses are maintained ALARA and within the dose limits in Rule R313-15.

R313-15-1003.  Disposal by Release into Sanitary Sewerage.
	(1)  A licensee or registrant may discharge licensed or registered material into sanitary sewerage if each of the following conditions is satisfied:
	(a)  The material is readily soluble, or is readily dispersible biological material, in water; and
	(b)  The quantity of licensed or registered radioactive material that the licensee or registrant releases into the sewer in one month divided by the average monthly volume of water released into the sewer by the licensee or registrant does not exceed the concentration listed in Table III of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference; and
	(c)  If more than one radionuclide is released, the following conditions shall also be satisfied:
	(i)  The licensee or registrant shall determine the fraction of the limit in Table III of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference, represented by discharges into sanitary sewerage by dividing the actual monthly average concentration of each radionuclide released by the licensee or registrant into the sewer by the concentration of that radionuclide listed in Table III of Appendix B of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference; and
	(ii)  The sum of the fractions for each radionuclide required by Subsection R313-15-1003(1)(c)(i) does not exceed unity; and
	(d)  The total quantity of licensed or registered radioactive material that the licensee or registrant releases into the sanitary sewerage system in a year does not exceed 185 GBq (five Ci) of hydrogen-3, 37 GBq (one Ci) of carbon-14, and 37 GBq (one Ci) of all other radioactive materials combined.
	(2)  Excreta from individuals undergoing medical diagnosis or therapy with radioactive material are not subject to the limitations contained in Subsection R313-15-1003(1).

R313-15-1004.  Treatment or Disposal by Incineration.
	A licensee or registrant may treat or dispose of licensed or registered material by incineration only in the form and concentration specified in Section R313-15-1005 or as specifically approved by the Director pursuant to Section R313-15-1002.

R313-15-1005.  Disposal of Specific Wastes.
	(1)  A licensee or registrant may dispose of the following licensed or registered material as if it were not radioactive:
	(a)  1.85 kBq (0.05 uCi), or less, of hydrogen-3 or carbon-14 per gram of medium used for liquid scintillation counting; and
	(b)  1.85 kBq (0.05 uCi) or less, of hydrogen-3 or carbon-14 per gram of animal tissue, averaged over the weight of the entire animal.
	(2)  A licensee or registrant shall not dispose of tissue pursuant to Subsection R313-15-1005(1)(b) in a manner that would permit its use either as food for humans or as animal feed.
	(3)  The licensee or registrant shall maintain records in accordance with Section R313-15-1109.

R313-15-1006.  Transfer for Disposal and Manifests.
	(1)  The requirements of Section R313-15-1006 and Appendix G of 10 CFR 20.1001 to 20.2402, (2010), which are incorporated into these rules by reference, are designed to:
	(a)  control transfers of low-level radioactive waste by any waste generator, waste collector, or waste processor licensee, as defined in Appendix G in 10 CFR 20.1001 to 20.2402, (2010), 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 Section R313-25-2;
	(b)  establish a manifest tracking system; and
	(c) supplement existing requirements concerning transfers and recordkeeping for those wastes.
	(2)  Any licensee shipping radioactive waste intended for ultimate disposal at a licensed land disposal facility must document the information required on the U.S. Nuclear Regulatory Commission'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 20.1001 to 20.2402, (2010), which is incorporated into these rules by reference.
	(3)  Each shipment manifest shall include a certification by the waste generator as specified in Section II of Appendix G to 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference.
	(4)  Each person involved in the transfer of waste for disposal or in the 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 20.1001 to 20.2402, (2010), which is incorporated by reference.
	(5)  A licensee shipping byproduct material as defined in paragraphs (c) and (d) of the Section R313-12-3 definition of byproduct material intended for ultimate disposal at a land disposal facility licensed under Rule R313-25 must document the information required on the NRC's Uniform Low-Level Radioactive Waste Manifest and transfer the recorded manifest information to the intended consignee in accordance with Appendix G to 10 CFR Part 20 (2010 edition).

R313-15-1007.  Compliance with Environmental and Health Protection Rules.
	Nothing in Sections R313-15-1001, R313-15-1002, R313-15-1003, R313-15-1004, R313-15-1005, or R313-15-1006 relieves the licensee or registrant from complying with other applicable Federal, State and local rules governing any other toxic or hazardous properties of materials that may be disposed of pursuant to Sections R313-15-1001, R313-15-1002, R313-15-1003, R313-15-1004, R313-15-1005, or R313-15-1006.

R313-15-1008.  Disposal of Section R313-12-3 Byproduct Material Definition Paragraphs (c) and (d).
	(1)  Licensed material defined in Section R313-12-3, byproduct material definition, paragraphs (c) and (d), may be disposed in accordance with Rule R313-25, even though it is not defined as low-level radioactive waste.  Therefore, licensed byproduct material being disposed of at a facility, or transferred for ultimate disposal at a facility licensed under Rule R313-25, must meet the requirements of Section R313-15-1006.
	(2) A licensee may dispose of licensed material defined in Section R313-12-3, byproduct material definition, paragraphs (c) and (d), at a disposal facility authorized to dispose of such material in accordance with Federal or State solid or hazardous waste law, including the Solid Waste Disposal Act, as authorized under the Energy Policy Act of 2005.

R313-15-1009.  Classification and Characteristics of Low-Level Radioactive Waste.
	(1)  Classification of Radioactive Waste for Land Disposal
	(a)  Considerations.  Determination of the classification of radioactive waste involves two considerations.  First, consideration shall be given to the concentration of long-lived radionuclides (and their shorter-lived precursors) whose potential hazard will persist long after such precautions as institutional controls, improved waste form, and deeper disposal have ceased to be effective.  These precautions delay the time when long-lived radionuclides could cause exposures.  In addition, the magnitude of the potential dose is limited by the concentration and availability of the radionuclide at the time of exposure.  Second, consideration shall be given to the concentration of shorter-lived radionuclides for which requirements on institutional controls, waste form, and disposal methods are effective.
	(b)  Classes of waste.
	(i)  Class A waste is waste that is usually segregated from other waste classes at the disposal site.  The physical form and characteristics of Class A waste shall meet the minimum requirements set forth in Subsection R313-15-1009(2)(a).  If Class A waste also meets the stability requirements set forth in Subsection R313-15-1009(2)(b), it is not necessary to segregate the waste for disposal.
	(ii)  Class B waste is waste that shall meet more rigorous requirements on waste form to ensure stability after disposal.  The physical form and characteristics of Class B waste shall meet both the minimum and stability requirements set forth in Subsection R313-15-1009(2).
	(iii)  Class C waste is waste that not only shall meet more rigorous requirements on waste form to ensure stability but also requires additional measures at the disposal facility to protect against inadvertent intrusion.  The physical form and characteristics of Class C waste shall meet both the minimum and stability requirements set forth in Subsection R313-15-1009(2).
	(c)  Classification determined by long-lived radionuclides.  If the radioactive waste contains only radionuclides listed in Table I, classification shall be determined as follows:
	(i)  If the concentration does not exceed 0.1 times the value in Table I, the waste is Class A.
	(ii)  If the concentration exceeds 0.1 times the value in Table I, but does not exceed the value in Table I, the waste is Class C.
	(iii)  If the concentration exceeds the value in Table I, the waste is not generally acceptable for land disposal.
	(iv)  For wastes containing mixtures of radionuclides listed in Table I, the total concentration shall be determined by the sum of fractions rule described in Subsection R313-15-1009(1)(g).

	TABLE I

	Concentration

Radionuclide           curie/cubic meter(1)     nanocurie/gram(2)

C-14                           8
C-14 in activated metal       80
Ni-59 in activated metal     220
Nb-94 in activated metal       0.2
Tc-99                          3
I-129                          0.08
Alpha emitting transuranic
 radionuclides with half-
 life greater than five
 years                                                      100
Pu-241                                                    3,500
Cm-242                                                   20,000
Ra-226                                                      100

NOTE:  (1)  To convert the Ci/m3 values to gigabecquerel
       (GBq)/cubic meter, multiply the Ci/m3 value by 37.
       (2)  To convert the nCi/g values to becquerel
       (Bq)/gram, multiply the nCi/g value by 37.
	
	(d)  Classification determined by short-lived radionuclides.  If the waste does not contain any of the radionuclides listed in Table I, classification shall be determined based on the concentrations shown in Table II.  However, as specified in Subsection R313-15-1009(1)(f), if radioactive waste does not contain any nuclides listed in either Table I or II, it is Class A.
	(i)  If the concentration does not exceed the value in Column 1, the waste is Class A.
	(ii)  If the concentration exceeds the value in Column 1 but does not exceed the value in Column 2, the waste is Class B.
	(iii)  If the concentration exceeds the value in Column 2 but does not exceed the value in Column 3, the waste is Class C.
	(iv)  If the concentration exceeds the value in Column 3, the waste is not generally acceptable for near-surface disposal.
	(v)  For wastes containing mixtures of the radionuclides listed in Table II, the total concentration shall be determined by the sum of fractions rule described in Subsection R313-15-1009(1)(g).

	TABLE II

Radionuclide               Concentration, curie/cubic meter(1)
                       Column 1           Column 2       Column 3
Total of all radio-
 nuclides with less
 than 5-year half-
 life                    700                (2)             (2)
H-3                       40                (2)             (2)
Co-60                    700                (2)             (2)
Ni-63                      3.5               70             700
Ni-63
 in activated metal       35                700            7000
Sr-90                      0.04             150            7000
Cs-137                     1                 44            4600

NOTE:  (1)  To convert the Ci/m3 value to gigabecquerel
(GBq)/cubic meter, multiply the Ci/m3 value by 37.
       (2)  There are no limits established for these
radionuclides in Class B or C wastes.  Practical considerations
such as the effects of external radiation and internal heat
generation on transportation, handling, and disposal will limit
the concentrations for these wastes.  These wastes shall be Class
B unless the concentrations of other radionuclides in Table II
determine the waste to be Class C independent of these
radionuclides.
	
	(e)  Classification determined by both long- and short-lived radionuclides.  If the radioactive waste contains a mixture of radionuclides, some of which are listed in Table I and some of which are listed in Table II, classification shall be determined as follows:
	(i)  If the concentration of a radionuclide listed in Table I is less than 0.1 times the value listed in Table I, the class shall be that determined by the concentration of radionuclides listed in Table II.
	(ii)  If the concentration of a radionuclide listed in Table I exceeds 0.1 times the value listed in Table I, but does not exceed the value in Table I, the waste shall be Class C, provided the concentration of radionuclides listed in Table II does not exceed the value shown in Column 3 of Table II.
	(f)  Classification of wastes with radionuclides other than those listed in Tables I and II.  If the waste does not contain any radionuclides listed in either Table I or II, it is Class A.
	(g)  The sum of the fractions rule for mixtures of radionuclides.  For determining classification for waste that contains a mixture of radionuclides, it is necessary to determine the sum of fractions by dividing each radionuclide's concentration by the appropriate limit and adding the resulting values.  The appropriate limits shall all be taken from the same column of the same table.  The sum of the fractions for the column shall be less than 1.0 if the waste class is to be determined by that column.  Example:  A waste contains Sr-90 in a concentration of 1.85 TBq/m3 (50 Ci/m3) and Cs-137 in a concentration of 814 GBq/m3 (22 Ci/m3). Since the concentrations both exceed the values in Column 1, Table II, they shall be compared to Column 2 values.  For Sr-90 fraction, 50/150 = 0.33., for Cs-137 fraction, 22/44 = 0.5; the sum of the fractions = 0.83.  Since the sum is less than 1.0, the waste is Class B.
	(h)  Determination of concentrations in wastes.  The concentration of a radionuclide may be determined by indirect methods such as use of scaling factors which relate the inferred concentration of one radionuclide to another that is measured, or radionuclide material accountability, if there is reasonable assurance that the indirect methods can be correlated with actual measurements.  The concentration of a radionuclide may be averaged over the volume of the waste, or weight of the waste if the units are expressed as becquerel (nanocurie) per gram.
	(2)  Radioactive Waste Characteristics
	(a)  The following are minimum requirements for all classes of waste and are intended to facilitate handling and provide protection of health and safety of personnel at the disposal site.
	(i)  Wastes shall be packaged in conformance with the conditions of the license issued to the site operator to which the waste will be shipped.  Where the conditions of the site license are more restrictive than the provisions of Rule R313-15, the site license conditions shall govern.
	(ii)  Wastes shall not be packaged for disposal in cardboard or fiberboard boxes.
	(iii)  Liquid waste shall be packaged in sufficient absorbent material to absorb twice the volume of the liquid.
	(iv)  Solid waste containing liquid shall contain as little free-standing and non-corrosive liquid as is reasonably achievable, but in no case shall the liquid exceed one percent of the volume.
	(v)  Waste shall not be readily capable of detonation or of explosive decomposition or reaction at normal pressures and temperatures, or of explosive reaction with water.
	(vi)  Waste shall not contain, or be capable of generating, quantities of toxic gases, vapors, or fumes harmful to persons transporting, handling, or disposing of the waste.  This does not apply to radioactive gaseous waste packaged in accordance with Subsection R313-15-1009(2)(a)(viii).
	(vii)  Waste shall not be pyrophoric.  Pyrophoric materials contained in wastes shall be treated, prepared, and packaged to be nonflammable.
	(viii)  Wastes in a gaseous form shall be packaged at an absolute pressure that does not exceed 1.5 atmospheres at 20 degrees celsius.  Total activity shall not exceed 3.7 TBq (100 Ci) per container.
	(ix)  Wastes containing hazardous, biological, pathogenic, or infectious material shall be treated to reduce to the maximum extent practical the potential hazard from the non-radiological materials.
	(b)  The following requirements are intended to provide stability of the waste.  Stability is intended to ensure that the waste does not degrade and affect overall stability of the site through slumping, collapse, or other failure of the disposal unit and thereby lead to water infiltration.  Stability is also a factor in limiting exposure to an inadvertent intruder, since it provides a recognizable and nondispersible waste.
	(i)  Waste shall have structural stability.  A structurally stable waste form will generally maintain its physical dimensions and its form, under the expected disposal conditions such as weight of overburden and compaction equipment, the presence of moisture, and microbial activity, and internal factors such as radiation effects and chemical changes.  Structural stability can be provided by the waste form itself, processing the waste to a stable form, or placing the waste in a disposal container or structure that provides stability after disposal.
	(ii)  Notwithstanding the provisions in Subsections R313-15-1009(2)(a)(iii) and R313-15-1009(2)(a)(iv), liquid wastes, or wastes containing liquid, shall be converted into a form that contains as little free-standing and non-corrosive liquid as is reasonably achievable, but in no case shall the liquid exceed one percent of the volume of the waste when the waste is in a disposal container designed to ensure stability, or 0.5 percent of the volume of the waste for waste processed to a stable form.
	(iii)  Void spaces within the waste and between the waste and its package shall be reduced to the extent practical.
	(3)  Labeling.  Each package of waste shall be clearly labeled to identify whether it is Class A, Class B, or Class C waste, in accordance with Subsection R313-15-1009(1).

R313-15-1101.  Records - General Provisions.
	(1)  Each licensee or registrant shall use the SI units becquerel, gray, sievert and coulomb per kilogram, or the special units, curie, rad, rem, and roentgen, including multiples and subdivisions, and shall clearly indicate the units of all quantities on records required by Rule R313-15.
	(2)  Notwithstanding the requirements of Subsection R313-15-1101(1), when recording information on shipment manifests, as required in Subsection R313-15-1006(2), information must be recorded in SI units or in SI units and the special units specified in Subsection R313-15-1101(1).
	(3)  The licensee or registrant shall make a clear distinction among the quantities entered on the records required by Rule R313-15, such as, total effective dose equivalent, total organ dose equivalent, shallow dose equivalent, lens dose equivalent, deep dose equivalent, or committed effective dose equivalent.

R313-15-1102.  Records of Radiation Protection Programs.
	(1)  Each licensee or registrant shall maintain records of the radiation protection program, including:
	(a)  The provisions of the program; and
	(b)  Audits and other reviews of program content and implementation.
	(2)  The licensee or registrant shall retain the records required by Subsection R313-15-1102(1)(a) until the Director terminates each pertinent license or registration requiring the record.  The licensee or registrant shall retain the records required by Subsection R313-15-1102(1)(b) for three years after the record is made.

R313-15-1103.  Records of Surveys.
	(1)  Each licensee or registrant shall maintain records showing the results of surveys and calibrations required by Section R313-15-501 and Subsection R313-15-906(2).  The licensee or registrant shall retain these records for three years after the record is made.
	(2)  The licensee or registrant shall retain each of the following records until the Director terminates each pertinent license or registration requiring the record:
	(a)  Records of the results of surveys to determine the dose from external sources of radiation used, in the absence of or in combination with individual monitoring data, in the assessment of individual dose equivalents; and
	(b)  Records of the results of measurements and calculations used to determine individual intakes of radioactive material and used in the assessment of internal dose; and
	(c)  Records showing the results of air sampling, surveys, and bioassays required pursuant to Subsections R313-15-703(3)(a) and R313-15-703(3)(b); and
	(d)  Records of the results of measurements and calculations used to evaluate the release of radioactive effluents to the environment.

R313-15-1105.  Records of Prior Occupational Dose.
	For each individual who is likely to receive in a year an occupational dose requiring monitoring pursuant to Section R313-15-502, the licensee or registrant shall retain the records of prior occupational dose and exposure history as specified in Section R313-15-205 on form DWMRC-05 or equivalent until the Director terminates each pertinent license requiring this record. The licensee or registrant shall retain records used in preparing form DWMRC-05 or equivalent for three years after the record is made.

R313-15-1106.  Records of Planned Special Exposures.
	(1)  For each use of the provisions of Section R313-15-206 for planned special exposures, the licensee or registrant shall maintain records that describe:
	(a)  The exceptional circumstances requiring the use of a planned special exposure; and
	(b)  The name of the management official who authorized the planned special exposure and a copy of the signed authorization; and
	(c)  What actions were necessary; and
	(d)  Why the actions were necessary; and
	(e)  What precautions were taken to assure that doses were maintained ALARA; and
	(f)  What individual and collective doses were expected to result; and
	(g)  The doses actually received in the planned special exposure.
	(2)  The licensee or registrant shall retain the records until the Director terminates each pertinent license or registration requiring these records.

R313-15-1107.  Records of Individual Monitoring Results.
	(1)  Recordkeeping Requirement.  Each licensee or registrant shall maintain records of doses received by all individuals for whom monitoring was required pursuant to Section R313-15-502, and records of doses received during planned special exposures, accidents, and emergency conditions.  Assessments of dose equivalent and records made using units in effect before January 1, 1994, need not be changed.  These records shall include, when applicable:
	(a)  The deep dose equivalent to the whole body, lens dose equivalent, shallow dose equivalent to the skin, and shallow dose equivalent to the extremities; and
	(b)  The estimated intake of radionuclides, see Section R313-15-202; and
	(c)  The committed effective dose equivalent assigned to the intake of radionuclides; and
	(d)  The specific information used to calculate the committed effective dose equivalent pursuant to Subsections R313-15-204(1) and R313-15-204(3) and when required by Section R313-15-502; and
	(e)  The total effective dose equivalent when required by Section R313-15-202; and
	(f)  The total of the deep dose equivalent and the committed dose to the organ receiving the highest total dose.
	(2)  Recordkeeping Frequency. The licensee or registrant shall make entries of the records specified in Subsection R313-15-1107(1) at intervals not to exceed one year.
	(3)  Recordkeeping Format.  The licensee or registrant shall maintain the records specified in Subsection R313-15-1107(1) on form DWMRC-06, in accordance with the instructions for form DWMRC-06, or in clear and legible records containing all the information required by form DWMRC-06.
	(4)  The licensee or registrant shall maintain the records of dose to an embryo/fetus with the records of dose to the declared pregnant woman.  The declaration of pregnancy, including the estimated date of conception, shall also be kept on file, but may be maintained separately from the dose records.
	(5)  The licensee or registrant shall retain each required form or record until the Director terminates each pertinent license or registration requiring the record.

R313-15-1108.  Records of Dose to Individual Members of the Public.
	(1)  Each licensee or registrant shall maintain records sufficient to demonstrate compliance with the dose limit for individual members of the public.  See Section R313-15-301.
	(2)  The licensee or registrant shall retain the records required by Subsection R313-15-1108(1) until the Director terminates each pertinent license or registration requiring the record.  Requirements for disposition of these records, prior to license termination, are located in Section R313-12-51 for activities licensed under these rules.

R313-15-1109.  Records of Waste Disposal.
	(1)  Each licensee or registrant shall maintain records of the disposal of licensed or registered materials made pursuant to Sections R313-15-1002, R313-15-1003, R313-15-1004, R313-15-1005, Rule R313-25, and disposal by burial in soil, including burials authorized before January 28, 1981.
	(2)  The licensee or registrant shall retain the records required by Subsection R313-15-1109(1) until the Director terminates each pertinent license or registration requiring the record.

R313-15-1110.  Records of Testing Entry Control Devices for Very High Radiation Areas.
	(1)  Each licensee or registrant shall maintain records of tests made pursuant to Subsection R313-15-603(2)(i) on entry control devices for very high radiation areas.  These records shall include the date, time, and results of each such test of function.
	(2)  The licensee or registrant shall retain the records required by Subsection R313-15-1110(1) for three years after the record is made.

R313-15-1111.  Form of Records.
	Each record required by Rule R313-15 shall be legible throughout the specified retention period. The record shall 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 or 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, shall include all pertinent information, such as stamps, initials, and signatures.  The licensee shall maintain adequate safeguards against tampering with and loss of records.

R313-15-1201.  Reports of Stolen, Lost, or Missing Licensed or Registered Sources of Radiation.
	(1)  Telephone Reports.  Each licensee or registrant shall report to the Director by telephone as follows:
	(a)  Immediately after its occurrence becomes known to the licensee or registrant, stolen, lost, or missing licensed or registered radioactive material in an aggregate quantity equal to or greater than 1,000 times the quantity specified in Appendix C of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference, under such circumstances that it appears to the licensee or registrant that an exposure could result to individuals in unrestricted areas;
	(b)  Within 30 days after its occurrence becomes known to the licensee or registrant, lost, stolen, or missing licensed or registered radioactive material in an aggregate quantity greater than ten times the quantity specified in Appendix C of 10 CFR 20.1001 to 20.2402, (2010), which is incorporated by reference, that is still missing.
	(c)  Immediately after its occurrence becomes known to the registrant, a stolen, lost, or missing radiation machine.
	(2)  Written Reports.  Each licensee or registrant required to make a report pursuant to Subsection R313-15-1201(1) shall, within 30 days after making the telephone report, make a written report to the Director setting forth the following information:
	(a)  A description of the licensed or registered source of radiation involved, including, for radioactive material, the kind, quantity, and chemical and physical form; and, for radiation machines, the manufacturer, model and serial number, type and maximum energy of radiation emitted;
	(b)  A description of the circumstances under which the loss or theft occurred; and
	(c)  A statement of disposition, or probable disposition, of the licensed or registered source of radiation involved; and
	(d)  Exposures of individuals to radiation, circumstances under which the exposures occurred, and the possible total effective dose equivalent to persons in unrestricted areas; and
	(e)  Actions that have been taken, or will be taken, to recover the source of radiation; and
	(f)  Procedures or measures that have been, or will be, adopted to ensure against a recurrence of the loss or theft of licensed or registered sources of radiation.
	(3)  Subsequent to filing the written report, the licensee or registrant shall also report additional substantive information on the loss or theft within 30 days after the licensee or registrant learns of such information.
	(4)  The licensee or registrant shall prepare any report filed with the Director pursuant to Section R313-15-1201 so that names of individuals who may have received exposure to radiation are stated in a separate and detachable portion of the report.

R313-15-1202.  Notification of Incidents.
	(1)  Immediate Notification.  Notwithstanding other requirements for notification, each licensee or registrant shall immediately report each event involving a source of radiation possessed by the licensee or registrant that may have caused or threatens to cause any of the following conditions:
	(a)  An individual to receive:
	(i)  A total effective dose equivalent of 0.25 Sv (25 rem) or more; or
	(ii)  A lens dose equivalent of 0.75 Sv (75 rem) or more; or
	(iii)  A shallow dose equivalent to the skin or extremities or a total organ dose equivalent of 2.5 Gy (250 rad) or more; or
	(b)  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 occupational ALI.  This provision does not apply to locations where personnel are not normally stationed during routine operations, such as hot-cells or process enclosures.
	(2)  Twenty-Four Hour Notification.  Each licensee or registrant shall, within 24 hours of discovery of the event, report to the Director each event involving loss of control of a licensed or registered source of radiation possessed by the licensee or registrant that may have caused, or threatens to cause, any of the following conditions:
	(a)  An individual to receive, in a period of 24 hours:
	(i)  A total effective dose equivalent exceeding 0.05 Sv (five rem); or
	(ii)  A lens dose equivalent exceeding 0.15 Sv (15 rem); or
	(iii)  A shallow dose equivalent to the skin or extremities or a total organ dose equivalent exceeding 0.5 Sv (50 rem); or
	(b)  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 ALI.  This provision does not apply to locations where personnel are not normally stationed during routine operations, such as hot-cells or process enclosures.
	(3)  The licensee or registrant shall prepare each report filed with the Director pursuant to Section R313-15-1202 so that names of individuals who have received exposure to sources of radiation are stated in a separate and detachable portion of the report.
	(4)  Licensees or registrants shall make the reports required by Subsections R313-15-1202(1) and R313-15-1202(2) to the Director by telephone, telegram, mailgram, or facsimile.
	(5)  The provisions of Section R313-15-1202 do not apply to doses that result from planned special exposures, provided such doses are within the limits for planned special exposures and are reported pursuant to Section R313-15-1204.

R313-15-1203.  Reports of Exposures, Radiation Levels, and Concentrations of Radioactive Material Exceeding the Constraints or Limits.
	(1)  Reportable Events.  In addition to the notification required by Section R313-15-1202, each licensee or registrant shall submit a written report within 30 days after learning of any of the following occurrences:
	(a)  Incidents for which notification is required by Section R313-15-1202; or
	(b)  Doses in excess of any of the following:
	(i)  The occupational dose limits for adults in Section R313-15-201; or
	(ii)  The occupational dose limits for a minor in Section R313-15-207; or
	(iii)  The limits for an embryo/fetus of a declared pregnant woman in Section R313-15-208; or
	(iv)  The limits for an individual member of the public in Section R313-15-301; or
	(v)  Any applicable limit in the license or registration; or
	(vi)  The ALARA constraints for air emissions established under Subsection R313-15-101(4); or
	(c)  Levels of radiation or concentrations of radioactive material in:
	(i)  A restricted area in excess of applicable limits in the license or registration; or
	(ii)  An unrestricted area in excess of ten times the applicable limit set forth in Rule R313-15 or in the license or registration, whether or not involving exposure of any individual in excess of the limits in Section R313-15-301; or
	(d)  For licensees subject to the provisions of U.S. Environmental Protection Agency's generally applicable environmental radiation standards in 40 CFR 190, levels of radiation or releases of radioactive material in excess of those standards, or of license conditions related to those standards.
	(2)  Contents of Reports.
	(a)  Each report required by Subsection R313-15-1203(1) shall describe the extent of exposure of individuals to radiation and radioactive material, including, as appropriate:
	(i)  Estimates of each individual's dose; and
	(ii)  The levels of radiation and concentrations of radioactive material involved; and
	(iii)  The cause of the elevated exposures, dose rates, or concentrations; and
	(iv)  Corrective steps taken or planned to ensure against a recurrence, including the schedule for achieving conformance with applicable limits, ALARA constraints, generally applicable environmental standards, and associated license or registration conditions.
	(b)  Each report filed pursuant to Subsection R313-15-1203(1) shall include for each occupationally overexposed individual: the name, Social Security account number, and date of birth.  With respect to the limit for the embryo/fetus in Section R313-15-208, the identifiers should be those of the declared pregnant woman.  The report shall be prepared so that this information is stated in a separate and detachable portion of the report.
	(3)  All licensees or registrants who make reports pursuant to Subsection R313-15-1203(1) shall submit the report in writing to the Director.

R313-15-1204.  Reports of Planned Special Exposures.
	The licensee or registrant shall submit a written report to the Director within 30 days following any planned special exposure conducted in accordance with Section R313-15-206, informing the Director that a planned special exposure was conducted and indicating the date the planned special exposure occurred and the information required by Section R313-15-1106.

R313-15-1205.  Reports to Individuals of Exceeding Dose Limits.
	When a licensee or registrant is required, pursuant to the provisions of Sections R313-15-1203 or R313-15-1204, to report to the Director any exposure of an identified occupationally exposed individual, or an identified member of the public, to sources of radiation, the licensee or registrant shall also provide the individual a written report on the exposure data included in the report to the Director.  This report shall be transmitted at a time no later than the transmittal to the Director.

R313-15-1206.  Reports of Transactions Involving Nationally Tracked Sources.
	Each licensee who manufactures, transfers, receives, disassembles, or disposes of a nationally tracked source shall complete and submit a National Source Tracking Transaction Report as specified in paragraphs (1) through (5) of this section for each type of transaction.
	(1)  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:
	(a)  The name, address, and license number of the reporting licensee;
	(b)  The name of the individual preparing the report;
	(c)  The manufacturer, model, and serial number of the source;
	(d)  The radioactive material in the source;
	(e)  The initial source strength in becquerels (curies) at the time of manufacture; and
	(f)  The manufacture date of the source.
	(2)  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:
	(a)  The name, address, and license number of the reporting licensee;
	(b)  The name of the individual preparing the report;
	(c)  The name and license number of the recipient facility and the shipping address;
	(d)  The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;
	(e)  The radioactive material in the source;
	(f)  The initial or current source strength in becquerels (curies);
	(g)  The date for which the source strength is reported;
	(h)  The shipping date;
	(i)  The estimated arrival date; and
	(j)  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.
	(3)  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:
	(a)  The name, address, and license number of the reporting licensee;
	(b)  The name of the individual preparing the report;
	(c)  The name, address, and license number of the person that provided the source;
	(d)  The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;
	(e)  The radioactive material in the source;
	(f)  The initial or current source strength in becquerels (curies);
	(g)  The date for which the source strength is reported;
	(h)  The date of receipt; and
	(i)  For material received under a Uniform Low-Level Radioactive Waste Manifest, the waste manifest number and the container identification with the nationally tracked source.
	(4)  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:
	(a)  The name, address, and license number of the reporting licensee;
	(b)  The name of the individual preparing the report;
	(c)  The manufacturer, model, and serial number of the source or, if not available, other information to uniquely identify the source;
	(d)  The radioactive material in the source;
	(e)  The initial or current source strength in becquerels (curies);
	(f)  The date for which the source strength is reported; and
	(g)  The disassemble date of the source.
	(5)  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:
	(a)  The name, address, and license number of the reporting licensee;
	(b)  The name of the individual preparing the report;
	(c)  The waste manifest number;
	(d)  The container identification with the nationally tracked source.
	(e)  The date of disposal; and
	(f)  The method of disposal.
	(6)  The reports discussed in paragraphs (1) through (5) 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:
	(a)  The on-line National Source Tracking System;
	(b)  Electronically using a computer-readable format;
	(c)  By facsimile;
	(d)  By mail to the address on the National Source Tracking Transaction Report Form (NRC Form 748); or
	(e)  By telephone with followup by facsimile or mail.
	(7)  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 (1) through (5) 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.
	(8)  Each licensee that possesses Category 1 nationally tracked sources shall report its initial inventory of Category 1 nationally tracked sources to the National Source Tracking System by November 15, 2007.  Each licensee that possesses Category 2 nationally tracked sources shall report its initial inventory of Category 2 nationally tracked sources to the National Source Tracking System by November 30, 2007.  The information may be submitted by using any of the methods identified by paragraph (6)(a) through (6)(d) of this section.  The initial inventory report must include the following information:
	(a)  The name, address, and license number of the reporting licensee;
	(b)  The name of the individual preparing the report;
	(c)  The manufacturer, model, and serial number of each nationally tracked source or, if not available, other information to uniquely identify the source;
	(d)  The radioactive material in the sealed source;
	(e)  The initial or current source strength in becquerels (curies); and
	(f)  The date for which the source strength is reported.

R313-15-1207.  Notifications and Reports to Individuals.
	(1)  Requirements for notification and reports to individuals of exposure to radiation or radioactive material are specified in Rule R313-18.
	(2)  When a licensee or registrant is required pursuant to Section R313-15-1203 to report to the Director any exposure of an individual to radiation or radioactive material, the licensee or registrant shall also notify the individual.  Such notice shall be transmitted at a time not later than the transmittal to the Director, and shall comply with the provisions of Rule R313-18.

R313-15-1301.  Vacating Premises.
	Each specific licensee or registrant shall, no less than 30 days before vacating or relinquishing possession or control of premises which may have been contaminated with radioactive material as a result of his activities, notify the Director in writing of intent to vacate.  When deemed necessary by the Director, the licensee shall decontaminate the premises in such a manner that the annual total effective dose equivalent to any individual after the site is released for unrestricted use should not exceed 0.1 mSv (0.01 rem)above background and that the annual total effective dose equivalent from any specific environmental source during decommissioning activities should not exceed 0.1 mSv (0.01 rem)above background.

KEY:  radioactive materials, contamination, waste disposal, safety
Date of Enactment or Last Substantive Amendment:  March 15, 2016
Notice of Continuation:  January 17, 2017
Authorizing, and Implemented or Interpreted Law:  19-3-104; 19-6-107