902 KAR 100:019. Standards for protection against radiation.

902 KAR 100:019. Standards for protection against radiation.

RELATES TO: KRS 211.842-211.852, 211.990(4), 10 C.F.R. 20.1001-20.1906, 20.2101-20.2204, 20.2206, Appendixes A, B-20.1001-20.2401, 40 C.F.R. 190, 49 C.F.R. 100-180, 173.403(m),(w), 173.421-173.424

STATUTORY AUTHORITY: KRS 13B.170, 194.050, 211.090, 211.844, 10 C.F.R. 10.1001-20.1906, 20.2101-20.2204, 20.2206, Appendixes A, B-20.1001-20.2401, 40 C.F.R. 190, 49 C.F.R. 100-180, 49 C.F.R. 173.403(m),(w), 173.421-173.424, EO 96-862

NECESSITY, FUNCTION, AND CONFORMITY: Executive Order 96-862, effective July 2, 1996, reorganizes the Cabinet for Human Resources and places the Department for Public Health and its programs under the Cabinet for Health Services. KRS 211.844 authorizes the Cabinet for Health Services to provide by administrative regulation for the registration and licensing of the possession or use of sources of ionizing or electronic product radiation and the handling and disposal of radioactive waste. This administrative regulation provides standards for the protection of the user and general public against radiation exposure and shall establish standards for protection against ionizing radiation resulting from activities conducted by persons issued licenses or registrations by the cabinet. This administrative regulation provides standards to control the receipt, possession, use, transfer, and disposal of sources of radiation by a person, licensee, or registrant so the total dose to an individual (including doses resulting from licensed and unlicensed radioactive material and radiation sources other than background radiation) shall not exceed the standards for protection against radiation prescribed in this administrative regulation. 902 KAR 100:020 and 902 KAR 100:025 are repealed due to the promulgation of new radiation standards by the U.S. Nuclear Regulatory Commission in 10 CFR 20.

Section 1. Radiation Protection Implementation. (1) This administrative regulation shall not limit actions required in order to protect against an immediate danger to public health and safety.

(2) This administrative regulation shall apply to a person licensed or registered by the cabinet to receive, possess, use, transfer, or dispose of sources of radiation.

(3) The limits in this administrative regulation shall not apply to doses due to background radiation, exposure of patients to radiation for the purpose of medical diagnosis or therapy, or voluntary participation in medical research programs.

Section 2. Radiation Protection Programs. A person, licensee, or registrant shall:

(1) Develop, document, and implement a radiation protection program commensurate with the scope and extent of their activities and sufficient to ensure compliance with the provisions of this administrative regulation.

(2) Use procedures and engineering controls based upon sound radiation protection principles to achieve occupational doses and doses to members of the public that shall be as low as reasonably achievable (ALARA) pursuant to 902 KAR 100:015, Section 2.

(3) Annually review the radiation protection program content and implementation.

(4) Establish a constraint on air emissions of radioactive material to the environment, excluding radon-222 and its daughters, to implement the ALARA requirements of subsection (2) of this section and in addition to the requirements of Section 10 of this administrative regulation.

(a) These constraints shall be established so 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 ten (10) millirems (0.1 mSv) per year from these emissions.

(b) A licensee, if required to establish these constraints, shall report an exceedance as provided in Section 40 of this administrative regulation and take appropriate corrective action to ensure against recurrence.

Section 3. Occupational Dose Limits for Adults. (1) A person, licensee, or registrant shall control the occupational dose to individual adults, except for planned special exposures as described in Section 7 of this administrative regulation, to the following dose limits:

(a) An annual limit, which shall be the more limiting of the:

1. Total effective dose equivalent being equal to five (5) rems (0.05 sievert (Sv)); or

2. Sum of the deep-dose equivalent and the committed dose equivalent to an individual organ or tissue other than the lens of the eye being equal to fifty (50) rems (five-tenths (0.50) Sv).

(b) The annual limits to the lens of the eye, the skin, and the extremities shall be:

1. An eye dose equivalent of fifteen (15) rems (0.15 Sv); and

2. A shallow-dose equivalent of fifty (50) rems (five-tenths (0.50) Sv) to the skin or to each of the extremities.

(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 as described in Section 7(3)(a) and (b) of this administrative regulation.

(3) The assigned deep-dose equivalent and shallow-dose equivalent shall be for the part of the body receiving the highest exposure. If the individual monitoring device was not in the region of highest potential exposure, or the results of individual monitoring are unavailable, the deep-dose equivalent, eye 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.

(4) Derived air concentration (DAC) and annual limit on intake (ALI) values are presented in Section 44 of this administrative regulation and shall be used to:

(a) Determine the individual's dose as required in Section 34 of this administrative regulation; and

(b) Demonstrate compliance with the occupational dose limits.

(5) In addition to the annual dose limits, the person, licensee, or registrant shall limit the soluble uranium intake by an individual to ten (10) milligrams in a week in consideration of chemical toxicity (see footnote 3 in Section 44 of this administrative regulation).

(6) A person, 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 a person as described in Section 32 of this administrative regulation.

Section 4. Compliance with Requirements for Summation of External and Internal Doses. (1) If a licensee or registrant is required to monitor by both Section 13(1) and (2) of this administrative regulation, the licensee or registrant shall demonstrate compliance with the dose limits by summing external and internal doses.

(2) If a licensee or registrant is required to monitor only by Section 13(1) or (2) of this administrative regulation, summation shall not be required to demonstrate compliance with the dose limits.

(3) A licensee or registrant may demonstrate compliance with the requirements for summation of external and internal doses by meeting one (1) of the conditions specified in subsection (5) of this section and the conditions in subsections (6) and (7) of this section.

(4) The dose equivalents for the lens of the eye, the skin, and the extremities shall not be included in the summation, but shall be subject to separate limits.

(5) If the only intake of radionuclides occurs by inhalation, the total effective dose equivalent limit shall not be exceeded if the sum of the deep-dose equivalent divided by the total effective dose equivalent limit, and one (1) of the following, does not exceed unity:

(a) Sum of the fractions of the inhalation ALI for each radionuclide;

(b) Total number of derived air concentration-hours (DAC-hours) for radionuclides divided by 2,000; or

(c) Sum of the calculated committed effective dose equivalents to significantly irradiated organs or tissues (T) calculated from bioassay data using appropriate biological models and expressed as a fraction of the annual limit.

(6) If the occupationally exposed individual also receives an intake of radionuclides by oral ingestion greater than ten (10) percent of the applicable oral ALI, the licensee or registrant shall account for this intake and include it in demonstrating compliance with the limits.

(7) A 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 may not need to be further evaluated.

Section 5. Determination of External Dose from Airborne Radioactive Material. (1) If determining the dose from airborne radioactive material, a licensee or registrant shall include the contribution to the deep-dose equivalent, eye dose equivalent, and shallow-dose equivalent from external exposure to the radioactive cloud.

(2) If the airborne radioactive material includes radionuclides other than noble gases or the cloud of airborne radioactive material is not relatively uniform, airborne radioactivity measurements and DAC values shall not be used as the primary means to assess the deep-dose equivalent.

(3) The determination of the deep-dose equivalent to an individual shall be based upon measurements using instruments or individual monitoring devices.

Section 6. Determination of Internal Exposure. (1) For purposes of assessing dose used to determine compliance with occupational dose equivalent limits, the licensee or registrant shall, if required by Section 13 of this administrative regulation, take suitable and timely measurements of:

(a) Concentrations of radioactive materials in the air in work areas;

(b) Quantities of radionuclides in the body;

(d) Combinations of these measurements.

(2) A licensee or registrant shall assume an individual inhales radioactive material at the airborne concentration in which the individual is present, unless respiratory protective equipment is used, as provided in Section 19 of this administrative regulation, or the assessment of intake is based on bioassays.

(3) If specific information on the physical and biochemical properties of the radionuclides taken into the body, or the behavior or material in an individual is known, a licensee or registrant may:

(a) Use the information to calculate the committed effective dose equivalent; and, if used, the licensee or registrant shall document the information in the individual's record;

(b) Upon prior approval by the cabinet, 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 radionuclide, as provided in Section 44 of this administrative regulation, to the committed effective dose equivalent.

(4) If a licensee or registrant chooses to assess intakes of Class Y material using the measurements provided in subsection (1)(b) or (c) of this section, the licensee or registrant may delay the recording and reporting of the assessments for periods up to seven (7) months, unless otherwise required by Sections 39 or 40 of this administrative regulation, in order to permit the licensee or registrant to make additional measurements basic to the assessments.

(5) If the identity and concentration of radionuclides in a mixture are known, the fraction of the DAC applicable to the mixture for use in calculating DAC-hours shall be the:

(a) Sum of the ratios of the concentration to the appropriate DAC value (e.g., D, W, Y) from Section 44 of this administrative regulation for radionuclides in the mixture; or

(b) Ratio of the total concentration for radionuclides in the mixture to the most restrictive DAC value for a radionuclide in the mixture.

(6) If the identity of radionuclides in a mixture is known, but the concentration of one (1) or more of the radionuclides in the mixture is not known, the DAC for the mixture shall be the most restrictive DAC of a radionuclide in the mixture.

(7) If a mixture of radionuclides in air exists, a licensee or registrant may disregard certain radionuclides in the mixture if the:

(a) Licensee or registrant uses the total activity of the mixture in demonstrating compliance with the dose limits in Section 3 of this administrative regulation and in complying with the monitoring requirements in Section 13(2) of this administrative regulation;

(b) Concentration of a disregarded radionuclide is less than ten (10) percent of its DAC; and

(8) In order to calculate the committed effective dose equivalent, a licensee or registrant may assume that the inhalation of one (1) ALI, or an exposure of 2,000 DAC-hours, results in a committed effective dose equivalent of five (5) rems (0.05 Sv) for radionuclides having their ALIs or DACs based on the committed effective dose equivalent.

(a) If the ALI, and the associated DAC, is determined by the nonstochastic organ dose limit of fifty (50) rems (five-tenths (0.50) Sv), the intake of radionuclides that result in a committed effective dose equivalent of five (5) rems (0.05 Sv) (the stochastic ALI) is listed in parentheses in Section 44 of this administrative regulation. A licensee or registrant may, as a simplifying assumption, use the stochastic ALIs to determine committed effective dose equivalent.

(b) If a licensee or registrant uses the stochastic ALIs, the licensee or registrant shall also demonstrate that the limit in Section 3(1)(a)2 of this administrative regulation shall be met.

Section 7. Planned Special Exposures. (1) 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 3 of this administrative regulation provided each of the following conditions are satisfied:

(a) The licensee or registrant authorizes a planned special exposure only in an exceptional situation if alternatives that may avoid the higher exposure are unavailable or impractical;

(b) The licensee or registrant, and employer if the employer is not the licensee or registrant, specifically authorize the planned special exposure, in writing, before the exposure occurs;

1. Informed of the purpose of the planned operation;

2. Informed of the estimated doses and associated potential risks and specific radiation levels or other conditions that may be involved in performing the task; and

3. Instructed in the measures to be taken to keep the dose ALARA considering other risks that may be present.

(2) Prior to permitting an individual to participate in a planned special exposure, a licensee or registrant shall ascertain prior doses as required by Section 32(2) of this administrative regulation during the lifetime of the individual for each individual involved.

(3) Subject to Section 3(2) of this administrative regulation, a licensee or registrant shall not authorize a planned special exposure that shall cause an individual to receive a dose from planned special exposures and doses in excess of the limits to exceed:

(a) The numerical values of the dose limits in Section 3(1) of this administrative regulation in a year; and

(b) Five (5) times the annual dose limits in Section 3(1) of this administrative regulation during the individual's lifetime.

(4) A licensee or registrant shall:

(a) Maintain records of the conduct of a planned special exposure pursuant to Section 33 of this administrative regulation; and

(b) Submit a written report pursuant to Section 41 of this administrative regulation.

(5) A licensee or registrant shall record the best estimate of the dose resulting from the planned special exposure in the individual's record and inform the individual, in writing, of the dose within thirty (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 by Section 3(1) of this administrative regulation, but shall be included in evaluations required by Section 7(2) and (3) of this administrative regulation.

Section 8. Occupational Dose Limits for Minors. The annual occupational dose limits for minors shall be ten (10) percent of the annual dose limits specified for adult workers in Section 3 of this administrative regulation.

Section 9. Dose to an Embryo or Fetus. (1) A licensee or registrant shall ensure that the dose to an embryo or fetus during the entire pregnancy, due to occupational exposure of a declared pregnant woman, does not exceed five-tenths (0.5) rem (5 mSv).

(2) A licensee or registrant shall make efforts to avoid substantial variation above a uniform monthly exposure rate to a declared pregnant woman to satisfy the limit in subsection (1) of this section.

(3) The dose to an embryo or fetus shall be taken as the sum of:

(a) The deep-dose equivalent to the declared pregnant woman; and

(b) The dose to the embryo or fetus from radionuclides in the embryo or fetus and radionuclides in the declared pregnant woman.

(4) If the dose to the embryo or fetus is found to have exceeded five-tenths (0.5) rem (five (5) mSv), or is within 0.05 rem (five-tenths (0.5) mSv) of this dose, by the time the woman declares the pregnancy to a licensee or registrant, the licensee or registrant shall be in compliance with subsection (1) of this section if the additional dose to the embryo or fetus does not exceed 0.05 rem (five-tenths (0.5) mSv) during the remainder of the pregnancy.

Section 10. Radiation Dose Limits for Individual Members of the Public. (1) A licensee or registrant shall conduct operations to ensure:

(a) The total effective dose equivalent to individual members of the public from licensed, registered, and other operations shall not exceed one-tenth (0.1) rem (one (1) mSv) in a year, exclusive of the dose contributions from:

1. Background radiation;

2. A medical administration the individual received;

3. An exposure to individuals administered radioactive material and released in accordance with 902 KAR 100:073, Section 25;

4. Voluntary participation in medical research programs; and

5. The licensee's or registrant's disposal of radioactive material into sanitary sewerage under 902 KAR 100:021, Section 3; and

(b) The dose in an unrestricted area from external sources, exclusive of the dose contributions from patients administered radioactive material and released in accordance with 902 KAR 100:073, Section 25, shall not exceed 0.002 rem (0.02 mSv) in one (1) hour.

(2) If a licensee or registrant permits members of the public to have access to controlled areas, the limits for members of the public shall continue to apply to those individuals.

(3) A licensee, registrant, or applicant for a license or registration may apply for prior authorization to operate up to an annual dose limit for an individual member of the public of five-tenths (0.5) rem (five (5) mSv). The 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 (1) of this section;

(b) A licensee's or registrant's program to assess and control dose within the five-tenths (0.5) rem (five (5) mSv) annual limit; and

(4) In addition to the provisions of this administrative regulation, a person, licensee, or registrant subject to the provisions of U.S. Environmental Protection Agency's applicable environmental radiation standards in 40 CFR 190 shall comply with those standards.

(5) The cabinet 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.

Section 11. Compliance with Dose Limits for Individual Members of the Public. (1) To demonstrate compliance with the dose limits for individual members of the public in Section 10 of this administrative regulation, a licensee or registrant shall make or cause to be made, as appropriate, surveys of:

(a) Radiation levels in unrestricted and controlled areas; and

(b) Radioactive materials in effluents released to unrestricted and controlled areas.

(2) A licensee or registrant shall show compliance with the annual dose limit in Section 10 of this administrative regulation 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 operation shall not exceed the annual dose limit; or

(b) Demonstrating that:

1. The annual average concentrations of radioactive material released in gaseous and liquid effluents at the boundary of the restricted area shall not exceed the values specified in Section 44(9), Table II, of this administrative regulation; and

2. If an individual were continually present in an unrestricted area, the dose from external sources shall not exceed 0.002 rem (0.02 mSv) in an hour and 0.05 rem (five-tenths (0.5) mSv) in a year.

(3) Upon approval from the cabinet, a licensee or registrant may adjust the effluent concentration values in Section 44(9), Table II, of this administrative regulation, for members of the public, to take into account the actual physical and chemical characteristics of the effluents (for example, aerosol size distribution, solubility, density, radioactive decay equilibrium, or chemical form).

Section 12. Surveys and Monitoring. (1) A licensee or registrant shall make or cause to be made, surveys that are:

(a) Necessary for the licensee or registrant to comply with the provisions in this administrative regulation; and

(b) Reasonable under the circumstances to evaluate:

1. The extent of radiation levels;

2. Concentrations or quantities of radioactive material; and

3. The potential radiological hazards that may be present.

(2) A licensee or registrant shall ensure that instruments and equipment used for quantitative radiation measurements (for example, dose rate and effluent monitoring) are calibrated periodically for the radiation measured.

(3) Personnel dosimeters, except direct and indirect reading pocket ionization chambers and those dosimeters used to measure the dose to the extremities, that require processing to determine the radiation doses used by licensees or registrants to comply with Section 3 of this administrative regulation, other applicable provisions of 902 KAR Chapter 100, or conditions specified in a license 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.

Section 13. Conditions Requiring Individual Monitoring of External and Internal Occupational Dose. (1) A licensee or registrant shall monitor exposures to radiation and radioactive material at levels sufficient to demonstrate compliance with the occupational dose limits of this administrative regulation. As a minimum, the licensee or registrant shall monitor occupational exposure to radiation, and shall supply and require the use of individual monitoring devices by:

(a) Adults likely to receive, in one (1) year from sources external to the body, a dose in excess of ten (10) percent of the limits in Section 3(1) of this administrative regulation;

(b) Minors and declared pregnant women likely to receive, in one (1) year from sources external to the body, a dose in excess of ten (10) percent of the applicable limits in Sections 8 or 9 of this administrative regulation; and

(2) A licensee or registrant shall monitor, pursuant to Section 6 of this administrative regulation, the occupational intake of radioactive material by, and assess the committed effective dose equivalent to:

(a) Adults likely to receive, in one (1) year, an intake in excess of ten (10) percent of the applicable ALIs in Section 44(9), Table I, Columns 1 and 2, of this administrative regulation; and

(b) Minors and declared pregnant women likely to receive, in one (1) year, a committed effective dose equivalent in excess of 0.05 rem (five-tenths (0.5) mSv).

Section 14. Control of Access to High Radiation Areas. (1) A licensee or registrant shall ensure that each entrance or access point to a high radiation area shall have at least one (1) of the following features:

(a) A control device that, upon entry into the area, shall cause the level of radiation to be reduced below the level an individual may receive a deep-dose equivalent of one-tenth (0.1) rem (one (1) mSv) in one (1) hour at thirty (30) centimeters from the radiation source or from a surface that the radiation penetrates;

(b) A control device that shall energize a conspicuous visible or audible alarm signal so the individual entering the high radiation area and the supervisor of the activity shall be made aware of the entry; or

(c) Entryways that shall be locked, except during periods that access to the areas is required, with positive control over each individual entry.

(2) In place of the controls required by subsection (1) of this section for a high radiation area, a licensee or registrant may substitute continuous direct or electronic surveillance that shall be capable of preventing unauthorized entry.

(3) A licensee or registrant may apply to the cabinet for approval of alternative methods for controlling access to high radiation areas.

(4) A licensee or registrant shall establish the controls required by subsections (1) and (3) of this section that shall not prevent individuals from leaving a high radiation area.

(5) Control shall not be required for an 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 49 CFR 100-180 if the packages will not remain in the area longer than three (3) days, and the dose rate at one (1) meter from the external surface of a package will not exceed 0.01 rem (one-tenth (0.1) mSv) per hour.

(6) Control of entrance or access to rooms or other areas in hospitals shall not be required solely because of the presence of patients containing radioactive material if personnel are in attendance who:

(a) Take the necessary precautions to prevent the exposure of individuals to radiation or radioactive material in excess of the limits established in this administrative regulation; and

(b) Operate within the ALARA provisions of the licensee's or registrant's radiation protection program.

(7) A 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 this section if the registrant has met the specific requirements for access and control specified in 902 KAR 100:100, 902 KAR 100:115, and 902 KAR 100:155.

Section 15. Control of Access to Very High Radiation Areas. (1) In addition to the provisions in Section 14 of this administrative regulation, a licensee or registrant shall institute additional measures to ensure that an individual shall not be able to gain unauthorized or inadvertent access to areas in which radiation levels may be encountered at 500 rads (five (5) grays) or more in one (1) hour at one (1) meter from a radiation source or a surface through which the radiation penetrates.

(2) A registrant shall not be 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 (1) of this section if the registrant has met the specific requirements for access and control specified in 902 KAR 100:100, 902 KAR 100:115, and 902 KAR 100:155.

Section 16. Control of Access to Very High Radiation Areas for Irradiators. (1) This section shall apply to radiation from sources of radiation used in sealed sources in nonself-shielded irradiators.

(2) This section shall not apply to:

(a) Sources of radiation used in teletherapy, radiography, or completely self-shielded irradiators in which the source:

1. Is both stored and operated within the same shielding radiation barrier; and

2. In the designed configuration of the irradiator, is always physically inaccessible to an individual and cannot create high levels of radiation in an area that is accessible to an individual.

(b) Sources from which the radiation shall be incidental to some other use or to nuclear reactor-generated radiation.

(3) Areas where radiation levels may exist in excess of 500 rads (five (5) grays) in one (1) hour at one (1) meter from a source of radiation used to irradiate materials shall meet the following requirements.

(a) An entrance or access point shall be equipped with entry control devices which:

1. Function automatically to prevent an individual from inadvertently entering the area if very high radiation levels exist;

2. 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 a level where it is possible for an individual to receive a deep-dose equivalent in excess of one-tenth (0.1) rem (one (1) mSv) in one (1) hour; and

3. Prevent operation of the source of radiation if the source would produce radiation levels in the area that may result in a deep-dose equivalent to an individual in excess of one-tenth (0.1) rem (one (1) mSv) in one (1) hour.

(b) Additional control devices shall be provided so that, upon failure of the entry control devices to function as required by subsection (3)(a) of this section:

1. The radiation level within the area, from the source of radiation, is reduced below a level where it is possible for an individual to receive a deep-dose equivalent in excess of one-tenth (0.1) rem (one (1) mSv) in one (1) hour; and

2. 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 (1) 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) A licensee or registrant shall provide control devices so that, upon failure or removal of physical radiation barriers other than the source's shielded storage container:

1. The radiation level from the source of radiation shall be reduced below a level where it is possible for an individual to receive a deep-dose equivalent in excess of one-tenth (0.1) rem (one (1) mSv) in one (1) hour; and

2. Conspicuous visible and audible alarm signals shall be generated to make potentially affected individuals aware of the hazard, and a licensee, registrant, or at least one (1) 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) If the shield for the stored source is a liquid, the licensee or registrant shall provide means to:

1. Monitor the integrity of the shield; and

2. Automatically signal 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 paragraphs (c) and (d) of this subsection;

(f) An area shall be equipped with devices that automatically generate conspicuous visible and audible alarm signals:

1. To alert personnel in the area before the source can be put into operation;

2. In sufficient time for an individual in the area to operate a clearly identified control device, which is installed in the area and can prevent the source from being put into operation;

(g) An area shall be controlled by use of administrative procedures and devices as are necessary to ensure that the area is cleared of personnel prior to use of the source;

(h) An area shall be checked by a radiation measurement to ensure that, prior to the first individual's entry into the area after use of the source of radiation, the radiation level from the source of radiation in the area is below a level where it is possible for an individual to receive a deep-dose equivalent in excess of one-tenth (0.1) rem (one (1) mSv) in one (1) hour;

(i) The entry control devices required in paragraph (a) of this subsection shall have been tested for proper functioning as follows:

1. Daily prior to initial operation with the source of radiation, unless operations were continued uninterrupted from a previous day;

2. Prior to resumption of operation of the source of radiation after an unintended interruption; and

3. By adherence to a submitted schedule for periodic tests of the entry control and warning systems.

(j) A licensee or registrant shall not conduct operations if control devices are not functioning properly, other than those necessary to place the source of radiation in safe condition or to effect repairs on controls;

(k) Entry and exit portals used in transporting materials to and from the irradiation area, and not intended for use by individuals, shall be controlled by devices and administrative procedures as are necessary to physically protect and warn against inadvertent entry by an individual through these portals. Exit portals for processed materials shall be equipped to detect and signal the presence of loose radiation sources carried toward an exit to automatically prevent loose radiation sources from being carried out of the area.

(4)(a) Persons holding licenses or registrations, or applicants for licenses or registrations, for radiation sources may apply to the cabinet for approval of the use of alternative safety measures if they:

1. Are governed by the provisions of subsection (3) of this section; and

2. May be used in a variety of positions or in locations, such as open fields or forests, that make it impracticable to comply with provisions of subsection (3) of this section (for example, those for the automatic control of radiation levels).

(b) Alternative safety measures shall provide a degree of personnel protection equivalent to those specified in subsection (3) of this section.

(c) At least one (1) 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 may gain access to the area in which sources of radiation are used.

(5) Entry control devices required by subsections (3) and (4) of this section shall be established in a way that an individual will not be prevented from leaving the area.

Section 17. Use of Process or Other Engineering Controls. The licensee or registrant shall use, to the extent practicable, process or other engineering controls (for example, containment or ventilation) to control the concentrations of radioactive material in air.

Section 18. Use of Other Controls. If it is not practicable to apply process or other engineering controls to control the concentrations of radioactive material in air to values below those that define an airborne radioactivity area, a licensee or registrant shall, consistent with maintaining the total effective dose equivalent ALARA, increase monitoring and limit intakes by one (1) or more of the following means:

(1) Control of access;

(2) Limitation of exposure times;

(3) Use of respiratory protection equipment; or

(4) Other controls approved by the cabinet.

Section 19. Use of Individual Respiratory Protection Equipment. (1) If a licensee or registrant uses respiratory protection equipment to limit intakes pursuant to Section 18 of this administrative regulation, the licensee or registrant shall use only respiratory protection equipment that shall be tested and certified or shall have had certification extended by the National Institute for Occupational Safety and Health/Mine Safety and Health Administration (NIOSH/MSHA).

(a) If a licensee or registrant wishes to use equipment that has not been tested or certified by NIOSH/MSHA, has not had certification extended by NIOSH/MSHA, or for which there exists no schedule for testing or certification, the licensee shall submit:

1. An application for authorized use of that equipment, including a demonstration by testing; or

2. A demonstration on the basis of reliable test information that the material and performance characteristics of the equipment shall be capable of providing the proposed degree of protection under anticipated conditions of use;

(b) A licensee or registrant shall implement and maintain a respiratory protection program that shall include:

1. Air sampling sufficient to identify the potential hazard, permit proper equipment selection, and estimate exposures;

2. Surveys and bioassays, as appropriate, to evaluate actual intakes;

3. Testing of respirators for operability immediately prior to each use;

4. Written procedures regarding:

a. Selection, fitting, issuance, maintenance, and testing of respirators, including testing for operability immediately prior to use;

b. Supervision and training of personnel;

c. Monitoring, including air sampling and bioassays; and

d. Recordkeeping; and

5. Determination by a physician prior to initial fitting of respirators, and either every twelve (12) months or at a frequency determined by a physician, that the individual user shall be physically able to use the respiratory protection equipment;

1. Use of process or other engineering controls, instead of respirators;

2. Routine, nonroutine, and emergency use of respirators; and

3. Periods of respirator use and relief from respirator use;

(d) A licensee or registrant shall advise a respirator user that the user may leave the area for relief from respirator use in the event of:

1. Equipment malfunction;

2. Physical or psychological distress;

3. Procedural or communication failure;

4. Significant deterioration of operating conditions; or

5. Other conditions that may require relief; and

(e) A licensee or registrant shall:

1. Use equipment within limitations for type and mode of use; and

2. If needed, provide proper visual, communication, and other special capabilities such as adequate skin protection.

(2) In estimating exposure of individuals to airborne radioactive materials, a licensee or registrant may make allowance for respiratory protection equipment used to limit intakes under Section 18 of this administrative regulation, if the following conditions, in addition to those in subsection (1) of this section, are satisfied:

(a) The licensee or registrant selects respiratory protection equipment that provides a protection factor greater than the multiple by which peak concentrations of airborne radioactive materials in the working area are expected to exceed the values specified in Section 44(9), Table I, Column 3, of this administrative regulation.

1. If the selection of a respiratory protection device with a protection factor greater than the peak concentration is inconsistent with the goal specified in Section 18 of this administrative regulation of keeping the total effective dose equivalent ALARA, the licensee or registrant may select respiratory protection equipment with a lower protection factor only if the selection would result in keeping the total effective dose equivalent ALARA;

2. The concentration of radioactive material in air that is inhaled if respirators are worn may be initially estimated by dividing the average concentration in air during each period of uninterrupted use by the protection factor;

3. If the exposure is later found to be greater than estimated, the corrected value shall be used; and

4. If the exposure is later found to be less than estimated, the corrected value may be used; and

(b) The licensee or registrant shall obtain authorization from the cabinet before assigning respiratory protection factors in excess of those specified in Section 43 of this administrative regulation. The cabinet may authorize the licensee or registrant to use higher protection factors on receipt of an application that:

1. Describes the situation for which a need exists for higher protection factors; and

2. Demonstrates the respiratory protection equipment provides these higher protection factors under the proposed conditions of use.

(3) A licensee or registrant shall use as emergency devices only respiratory protection equipment that has been specifically certified or had certification extended for emergency use by NIOSH/MSHA.

(4) A licensee or registrant shall notify, in writing, the Manager of the Radiation Control Branch at least thirty (30) days before the date that respiratory protection equipment will first be used under the provisions of either subsection (1) or (2) of this section.

Section 20. Further Restrictions on the Use of Respiratory Protection Equipment. The cabinet may impose restrictions in addition to those in Sections 18, 19, and 43 of this administrative regulation to:

(1) Ensure that the respiratory protection program of the licensee shall be adequate to limit exposures of individuals to airborne radioactive materials; and

(2) Limit the extent to which a licensee shall use respiratory protection equipment instead of process or other engineering controls.

Section 21. Security of Sources of Radiation. A licensee or registrant shall secure from unauthorized removal or access licensed materials stored in controlled or unrestricted areas.

Section 22. Control of Sources of Radiation Not in Storage. A licensee or registrant shall control and maintain constant surveillance of licensed or registered material in a controlled or unrestricted area and not in storage.

Section 23. Caution Signs and Standard Radiation Symbol. (1) Unless otherwise authorized by the cabinet, the symbol prescribed by this section shall use the colors magenta, purple, or black on yellow background. The symbol prescribed by this section shall be the three (3) bladed design:

RADIATION SYMBOL

(a) Cross-hatched area shall be magenta, purple, or black; and

(b) The background shall be yellow.

(2) Exception to color requirements for standard radiation symbol. A licensee or registrant may label sources, source holders, or device components containing sources of radiation 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 this section, a licensee or registrant may provide, on or near the required signs and labels, additional information, as appropriate, to make individuals aware of potential radiation exposures and to minimize the exposures.

Section 24. Posting Requirements. (1) Posting of radiation areas. A licensee or registrant shall post a radiation area with a conspicuous sign or signs bearing the radiation symbol and the words: "CAUTION, RADIATION AREA".

(2) Posting of high radiation areas. A licensee or registrant shall post a 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. A licensee or registrant shall post a 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. A licensee or registrant shall post an 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 shall be used or stored. A licensee or registrant shall post an area or room in which there is used or stored an amount of licensed or registered material exceeding ten (10) times the quantity of the material specified in 902 KAR 100:030, Section 2, with a conspicuous sign or signs bearing the radiation symbol and the words "CAUTION, RADIOACTIVE MATERIAL(S)" or "DANGER, RADIOACTIVE MATERIAL(S)".

Section 25. Exceptions to Posting Requirements. (1) A licensee or registrant shall not be required to post caution signs in areas or rooms containing sources of radiation for periods of less than eight (8) hours, if the following conditions are 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 radiation or radioactive materials in excess of the limits established in this administrative regulation; and

(b) The area or room are subject to the licensee's or registrant's control.

(2) Rooms or other areas in hospitals occupied by patients shall not be required to be posted with caution signs pursuant to Section 24 of this administrative regulation if the patient could be released from licensee control in accordance with 902 KAR 100:073, Section 25.

(3) A room or area is not required to be posted with a caution sign because of the presence of a sealed source if the radiation level at thirty (30) centimeters from the surface of the source container or housing does not exceed 0.005 rem (0.05 mSv) per hour.

Section 26. Labeling Containers. (1) A licensee or registrant shall ensure a container of licensed or registered material bears a durable, clearly visible label with the radiation symbol and the words "CAUTION, RADIOACTIVE MATERIAL" or "DANGER, RADIOACTIVE MATERIAL".

(a) The label shall provide the following information:

1. Radionuclide present;

2. An estimate of the quantity of radioactivity;

3. Date the activity is estimated;

4. Radiation levels, kinds of materials; and

5. Mass enrichment.

(b) Information in this subsection shall permit individuals handling or using the containers, or working in the vicinity of the containers, to take precautions to avoid or minimize exposures.

(2) A licensee or registrant shall, prior to removal or disposal of empty uncontaminated containers to unrestricted areas:

1. Remove or deface the radioactive material label; or

2. Clearly indicate the container no longer contains radioactive materials.

Section 27. Exemptions to Labeling Requirements. (1) A licensee or registrant shall not be required to label:

(a) Containers holding licensed or registered material in quantities less than the quantities listed in 902 KAR 100:030, Section 2;

(b) Containers holding licensed or registered material in concentrations less than those specified in Section 44(9), Table III, of this administrative regulation;

(c) Containers attended by an individual who takes precautions necessary to prevent the exposure of individuals in excess of the limits established by this administrative regulation;

(d) Containers if they are in transport and packaged and labeled in accordance with 49 CFR Parts 100-180; or

(e) Containers that are accessible only to individuals authorized to handle or use them, or to work in the vicinity of the containers, if the contents are identified to these individuals by a readily available written record (for example, containers in locations that include 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

(f) Installed manufacturing or process equipment, such as chemical process equipment, piping, and tanks;

(2) Labeling of packages containing radioactive materials shall be required by the U.S. Department of Transportation (DOT) if the amount and type of radioactive material exceeds the limits for an excepted quantity or article pursuant to 49 CFR 173.403(m) and (w) and 173.421-173.424.

Section 28. Procedures for Receiving and Opening Packages. (1) A licensee or registrant who expects to receive a package containing quantities of radioactive material in excess of a Type A quantity pursuant to 902 KAR 100:010 shall make arrangements to receive:

(a) The package if the carrier offers it for delivery; or

(b) Notification of the arrival of the package at the carrier's terminal and take possession of the package expeditiously.

(2)(a) A licensee or registrant shall monitor the external surfaces of a labeled package for:

1. Radioactive contamination unless the package contains only radioactive material in the form of a gas or in special form as defined in 902 KAR 100:010;

2. Radiation levels unless the package contains quantities of radioactive material that are less than or equal to the Type A quantity defined in 902 KAR 100:010; and

(b) All packages known to contain radioactive material for radioactive contamination and radiation levels if there is evidence of potential contamination such as packages that are crushed, wet, or damaged.

(3) A licensee or registrant shall perform the monitoring required by subsection (2) of this section as soon as practicable after receipt of the package, but not later than:

(a) Three (3) hours after the package is received at the licensee's facility if received during the licensee's or registrant's normal working hours; or

(b) Three (3) hours from the beginning of the next working day if received after working hours.

(4) A licensee or registrant shall immediately notify the final delivery carrier and, by telephone, telegram, mailgram, or facsimile, the Manager of the Radiation Control Branch if:

(a) Removable radioactive surface contamination exceeds the limits of 902 KAR 100:070, Section 14; or

(b) External radiation levels exceed the limits of 902 KAR 100:070, Section 14.

(5) A 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 due consideration is given to special instructions for the type of package being opened.

(6) A licensee or registrant transferring special form sources in licensee or registrant owned or operated vehicles to and from a work site shall be exempt from the contamination monitoring requirements of subsection (2) of this section, but shall not be exempt from the survey requirement for measuring radiation levels that are required to ensure the source shall remain properly lodged in its shield.

Section 29. General Provisions for Records. (1) A licensee or registrant shall use the units curie, rad, and rem, including multiples and subdivisions, and shall clearly indicate the units of quantities on records required by this administrative regulation.

(2) A licensee or registrant shall make a clear distinction among the quantities entered on the records required by this administrative regulation, such as:

(a) Total effective dose equivalent;

(b) Shallow-dose equivalent;

(d) Deep-dose equivalent; and

(e) Committed effective dose equivalent.

Section 30. Records of Radiation Protection Programs. (1) A 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) A licensee or registrant shall retain records required by subsection (1)(a) of this section until the cabinet terminates each pertinent license requiring the record.

(3) A licensee or registrant shall retain records required by subsection (1)(b) of this section for three (3) years after the record is made.

Section 31. Records of Surveys. (1) A licensee or registrant shall:

(a) Maintain records showing the results of surveys and calibrations required by Sections 12 and 28(2) of this administrative regulation; and

(b) Retain records for three (3) years after the record is made.

(2) A licensee or registrant shall retain the following records until the cabinet terminates the pertinent license or registration requiring the record:

(a) Results of surveys to determine the dose from external sources of radiation and used, in the absence of or in combination with individual monitoring data, in the assessment of individual dose equivalents;

(b) Results of measurements and calculations used to determine individual intakes of radioactive material and used in the assessment of internal dose;

(c) Results of air sampling, surveys, and bioassays required pursuant to Section 19(1)(c)1 and 2 of this administrative regulation; and

(d) Results of measurements and calculations used to evaluate the release of radioactive effluents to the environment.

Section 32. Determination of Prior Occupational Dose. (1) For an individual likely to receive, in a year, an occupational dose requiring monitoring under Section 13 of this administrative regulation, the licensee or registrant shall:

(a) Determine the occupational radiation dose received during the current year; and

(b) Attempt to obtain the records of lifetime cumulative occupational radiation dose.

(2) Prior to permitting an individual to participate in a planned special exposure, a licensee or registrant shall determine:

(a) The internal and external doses from previous planned special exposures; and

(b) 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 subsection (1) of this section, a licensee or registrant may:

(a) Accept, as a record of the occupational dose 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 amount of an occupational dose the individual may have received during the current year.

(b) Accept, as the record of lifetime cumulative radiation dose, an up-to-date NRC Form 4, "Cumulative Occupational Exposure History," or equivalent, signed by the individual and counter-signed by an:

1. Appropriate official of the most recent employer for work involving radiation exposure; or

2. The individual's current employer if the individual is not employed by the licensee or registrant.

(c) Obtain reports of the individual's dose equivalent 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, electronic media, or letter. If the authenticity of the transmitted report cannot be established, a licensee or registrant shall request a written verification of the dose data.

(4) A licensee or registrant shall record the exposure history, as required by subsection (1) of this section, on NRC Form 4, or other clear and legible record, of the information required on that form.

(a) The form or record shall:

1. Show each period the individual received occupational exposure to radiation or radioactive material; and

2. Be signed by the individual who received the exposure;

(b) For each period a licensee or registrant obtains reports, the licensee or registrant shall use the dose shown in the report in preparing NRC Form 4; and

(c) For a period in which a licensee or registrant does not obtain a report, the licensee shall place a notation on NRC Form 4 indicating the periods of time for which data are not available.

(5) If a licensee 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 Section 3(6) of this administrative regulation for the current year, that the allowable dose limit for the individual is reduced by 1.25 rems (twelve and five-tenths (12.5) mSv) for each quarter for which records were unavailable and the individual was engaged in activities that may have resulted in occupational radiation exposure; and

(b) That the individual is not available for planned special exposures.

(6) A licensee or registrant shall:

1. Retain the records on NRC Form 4, or equivalent, until the cabinet terminates the pertinent license or registration requiring this record; and

2. Retain records used in preparing NRC Form 4 for three (3) years after the record is made.

Section 33. Records of Planned Special Exposures. (1) For each use of the provisions of Section 7 of this administrative regulation for planned special exposures, a licensee or registrant shall maintain records that includes:

(a) The name of the management official who authorized the planned special exposure; and

(b) A copy of the signed authorization; and

1. The exceptional circumstances requiring the use of a planned special exposure;

2. What actions were necessary;

3. Why the actions were necessary;

4. How doses were maintained ALARA;

5. What individual and collective doses were expected to result; and

6. The doses actually received in the planned special exposure.

(2) A licensee or registrant shall retain the records until the cabinet terminates the pertinent license or registration requiring these records.

Section 34. Records of Individual Monitoring Results. (1) A licensee or registrant shall maintain records of doses received:

(a) By individuals for whom monitoring was required by Section 13 of this administrative regulation; and

(b) During planned special exposures, accidents, and emergency conditions.

(2) The recordkeeping requirements shall include, if applicable:

(a) Deep-dose equivalent to the whole body;

(b) Eye dose equivalent;

(d) Estimated intake or body burden of radionuclides;

(e) Committed effective dose equivalent assigned to the intake or body burden of radionuclides;

(f) Specific information used to calculate the committed effective dose equivalent under Section 6(3) of this administrative regulation;

(g) Total effective dose equivalent, if required by Section 4 of this administrative regulation; and

(h) Total of the deep-dose equivalent and the committed dose to the organ receiving the highest total dose.

(3) A licensee or registrant shall make entries of the records specified in subsection (1) of this section at least annually.

(4) A licensee or registrant shall maintain the records specified in subsection (1) of this section on NRC Form 5, "Occupational Exposure Record for a Monitoring Period," in accordance with the instructions for NRC Form 5, or in clear and legible records containing the information required by NRC Form 5.

(5) The records required under this section shall be protected from public disclosure because of their personal privacy nature.

(6) A licensee or registrant shall maintain the:

(a) Records of dose to an embryo or fetus with the records of dose to the declared pregnant woman; and

(b) Declaration of pregnancy on file, but may be maintained separately from the dose records.

(7) A licensee or registrant shall retain each required form or record until the cabinet terminates the pertinent license or registration requiring the record.

(8) Assessments of dose equivalent and records made using units in effect before a licensee's or registrant's adoption of this administrative regulation need not to be changed.

Section 35. Records of Dose to Individual Members of the Public. (1) A licensee or registrant shall maintain records sufficient to demonstrate compliance with the dose limit for individual members of the public.

(2) A licensee or registrant shall retain the records required by subsection (1) of this section until the cabinet terminates the pertinent license or registration requiring the record.

Section 36. Records of Testing Entry Control Devices for Very High Radiation Areas. (1) A licensee or registrant shall maintain records of tests made under Section 16(4)(i) of this administrative regulation on entry control devices for very high radiation areas. These records shall include the date, time, and results of each test of function.

(2) A licensee or registrant shall retain the records required by subsection (1) of this section for three (3) years after the record is made.

Section 37. Form of Records. (1) Records required by 902 KAR Chapter 100 shall be legible throughout the specified retention period.

(2) The record shall be:

1. The original;

2. A reproduced copy; or

3. A microform if the copy or microform is authenticated by authorized personnel and the microform is capable of producing a clear copy throughout the required retention period.

(3) The record may be stored in electronic media with the capability for producing legible, accurate, and complete records during the required retention period.

(4) Records such as letters, drawings, and specifications, shall include pertinent information such as stamps, initials, and signatures.

(5) A licensee or registrant shall maintain adequate safeguards against tampering with and loss of records.

Section 38. Reports of Theft or Loss of Licensed or Registered Sources of Radiation. (1) Telephone reports.

(a) A licensee or registrant shall report by telephone as follows:

1. Immediately after its occurrence becomes known to the licensee or registrant, lost, stolen, or missing licensed or registered material in an aggregate quantity equal to or greater than 1,000 times the quantity specified in 902 KAR 100:030, Section 2, under circumstances where it appears to the licensee or registrant that an exposure may result to persons in unrestricted areas; or

2. Within thirty (30) days after the occurrence of lost, stolen, or missing licensed or registered material becomes known to the licensee or registrant, licensed or registered material in a quantity greater than ten (10) times the quantity pursuant to 902 KAR 100:030, Section 2, still missing at this time.

(b) Reports shall be made to the cabinet.

(2) Written reports.

(a) A licensee or registrant required to make a report pursuant to subsection (1) of this section shall, within thirty (30) days after making the telephone report, make a written report setting forth the following information:

1. Description of the licensed or registered material involved, including:

a. Kind;

b. Quantity; and

c. Chemical and physical form;

2. Description of the circumstances under which the loss or theft occurred;

3. Statement of disposition, or probable disposition, of the licensed or registered material involved;

4. Exposures of individuals to radiation, circumstances under which the exposures occurred, and the possible total effective dose equivalent to persons in unrestricted areas;

5. Actions that have been, or shall be, taken to recover the material; and

6. Procedures or measures that have been, or shall be, adopted to ensure against a recurrence of the loss or theft of licensed or registered material.

(b) Reports shall be made to the cabinet.

(3) Subsequent to filing the written report, a licensee or registrant shall report additional substantive information on the loss or theft within thirty (30) days after the licensee or registrant learns of the information.

(4) A licensee or registrant shall prepare and file a report with the cabinet as required by this section so that names of individuals who may have received exposure to radiation shall be stated in a separate and detachable part of the report.

Section 39. Notification of Incidents. (1) Immediate notification. A licensee or registrant shall immediately report an event involving radioactive material possessed by the licensee or registrant that may have caused, or threatens to cause, one (1) or more of the following conditions:

(a) An individual may receive:

1. A total effective dose equivalent of twenty-five (25) rems (0.25 Sv) or more;

2. An eye dose equivalent of seventy-five (75) rems (0.75 Sv) or more; or

3. A shallow-dose equivalent to the skin or extremities of 250 rads (two and five-tenths (2.5) Gy) or more;

(b) The release of radioactive material, inside or outside of a restricted area; so that, had an individual been present for twenty-four (24) hours, the individual may have received an intake five (5) times the occupational annual limit on intake. The provisions of this paragraph shall not apply to locations in which personnel are not normally stationed during routine operations, such as in hot-cells or process enclosure;

(d) Damage to property in excess of $200,000.

(2) Twenty-four (24) hour notification. A licensee or registrant shall, within twenty-four (24) hours of discovery of the event, report an event involving loss of control of licensed or registered source of radiation possessed by the licensee or registrant that may have caused, or shall threaten to cause, one (1) or more of the following conditions:

(a) An individual to receive, in a period of twenty-four (24) hours:

1. A total effective dose equivalent exceeding five (5) rems (0.05 Sv);

2. An eye dose equivalent exceeding fifteen (15) rems (0.15 Sv); or

3. A shallow-dose equivalent to the skin or extremities exceeding fifty (50) rems (five-tenths (0.5) Sv);

(b) The release of radioactive material, inside or outside of a restricted area; so that, had an individual been present for twenty-four (24) hours, the individual may have received an intake in excess of one (1) occupational annual limit on intake. The provisions of this paragraph shall not apply to locations in which personnel are not normally stationed during routine operations, such as in hot-cells or process enclosures;

(d) Damage to property in excess of $2,000.

(3) A licensee or registrant shall prepare and file a report with the cabinet as required by this section so that names of individuals who have received exposure to radiation or radioactive material are stated in a separate and detachable part of the report.

(4) Licensees or registrant shall make reports required by this section to the cabinet by:

(a) Telephone;

(b) Telegram;

(d) Facsimile.

(5) The provisions of this section shall not include doses that result from planned special exposures that are within the limits for planned special exposures, and are reported under Section 41 of this administrative regulation.

Section 40. Reports of Exposures, Radiation Levels, and Concentrations of Radioactive Material Exceeding the Limits. (1) Reportable events. In addition to the notification required by Section 39 of this administrative regulation, a licensee or registrant shall submit a written report within thirty (30) days after learning of one (1) or more of the following occurrences:

(a) An incident for which notification shall be required by Section 39 of this administrative regulation; or

(b) Doses in excess of one (1) of the following:

1. Occupational dose limits for adults in Section 3 of this administrative regulation;

2. Occupational dose limits for a minor in Section 8 of this administrative regulation;

3. Limits for an embryo or fetus of a declared pregnant woman in Section 9 of this administrative regulation;

4. Limits for an individual member of the public in Section 10 of this administrative regulation;

5. Applicable limit in the license or registration;

6. ALARA constraints for air emissions established under Section 2(4); or

1. A restricted area in excess of an applicable limit in the license or registration; or

2. An unrestricted area in excess of ten (10) times an applicable limit set forth in this administrative regulation, the license, or the registration, regardless of exposure of an individual in excess of the limits in Section 10 of this administrative regulation occurs; or

(d) For a person, agency, or licensee subject to the provisions of 40 CFR 190, levels of radiation or releases of radioactive material in excess of those standards, or conditions related to those standards.

(2) Contents of reports.

(a) A report required by subsection (1) of this section shall describe the extent of exposure of individuals to radiation and radioactive material, including, as appropriate:

1. Estimates of each individual's dose;

2. The levels of radiation and concentrations of radioactive material involved;

3. The cause of the elevated exposures, dose rates, or concentrations; and

4. Corrective steps taken or planned to ensure against a recurrence, including the schedule for achieving conformance with applicable limits, ALARA constraints and environmental standards, and associated license or registration conditions.

(b) A report filed under subsection (1) of this section shall include for each individual exposed:

1. Name of the individual;

2. Social Security number; and

3. Date of birth.

(d) With respect to the limit for the embryo or fetus, the identifiers shall be of the declared pregnant woman.

(3) A licensee or registrant who makes a report under subsection (1) of this section shall submit the report, in writing, to the Manager of the Radiation Control Branch, Department for Health Services, 275 East Main Street, Frankfort, Kentucky 40621.

Section 41. Reports of Planned Special Exposures. (1) A licensee or registrant shall submit a written report to the Manager of the Radiation Control Branch, Department for Health Services, 275 East Main Street, Frankfort, Kentucky 40621, within thirty (30) days following a planned special exposure conducted in accordance with Section 7 of this administrative regulation.

(2) A licensee or registrant shall:

(a) Inform the Manager of the Radiation Control Branch that a planned special exposure was conducted;

(b) Indicate the date the planned special exposure occurred; and

Section 42. Reports of Individual Monitoring. (1) This section shall apply to persons licensed or registered by the cabinet to:

(a) Possess or use sources of radiation for purposes of radiography authorized by 902 KAR 100:100;

(b) Receive radioactive waste from other persons for disposal pursuant to 902 KAR 100:022; or

(c) Possess or use, for processing or manufacturing for distribution required by 902 KAR 100:058, byproduct material in amounts exceeding one (1) of the following quantities:

	Quantity of Radionuclide^ain curies
Cesium-137	1
Cobalt-60	1
Gold-198	100
Iodine-131	1
Iridium-192	10
Krypton-85	1,000
Promethium-147	10
Technetium-99m	1,000

^aThe cabinet may require as a license or registration condition, KRS 211.842-211.852 or 902 KAR 100:015, Section 8, reports from licensees or registrants who are licensed or registered to use radionuclides not on this list, in quantities sufficient to cause comparable radiation levels.

(2) A licensee or registrant in a category listed in subsection (1) of this section shall:

(a) Submit an annual report of the results of individual monitoring carried out by the licensee for each individual for whom monitoring was required by Section 13 of this administrative regulation during that year;

(b) The licensee or registrant shall use Form NRC 5, or other clear and legible record, which contains all the information required by Form NRC 5.

(3) A licensee or registrant may include additional data for individuals for whom monitoring may be provided, but not required.

(4) A licensee or registrant shall:

(a) File the report required by subsection (2) of this section covering the preceding year on or before April 30 of each year; and

(b) Submit the report to the Manager of the Radiation Control Branch, Department for Health Services, 275 East Main Street, Frankfort, Kentucky 40621.

Section 43. Protection Factors for Respirators. Protection Factors^a:

FOOTNOTES

a. For use in the selection of respiratory protective equipment to be used only if the contaminants have been identified and the concentrations, or possible concentrations, are known.

b. Only for shaven faces and if nothing interferes with the seal of tight-fitting facepieces against the skin. Hoods and suits shall be excepted.

c. The mode symbols shall be defined as follows:

CF = continuous flow

D = demand

NP = negative pressure, that is, negative phase during inhalation

PD = pressure demand, that is, always positive pressure

PP = positive pressure

RD = demand, recirculating or closed circuit

RP = pressure demand, recirculating or closed circuit

d.1. The protection factor shall be a measure of the degree of protection afforded by a respirator, defined as the ratio of the concentration of airborne radioactive material outside the respiratory protective equipment to that inside the equipment, usually inside the facepiece, under conditions of use. It shall be applied to the ambient airborne concentration to estimate the concentrations inhaled by the wearer according to the following formula:

Concentration inhaled =

Ambient airborne concentration

Protection factor

2. The protection factors apply:

(a) Only for individuals trained in using respirators and wearing properly fitted respirators that shall be used and maintained under supervision in a well-planned respiratory protective program.

(b) For air-purifying respirators only if high efficiency particulate filters, above 99.97% removal efficiency by thermally generated three-tenths (0.3) micron (mm) dioctyl phthalate (DOP) test or equivalent, shall be used in atmospheres not deficient in oxygen and not containing radioactive gas or vapor respiratory hazards.

(d) For atmosphere-supplying respirators only if supplied with adequate respirable air. Respirable air shall be provided of the quality and quantity required in accordance with the National Institute for Occupational Safety and Health and the Mine Safety and Health Administration certification described in 30 CFR Part 11. Oxygen and air shall not be used in the same apparatus.

e. Excluding radioactive contaminants that present an absorption or submersion hazard. For tritium oxide, approximately one-third (1/3) of the intake occurs by absorption through the skin so that an overall protection factor of less than two (2) shall be appropriate if atmosphere-supplying respirators are used to protect against tritium oxide. If the protection factor for respiratory protective equipment is five (5), the effective protection factor for tritium is about one and four-tenths (1.4); with protection factors of ten (10), the effective factor for tritium oxide is about one and seven-tenths (1.7); and with protection factors of 100 or more, the effective factor for tritium oxide is about one and nine-tenths (1.9). Air-purifying respirators shall not be suitable for protection against tritium oxide. See also footnote i concerning supplied-air suits.

f. Canisters and cartridges shall not be used beyond service-life limitations.

g. Under-chin type only. This type of respirator shall not be satisfactory for use if it may be possible, that if an accident or emergency were to occur, for the ambient airborne concentrations to reach instantaneous values greater than ten (10) times the pertinent values in Table I, Column 3 of Section 44(9) of this administrative regulation. This type of respirator shall not be suitable for protection against plutonium or other high-toxicity materials. The mask shall be tested for fit prior to use, each time it is donned.

h.1. Equipment shall be operated in a manner that ensures that proper airflow-rates are maintained. A protection factor of no more than 1000 may be utilized for tested-and-certified supplied-air hoods if a minimum air flow of six (6) cubic feet per minute (0.17 m³/min) is maintained and calibrated air line pressure gauges or flow measuring devices are used. A protection factor of up to 2000 may be used for tested and certified hoods only if the air flow is maintained at the manufacturer's recommended maximum rate for the equipment, this rate is greater than six (6) cubic feet per minute (0.17 m³/min) and calibrated air line pressure gauges or flow measuring devices are used.

2. The design of the supplied-air hood or helmet, with a minimum flow of six (6) cubic feet per minute (0.17 m³/min) of air, may determine its overall efficiency and the protection it provides. For example, some hoods aspirate contaminated air into the breathing zone if the wearer works with hands-over-head. This aspiration may be overcome if a short cape-like extension to the hood is worn under a coat or overalls. Other limitations specified by the approval agency shall be considered before using a hood in certain types of atmospheres. See footnote c.

i. Appropriate protection factors shall be determined, taking into account the design of the suit and its permeability to the contaminant under conditions of use. There shall be a standby rescue person equipped with a respirator or other apparatus appropriate for the potential hazards and communications equipment if supplied-air suits are used.

j. No approval schedules are currently available for this equipment. Equipment shall be evaluated by testing or on the basis of reliable test information.

k. This type of respirator may provide greater protection and be used as an emergency device in unknown concentrations for protection against inhalation hazards. External radiation hazards and other limitations to permitted exposure, for example, as skin absorption, shall be taken into account in these circumstances.

l. Quantitative fit testing shall be performed on each individual, and no more than 0.02% leakage shall be allowed with this type of apparatus. Perceptible outward leakage of gas from this or a positive pressure self-contained breathing apparatus shall be unacceptable because service life shall be reduced substantially. Special training in the use of this type of apparatus shall be provided to the wearer.

Note 1: Protection factors for respirators approved by the U.S. Bureau of Mines and the National Institute for Occupational Safety and Health, according to applicable approvals for respirators for type and mode of use to protect against airborne radionuclides, may be used to the extent that they do not exceed the protection factors listed in this table. The protection factors listed in this table may not be appropriate to circumstances if chemicals or other respiratory hazards exist in addition to radioactive hazards. The selection and use of respirators for these circumstances shall take into account applicable approvals of the U.S. Bureau of Mines and the National Institute for Occupational Safety and Health.

Note 2: Radioactive contaminants, for which the concentration values in Table I, Column 3 of Section 44(9) are based on internal dose due to inhalation, may present external exposure hazards at higher concentrations. Under these circumstances, limitations on occupancy may have to be governed by external dose limits.

Section 44. Annual Limits on Intake (ALI) and Derived Air Concentrations (DAC) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sanitary Sewerage. (1) For each radionuclide, subsection (9), Table I, of this section indicates the chemical form which shall be used for selecting the appropriate ALI or DAC value.

(2) The ALIs and DACs for inhalation are given for:

(a) An aerosol with an activity median aerodynamic diameter (AMAD) of one (1) μm; and

(b) Three (3) classes (D,W,Y) of radioactive material, which refer to their retention (approximately days, weeks, or years) in the pulmonary region of the lung. This classification applies to a range of clearance half-times for:

1. D if less than ten (10) days;

2. W from ten (10) to 100 days; and

3. Y greater than 100 days.

(3) Subsection (9) of this section provides concentration limits for airborne and liquid effluents released to the general environment.

(4) Subsection (9) of this section provides concentration limits for discharges to sanitary sewerage.

(5) The values in Tables I, II, and III of subsection (9) of this section are presented in the computer "E" notation. In this notation:

(a) A value of 6E-02 represents a value of 6 x 10^-2 or 0.06;

(b) 6E+2 represents 6 x 10² or 600; and

(6) Occupational Values - Table I.

(a) The columns in Table I of subsection (9) of this section captioned "Oral Ingestion ALI," "Inhalation ALI," and "DAC," shall be applicable to occupational exposure to radioactive material.

(b) The ALIs in subsection (9) of this section are the annual intakes of a given radionuclide by "Reference Man" which result in a committed effective dose equivalent of:

1. Five (5) rem (0.05 Sv), stochastic ALI; or

2. Fifty (50) rem (five-tenths (0.5) Sv) to an organ or tissue, nonstochastic ALI.

(c) The stochastic ALIs were derived to result in a risk, due to irradiation of organs and tissues, comparable to the risk associated with deep dose equivalent to the whole body of five (5) rem (0.05 Sv).

1. The derivation includes multiplying the committed dose equivalent to an organ or tissue by a weighting factor, w_T;

2. This weighting factor is the proportion of the risk of stochastic effects resulting from irradiation of the organ or tissue (T) to the total risk of stochastic effects if the whole body is irradiated uniformly; and

3. The values of w_T are listed under the definition of weighting factor in 902 KAR 100:010.

(d) The nonstochastic ALIs were derived to avoid nonstochastic effects, such as prompt damage to tissue or reduction in organ function.

(e) A value of w_T = 0.06 shall be applicable to each of the five (5) organs or tissues in the "remainder" category receiving the highest dose equivalents, and the dose equivalents of other remaining tissues may be disregarded. The following portions of the GI tract shall be treated as four (4) separate organs:

1. Stomach;

2. Small intestine;

3. Upper large intestine; and

4. Lower large intestine.

(f) The dose equivalents for an extremity, skin, and lens of the eye shall not be considered in computing the committed effective dose equivalent, and shall be subject to limits that are met separately.

(g) If an ALI shall be defined by the stochastic dose limit, this value alone is given. If an ALI shall be determined by the nonstochastic dose limit to an organ, the organ or tissue to which the limit applies is shown, and the ALI for the stochastic limit is shown in parentheses. Abbreviated organ or tissue designations are used as follows:

1. LLI wall = lower large intestine wall;

2. St. wall = stomach wall;

3. Blad wall = bladder wall; and

4. Bone surf = bone surface.

(h) The use of the ALIs listed first, the more limiting of the stochastic and nonstochastic ALIs, shall ensure nonstochastic effects are avoided and the risk of stochastic effects is limited to an acceptably low value.

1. If, in a particular situation involving a radionuclide for which the nonstochastic ALI is limiting, use of that nonstochastic ALI may be considered unduly conservative, a licensee may use the stochastic ALI to determine the committed effective dose equivalent;

2. A licensee shall also ensure that the fifty (50) rem (five-tenths (0.5) Sv) dose equivalent limit for an organ or tissue shall not be exceeded by the sum of the external deep dose equivalent plus the internal committed dose equivalent to that organ, not the effective dose;

3. If there is no external dose contribution, the requirements of subparagraph 2 of this paragraph shall be demonstrated if the sum of the fractions of the nonstochastic ALIs (ALI_ns) that contribute to the committed dose equivalent to the organ receiving the highest dose shall not exceed unity, that is, å(intake in mCi of each radionuclide/ALI_ns) £1.0; and

4. If there is an external deep dose equivalent contribution of H_d, then this sum shall be less than 1 - (H_d/50), instead of £1.0.

(i) The dose equivalents for an extremity, skin, and lens of the eye shall not be considered in computing the committed effective dose equivalent, but shall be subject to limits that shall be met separately.

(j) The derived air concentration (DAC) values are derived limits intended to control chronic occupational exposures. The relationship between the DAC and the ALI shall be given by:

1. DAC = ALI(in μCi)/(2000 hours per working year x 60 minutes/hour x 2 x 10⁴ ml per minute) = {ALI/2.4 x 10⁹} μCi/ml, if 2 x 10⁴ ml is the volume of air breathed per minute at work by the reference man under working conditions of light work;

2. The DAC values relate to one (1) of two (2) modes of exposure with external submersion or the internal committed dose equivalents resulting from inhalation of radioactive materials. DACs based upon submersion shall be for immersion in a semi-infinite cloud of uniform concentration and shall apply to each radionuclide separately;

3. The ALI and DAC values include contributions to exposure by the single radionuclide named and in-growth of daughter radionuclides produced in the body by decay of the parent. Intakes that include both the parent and daughter radionuclides shall be treated by the general method appropriate for mixtures;

4. The values of ALI and DAC shall not apply directly if the individual both ingests and inhales a radionuclide, if the individual is exposed to a mixture of radionuclides by inhalation, ingestion, or both, or if the individual is exposed to both internal and external irradiation (see Section 13 of this administrative regulation). If an individual is exposed to radioactive materials which fall under several of the translocation classifications of the same radionuclide (for example, Class D, Class W, or Class Y), the exposure may be evaluated as if it were a mixture of different radionuclides; and

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

(7) Effluent Concentrations - Table II.

(a) The columns in Table II of subsection (9) of this section captioned "Effluents," "Air," and "Water" shall be applicable to the assessment and control of dose to the public, particularly in the implementation of the provisions of 902 KAR 100:021, Section 3. The concentration values given in Columns 1 and 2 of Table II, subsection (9) of this section, are equivalent to the radionuclide concentrations which, if inhaled or ingested continuously over the course of a year, shall produce a total effective dose equivalent of 0.05 rem (five-tenths (0.5) mSv).

(b) Consideration of nonstochastic limits has not been included in deriving the air and water effluent concentration limits because nonstochastic effects are presumed not to occur at or below the dose levels established for individual members of the public. For radionuclides, where the nonstochastic limit will be governing in deriving the occupational DAC, the stochastic ALI shall be used in deriving the corresponding airborne effluent limit in Table II, subsection (9) of this section. For this reason, the DAC and airborne effluent limits are not always proportional.

(c) The air concentration values listed in Table II, subsection (9) of this section, Column 1, were derived by one (1) of two (2) methods. For those radionuclides for which the stochastic limit is governing, the occupational stochastic inhalation ALI was divided by 2.4 x 10⁹, relating the inhalation ALI to the DAC, as explained in subsection (6)(j)1, of this section and then divided by a factor of 300. The factor of 300 includes the following components:

1. A factor of fifty (50) to relate the 0.05 rem (0.05 Sv) annual occupational dose limit to the one-tenth (0.1) rem limit for members of the public;

2. A factor of three (3) to adjust for the difference in exposure time and the inhalation rate for a worker and for members of the public; and

3. A factor of two (2) to adjust the occupational values, derived for adults, so they are applicable to other age groups.

(d) For those radionuclides for which submersion, that is external dose, shall be limiting, the occupational DAC in Table I, Column 3, of subsection (9) of this section shall be divided by 219. The factor of 219 is composed of:

1. A factor of fifty (50), as described in subsection (7)(c) of this section;

2. A factor of 4.38 relating occupational exposure for 2,000 hours per year to full-time exposure (8,760 hours per year); and

3. An additional factor of two (2) for age considerations shall not be warranted in the submersion case.

(e) The water concentrations shall be derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 x 10⁷. The factor of 7.3 x 10⁷ (ml) includes the following components:

1. The factors of fifty (50) and two (2) described above; and

2. A factor of 7.3 x 10⁵ (ml) which is the annual water intake of the reference man.

(f) This section provides groupings of radionuclides which shall be applicable to unknown mixtures of radionuclides. These groupings, including occupational inhalation ALIs and DACs, air and water effluent concentrations, and releases to sewer, require demonstrating the most limiting radionuclides in successive classes are absent. The limit for the unknown mixture shall be defined if the presence of one (1) of the listed radionuclides cannot be definitely excluded as being present from knowledge of the radionuclide composition of the source or from actual measurements.

(8) Releases to Sewers - Table III.

(a) The monthly average concentrations for release to sanitary sewerage shall be applicable to Section 11 of this administrative regulation.

(b) The concentration values were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7.3 x 10⁶ (ml). The factor of 7.3 x 10⁶ (ml) shall be composed of a factor of 7.3 x 10⁵ (ml), the annual water intake by the reference man, and a factor of ten (10), that the concentrations, if the sewage released by the licensee was the only source of water ingested by a reference man during a year, shall result in a committed effective dose equivalent of five-tenths (0.5) rem.

(9) List of Elements and Tables I, II, and III.

Name	Symbol	Atomic Number	Name	Symbol	Atomic Number
Actinium	Ac	89	Mercury	Hg	80
Aluminum	Al	13	Molybdenum	Mo	42
Americium	Am	95	Neodymium	Nd	60
Antimony	Sb	51	Neptunium	Np	93
Argon	Ar	18	Nickel	Ni	28
Arsenic	As	33	Niobium	Nb	41
Astatine	At	85	Osmium	Os	76
Barium	Ba	56	Palladium	Pd	46
Berkelium	Bk	97	Phosphorus	P	15
Beryllium	Be	4	Platinum	Pt	78
Bismuth	Bi	83	Plutonium	Pu	94
Bromine	Br	35	Polonium	Po	84
Cadmium	Cd	48	Potassium	K	19
Calcium	Ca	20	Praseodymium	Pr	59
Californium	Cf	98	Promethium	Pm	61
Carbon	C	6	Protactinium	Pa	91
Cerium	Ce	58	Radium	Ra	88
Cesium	Cs	55	Radon	Rn	86
Chlorine	Cl	17	Rhenium	Re	75
Chromium	Cr	24	Rhodium	Rh	45
Cobalt	Co	27	Rubidium	Rb	37
Copper	Cu	29	Ruthenium	Ru	44
Curium	Cm	96	Samarium	Sm	62
Dysprosium	Dy	66	Scandium	Sc	21
Einsteinium	Es	99	Selenium	Se	34
Erbium	Er	68	Silicon	Si	14
Europium	Eu	63	Silver	Ag	47
Fermium	Fm	100	Sodium	Na	11
Fluorine	F	9	Strontium	Sr	38
Francium	Fr	87	Sulfur	S	16
Gadolinium	Gd	64	Tantalum	Ta	73
Gallium	Ga	31	Technetium	Tc	43
Germanium	Ge	32	Tellurium	Te	52
Gold	Au	79	Terbium	Tb	65
Hafnium	Hf	72	Thallium	Tl	81
Holmium	Ho	67	Thorium	Th	90
Hydrogen	H	1	Thulium	Tm	69
Indium	In	49	Tin	Sn	50
Iodine	I	53	Titanium	Ti	22
Iridium	Ir	77	Tungsten	W	74
Iron	Fe	26	Uranium	U	92
Krypton	Kr	36	Vanadium	V	23
Lanthanum	La	57	Xenon	Xe	54
Lead	Pb	82	Ytterbium	Yb	70
Lutetium	Lu	71	Yttrium	Y	39
Magnesium	Mg	12	Zinc	Zn	30
Manganese	Mn	25	Zirconium	Zr	40
Mendelevium	Md	101

Atomic No.	Radionuclide	Class	Table I Occupational Values			Table II Effluent Concentrations		Table III Releases to Sewers
			Col. 1 Oral injestion ALI (μCi)	Col. 2	Col. 3	Col.1 Air (μCi/ml)	Col. 2 Water (μCi/ml)	Monthly Average Concentration (μCi/ml)
				Col. 2	Col. 3
				Inhalation
				ALI (μCi)	DAC (μCi/ml)


1	Hydrogen-3	Water, DAC includes skin absorption	8E+4	8E+4	2E-5	1E-7	1E-3	1E-2
1	Hydrogen-3	Gas (HT or T₂) Submersion¹:	Use above values as HT and T₂ oxidize in air and in the body to HTO.
4	Beryllium-7	W, all compounds except those given for Y	4E+4	2E+4	9E-6	3E-8	6E-4	6E-3
4	Beryllium-7	Y, oxides, halides, and nitrates	-	2E+4	8E-6	3E-8	-	-
4	Beryllium-10	W, see ⁷Be	1E+3	2E+2	6E-8	2E-10	-	-
		LLI wall	(1E+3)	-	-	-	2E-5	2E-4
		Y, see ⁷Be	-	1E+1	6E-9	2E-11	-	-
6	Carbon-11²	Monoxide	-	1E+6	5E-4	2E-6	-	-
		Dioxide	-	6E+5	3E-4	9E-7	-	-
		Compounds	4E+5	4E+5	2E-4	6E-7	6E-3	6E-2
6	Carbon-14	Monoxide	-	2E+6	7E-4	2E-6	-	-
		Dioxide	-	2E+5	9E-5	3E-7	-	-
		Compounds	2E+3	2E+3	1E-6	3E-9	3E-5	3E-4
9	Fluorine-18²	D, fluorides of H, Li, Na, K, Rb, Cs, and Fr	5E+4	7E+4	3E-5	1E-7	-	-
			St wall
			(5E+4)	-	-	-	7E-4	7E-3
		W, fluorides of Be, Mg, Ca, Sr, Ba, Ra, Al, Ga, In, Tl, As, Sb, Bi, Fe, Ru, Os, Co, Ni, Pd, Pt, Cu, Ag, Au, Zn, Cd, Hg, Sc, Y, Ti, Zr, V, Nb, Ta, Mn, Tc, and Re	-	9E+4	4E-5	1E-7	-	-
		Y, lanthanum fluoride	-	8E+4	3E-5	1E-7	-	-
11	Sodium-22	D, all compounds	4E+2	6E+2	3E-7	9E-10	6E-6	6E-5
11	Sodium-24	D, all compounds	4E+3	5E+3	2E-6	7E-9	5E-5	5E-4
12	Magnesium-28	D, all compounds except those given for W	7E+2	2E+3	7E-7	2E-9	9E-6	9E-5
12	Magnesium-28	W, oxides, hydroxides, carbides, halides, and Nitrates	-	1E+3	5E-7	2E-9	-	-
13	Aluminum-26	D, all compounds except those given for W	4E+2	6E+1	3E-8	9E-11	6E-6	6E-5
13	Aluminum-26	W, oxides, hydroxides, Carbides, halides, and Nitrates	-	9E+1	4E-8	1E-10	-	-
14	Silicon-31	D, all compounds except those given for W and Y	9E+3	3E+4	1E-5	4E-8	1E-4	1E-3
		W, oxides, hydroxides, carbides, and nitrates	-	3E+4	1E-5	5E-8	-	-
		Y, aluminosilicate glass	-	3E+4	1E-5	4E-8	-	-
14	Silicon-32	D, see ³¹Si	2E+3	2E+2	1E-7	3E-10	-	-
			LLI wall
			(3E+3)	-	-	-	4E-5	4E-4
		W, see ³¹Si	-	1E+2	5E-8	2E-10	-	-
		Y, see ³¹Si	-	5E+0	2E-9	7E-12	-	-
15	Phosphorus-32	D, all compounds except phosphates given for W	6E+2	9E+2	4E-7	1E-9	9E-6	9E-5
15	Phosphorus-32	W, phosphates of Zn²⁺, S³⁺, Mg²⁺, Fe³⁺, Bi³⁺, and lanthanides	-	4E+2	2E-7	5E-10	-	-
15	Phosphorus-33	D, see ³²P	6E+3	8E+3	4E-6	1E-8	8E-5	8E-4
15	Phosphorus-33	W, see ³²P	-	3E+3	1E-6	4E-9	-	-
16	Sulfur-35	Vapor	1E+4	6E-6	2E-8	-	-
		D, sulfides and sulfates except those given for W	1E+4	2E+4	7E-6	2E-8	-	-
			LLI wall
			(8E+3)	-	-	-	1E-4	1E-3
		W, elemental sulfur, sulfides of Sr, Ba, Ge, Sn, Pb, As, Sb, Bi, Cu, Ag, Au, Zn, Cd, Hg, W, and Mo. Sulfates of Ca, Sr, Ba, Ra, As, Sb, and Bi	6E+3
			-	2E+3	9E-7	3E-9	-	-
17	Chlorine-36	D, chlorides of H, Li, Na, K, Rb, Cs, and Fr	2E+3	2E+3	1E-6	3E-9

Description^b	Protection Factors^d		Particulates, gases & vapors^e	Tested & Certified Equipment
Description^b	Modes^c	Particulates only	Particulates, gases & vapors^e	National Institute for Occupational Safety and Health & Mine Safety and Health Administration tests for permissibility
I. AIR-PURIFYING RESPIRATORS:
Facepiece, half-mask^g	N	10		30 CFR Part 11, Subpart K.
Facepiece, full	NP	50
Facepiece, half-mask	PP	1000
full, or hood
II. ATMOSPHERE-SUPPLYING RESPIRATORS:
1. Air-line respirator:
Facepiece, half-mask	CF		1000	30 CFR Part 11, Subpart J.
Facepiece, half-mask	D		5
Facepiece, full	CF		2000
Facepiece, full	D		5
Facepiece, full	PD		2000
Hood	CF		(^h)
Suit	CF		(ⁱ)	(^j)
2. Self-contained breathing apparatus (SCBA)
Facepiece, full	D		50	30 CFR 11, Subpart H.
Facepiece, full	PD		^k10,000
Facepiece, full	RD		50
Facepiece, full	RP		^l5,000
III. COMBINATION RESPIRATORS:
A combination of air-purifying and Atmosphere-supplying respirators	Protection factor for type and mode of operation as listed above.			30 CFR 11, Sec. 11.63(b)

See footnotes.