Indiana Administrative Code › Title 410 - INDIANA DEPARTMENT OF HEALTH › Article 5 - RADIOLOGICAL HEALTH › Rule 1 - General Provisions › Section 1-2 - Definitions

Current through July 10, 2024
Authority: IC 16-41-35-26; IC 16-41-35-29
Affected: IC 16-41-35
Sec. 2.
As used in 410 IAC 5, these terms have the definitions set
				  forth below. Additional definitions used only in a certain part will be found
				  in that part.
"Accelerator-produced material" means any material made
				  radioactive by exposing it in a particle accelerator.
"Act" means the Radiation Control Act of Indiana, IC 13-1-2
[IC 13-1 was repealed by P.L. 1-1996, SECTION 99, effective July 1,
				  1996.]
, Indiana General Assembly.
"Agreement state" means any state with which the United
				  States Nuclear Regulatory Commission has entered into an effective agreement
				  under Section 274 b. of the Atomic Energy Act of 1954, as amended (73 Stat.
				  689).
"Airborne radioactive material" means any radioactive
				  material dispersed in the air in the form of dusts, fumes, mists, vapors, or
				  gases.
"Airborne radioactivity area" means (1) any room, enclosure,
				  or operating area in which airborne radioactive material exists in
				  concentrations in excess of the amounts specified in Table I, Column 1 of
				  410
				  IAC 5-4-27; or (2) any room, enclosure, or operating
				  area in which airborne radioactive material exists in concentrations which,
				  averaged over the number of hours in any week during which individuals are in
				  the area, exceed 25 percent of the amounts specified in Table I, Column 1 of
				  410
				  IAC 5-4-27.
"Board" means executive board of the Indiana department of
				  health or its duly authorized representatives.
"Byproduct material" means any radioactive material (except
				  special nuclear material) yielded in or made radioactive by exposure to the
				  radiation incident to the process of producing or utilizing special nuclear
				  material.
"Calendar quarter" means not less than 12 consecutive weeks
				  nor more than 14 consecutive weeks. The first calendar quarter of each year
				  shall begin in January and subsequent calendar quarters shall be so arranged
				  such that no day is included in more than one calendar quarter and no day in
				  any one year is omitted from inclusion within a calendar quarter. No licensee
				  or registrant shall change the method observed by him of determining calendar
				  quarters for purposes of 410 IAC 5 except at the beginning of a calendar
				  year.
"Calibration" means the determination of (1) the response or
				  reading of an instrument relative to a series of known radiation values over
				  the range of the instrument, or (2) the strength of a source of radiation
				  relative to a standard.
"CFR" means Code of Federal Regulations (1982
				  Edition).
"Controlled area" see "Restricted area."
"Curie" means a unit of quantity of radioactivity. One curie
				  (Ci) is that quantity of radioactive material which decays at the rate of 3.7
				  × 1010 transformations per second (tps).
				  Commonly used submultiples of the curie are the millicurie and the microcurie.
				  One millicurie (mCi) = 0.001 curie = 3.7 × 107
				  tps. One microcurie (µCi) = 0.000001 curie =
				  3.7 × 104 tps. (See
				  410 IAC
				  5-1-10.5 for SI equivalent becquerel.)
"Depleted uranium" means the source material uranium in which
				  the isotope uranium-235 is less than 0.711 weight percent of the total uranium
				  present. Depleted uranium does not include special nuclear material.
"Dose" as used in 410 IAC 5 shall mean absorbed dose or dose
				  equivalent as appropriate.
"Absorbed dose" is the energy imparted to matter by ionizing
				  radiation per unit mass of irradiated material at the place of interest. The
				  special unit of absorbed dose is the rad. (See rad.) (See
				  410 IAC
				  5-1-10.5 for SI equivalent gray.)
"Dose equivalent" is a quantity that expresses on a common
				  scale for all radiation a measure of the postulated effect on a given organ. It
				  is defined as the absorbed dose in rads times certain modifying factors. The
				  unit of dose equivalent is the rem. (See rem.) (See
				  410 IAC
				  5-1-10.5 for SI equivalent sievert.)
"Dose commitment" means the total radiation dose to a part of
				  the body that will result from retention in the body of radioactive material.
				  For purposes of estimating the dose commitment, it is assumed that from the
				  time of intake, the period of exposure to retained material will not exceed 50
				  years.
* "
Exposure
" means the quotient of
				  dQ by dm where "dQ" is the absolute value of the total charge of the ions of
				  one sign produced in air when all the electrons (negatrons and positrons)
				  liberated by photons in a volume element of air having mass "dm" are completely
				  stopped in air. (The special unit of
exposure
is the
				  roentgen (R).) (See
				  410 IAC
				  5-1-10.5 for SI equivalent coulomb per
				  kilogram).
* (When not indicated as above or indicated as "exposure
				  (X)," the term "
exposure
" has a more general meaning
				  in 410 IAC 5.)
"Exposure rate" means the
exposure
per unit of time, such as R/min, mR/h etc.
"Former U.S. Atomic Energy Commission (AEC) or U.S. Nuclear
				  Regulatory Commission (NRC) licensed facilities" means nuclear reactors,
				  nuclear fuel reprocessing plants, uranium enrichment plants or critical mass
				  experimental facilities where AEC or NRC licenses have been terminated.
"Healing arts" includes any system, treatment, operation,
				  diagnosis, prescription or practice for the ascertainment, cure, relief,
				  palliation, adjustment or correction of any human or animal disease, ailment,
				  deformity, injury or unhealthy or abnormal physical or mental condition.
"High radiation area" means any area, accessible to
				  individuals, in which there exists radiation at such levels that a major
				  portion of the body could receive in any one hour a dose in excess of 100
				  millirems.
"Human use" means the internal or external administration of
				  radiation or radioactive material to human beings.
"Individual" means any human being.
"Inspection" means an official examination or observation
				  including but not limited to tests, surveys, and monitoring to determine
				  compliance with rules, regulations, orders, requirements and conditions of the
				  board.
"Interlock" means a device arranged or connected such that
				  the occurrence of an event or condition is required before a second event or
				  condition can occur or continue to occur.
"License" means a license issued by the board in accordance
				  with 410 IAC 5 and IC 13-1-2
[IC 13-1 was repealed by P.L. 1-1996,
				  SECTION 99, effective July 1, 1996.]
.
"Licensee" means any person who is licensed by the board in
				  accordance with 410 IAC 5 and IC 13-1-2
[IC 13-1 was repealed by P.L.
				  1-1996, SECTION 99, effective July 1, 1996.]
.
"Licensing state" means any state with regulations equivalent
				  to the suggested state regulations for control of radiation relating to, and an
				  effective program for, the regulatory control of NARM.
"Major processor" means a user processing, handling, or
				  manufacturing radioactive material exceeding Type A quantities as unsealed
				  sources or material, or exceeding 4 times Type B quantities as sealed sources,
				  but does not include nuclear medicine programs, universities, industrial
				  radiographers, or small industrial programs. Type A and B quantities are
				  defined in Section 71.4 of 10 CFR Part 71.
"NARM" means any naturally-occurring or accelerator-produced
				  radioactive material. It does not include byproduct, source or special nuclear
				  material.
"Natural radioactivity" means radioactivity of
				  naturally-occurring nuclides.
"Occupational dose" means exposure of an individual to
				  radiation (1) in a restricted area or (2) in the course of employment in which
				  the individual's duties involve exposure to radiation provided that
				  occupational dose shall not be deemed to include any exposure of an individual
				  to radiation for the purpose of diagnosis or therapy of such individual.
"Particle accelerator" means any machine capable of
				  accelerating electrons, protons, deuterons, or other charged particles in a
				  vacuum and of discharging the resultant particulate or other radiation into a
				  medium at energies usually in excess of 1 MeV.
"Person" means any individual, corporation, partnership,
				  firm, association, trust, estate, public or private institution, group, agency,
				  political subdivision of this state, any other state or political subdivision
				  or agency thereof, and any legal successor, representative, agent or agency of
				  the foregoing.
"Personnel monitoring equipment" means devices (e.g. film
				  badges, pocket dosimeters, and thermoluminescent dosimeters) designed to be
				  worn or carried by an individual for the purpose of estimating the dose
				  received by the individual.
"Pharmacist" means an individual licensed by the state of
				  Indiana to compound and dispense drugs, prescriptions, and poisons.
"Physician" means an individual licensed by the state of
				  Indiana to dispense drugs in the practice of medicine.
"Rad" means the special unit of absorbed dose. One rad equals
				  one hundredth of a joule per kilogram of material; for example, if tissue is
				  the material of interest, then 1 rad equals 100 ergs per gram of tissue.
"Radiation" means ionizing radiation; i.e., gamma rays and
				  x-rays, alpha and beta particles, high speed electrons, neutrons, high speed
				  protons, and other nuclear particles.
"Radiation area" means any area, accessible to individuals,
				  in which there exists radiation at such levels that a major portion of the body
				  could receive in any one hour a dose in excess of 5 millirems, or in any 5
				  consecutive days a dose in excess of 100 millirems.
"Radiation machine" means any device capable of producing
				  radiation except those which produce radiation only from radioactive
				  material.
"Radiation safety officer" means one who has the knowledge
				  and responsibility to apply appropriate radiation protection
				  regulations.
"Radioactive material" means any material (solid, liquid or
				  gas) which emits radiation spontaneously.
"Radioactivity" means the transformation of unstable atomic
				  nuclei by the emission of radiation.
"Registrant" means any person who is registered with the
				  board and is legally obligated to register with the board as required by 410
				  IAC 5 and IC 13-1-2
[IC 13-1 was repealed by P.L. 1-1996, SECTION 99,
				  effective July 1, 1996.]
.
"Registration" means registration with the board in
				  accordance with 410 IAC 5.
"Regulations of the U.S. Department of Transportation" means
				  the regulations in 49 CFR Parts 100-189.
"Rem" means a special unit of dose equivalent. (One millirem
				  (mrem) = 0.001 rem.) For the purpose of 410 IAC 5, any of the following is
				  considered to be equal to one rem:
(1) An
exposure
of 1 roentgen of x
				  or gamma radiation;
(2) An absorbed dose of 1 rad due to x, gamma or beta
				  radiation;
(3) An absorbed dose of 0.05 rad due to particles heavier
				  than protons and with sufficient energy to reach the lens of the eye;
(4) An absorbed dose of 0.1 rad due to neutrons or high
				  energy protons.1/ (See
				  410 IAC
				  5-1-10.5 for SI equivalent sievert.) 
				  1/ If it is more convenient to measure
				  the neutron flux or equivalent than to determine the neutron absorbed dose in
				  rads, one rem of neutron radiation may, for purposes of 410 IAC 5, be assumed
				  to be equivalent to 14 million neutrons per square centimeter incident upon the
				  body; or if there exists sufficient information to estimate with reasonable
				  accuracy the approximate distribution in energy of the neutrons, the incident
				  number of neutrons per square centimeter equivalent to one rem may be estimated
				  from the following table:
Neutron Flux Dose Equivalents
Neutron energy (MeV)
Number of neutrons per square centimeter for a dose
							 equivalent to 1 rem (neutrons/cm2)
Average flux density to deliver 100 millirems in 40
							 hours (neutrons/cm2 per second)
Thermal
.........970 × 106
................. 670
0.0001
.........720 × 106
................. 500
0.005
.........820 × 106
................. 570
0.02
.........400 ×
							 106
................. 280
0.1
.........120 ×
							 106
.................. 80
0.5
..........43 × 106
.................. 30
1.0
..........26 × 106
.................. 18
2.5
..........29 × 106
.................. 20
5.0
..........26 × 106
.................. 18
7.5
..........24 × 106
.................. 17
10.0
..........24 × 106
.................. 17
10 to 30
..........14 × 106
.................. 10
"Research and development" means:
(1) theoretical analysis, exploration, or experimentation or
(2) the extension of investigative findings and theories of a
				  scientific or technical nature into practical application for experimental and
				  demonstration purposes, including the experimental production and testing of
				  models, devices, equipment, materials, and processes. Research and development
				  does not include the internal or external administration of radiation or
				  radioactive material to human beings.
"Restricted area" (controlled area) means any area access to
				  which is controlled by the licensee or registrant for purposes of protection of
				  individuals from exposure to radiation and radioactive material. "Restricted
				  area" shall not include any areas used for residential quarters although a
				  separate room or rooms in a residential building may be set apart as a
				  restricted area.
"Roentgen" (R) means the special unit of
exposure
. One roentgen equals 2.58 ×
				  10-4 coulombs/kilogram of air (see
				  "
Exposure
").
"Saled source" means radioactive material that is permanently
				  bonded or fixed in a capsule or matrix designed to prevent release and
				  dispersal of the radioactive material under the most severe conditions which
				  are likely to be encountered in normal use and handling.
"Source material" means:
(1) uranium or thorium, or any combination thereof, in any
				  physical or chemical form or
(2) ores which contain by weight one-twentieth of one percent
				  (0.05 percent) or more of (i) uranium, (ii) thorium or (iii) any combination
				  thereof Source material does not include special nuclear material.
" Source material milling" means any activity that results in
				  the production of byproduct material as defined by definition (2) of source
				  material.
" Source of radiation" means any radioactive material or any
				  device or equipment emitting or capable of producing radiation.
"Special form" means any of the following physical forms of
				  licensed material of any transport group:
(1) The material is in solid form having no dimension less
				  than 0.5 millimeter or at least one dimension greater than five (5)
				  millimeters; does not melt, sublime or ignite in air at a temperature of
				  1000° F (538° C); will not shatter or crumble if subjected to the
				  percussion test described in Appendix B,
				  410 IAC
				  5-1-12; and is not dissolved or converted into
				  dispersible form to the extent of more than 0.005 percent by weight by
				  immersion for 1 week in water at 68° F (20° C) or in air at 86° F
				  (30°C); or
(2) The material is securely contained in a capsule having no
				  dimension less than 0.5 millimeter or at least one dimension greater than five
				  (5) millimeters, which will retain its contents if subjected to the tests
				  prescribed in Appendix B,
				  410 IAC
				  5-1-12; and which is constructed of materials which do
				  not melt, sublime or ignite in air at 1475° F (802° C), and do not
				  dissolve or convert into dispersible form to the extent of more than 0.005
				  percent by weight by immersion for 1 week in water at 68°F (20°C) or in
				  air at 86°F (30°C).
"Special nuclear material in quantities not sufficient to
				  form a critical mass" means uranium enriched in the isotope U-235 in quantities
				  not exceeding 350 grams of contained U-235, U-233 in quantities not exceeding
				  200 grams; plutonium in quantities not exceeding 200 grams; or any combination
				  of them in accordance with the following formula: For each kind of special
				  nuclear material, determine the ratio between the quantity of that special
				  nuclear material and the quantity specified above for the same kind of special
				  nuclear material. The sum of such ratios for all of the kinds of special
				  nuclear material in combination shall not exceed "1" (i.e., unity). For
				  example, the following quantities in combination would not exceed the
				  limitation and are within the formula:
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"Survey" means an evaluation of the production, use, release,
				  disposal, and/or presence of sources of radiation under a specific set of
				  conditions to determine actual or potential radiation hazards. When
				  appropriate, such evaluation includes but is not limited to tests, physical
				  examination and measurements of levels of radiation or concentration of
				  radioactive material present.
"Test" means the process of verifying compliance with the
				  applicable sections of 410 IAC 5.
"Transport group" means any one of seven groups into which
				  radionuclides in normal form are classified according to their toxicity and
				  their relative potential hazard in transport (see Appendix A,
				  410 IAC
				  5-1-11 ).
(1) Any radionuclide not specifically listed in one of the
				  groups in Appendix A,
				  410 IAC
				  5-1-11 shall be assigned to one of the groups in
				  accordance with the following table:
Radioactive half-life
Radionuclide
0 to 1000 days
1000 days to 106 years
Over 106 years
Atomic number 1-81
Atomic number 82 and over
Group III
Group I
Group II
Group I
Group III
Group III
(2) For mixtures of radionuclides the following shall apply:
(i) If the identity and respective activity of each
				  radionuclide are known, the permissible activity of each radionuclide shall be
				  such that the sum for all groups present of the ratio between the total
				  activity for each group to the permissible activity for each group will not be
				  greater than unity.
(ii) If the groups of the radionuclides are known but the
				  amount in each group cannot be reasonably determined, the mixture shall be
				  assigned to the most restrictive group present.
(iii) If the identity of all or some of the radionuclides
				  cannot be reasonably determined, each of those unidentified radionuclides shall
				  be considered as belonging to the most restrictive group which cannot be
				  positively excluded.
(iv) Mixtures consisting of a single radioactive decay chain
				  where the radionuclides are in the naturally-occurring proportions shall be
				  considered as consisting of a single radionuclide. The group and activity shall
				  be that of the first member present in the chain, except that if a radionuclide
				  "X" has a half-life longer than that of the first member and an activity
				  greater than that of any other member, including the first, at any time during
				  transportation, the transport group of the nuclide "X" and the activity of the
				  mixture shall be the maximum activity of that nuclide "X" during
				  transportation. "U.S. Department of Energy" means the Department of Energy
				  established by Public Law 95-91, August 4, 1977, 91 Stat. 565,
				  42
				  U.S.C. 7101 et seq., to the extent that the
				  department exercises functions formerly vested in the U.S. Atomic Energy
				  Commission, its chairman, members, officers, and components and transferred to
				  the U.S. Energy Research and Development Administration and to the
				  administrator thereof pursuant to sections 104(b), (c), and (d) of the Energy
				  Reorganization Act of 1974 ( Public Law 93-438, October 11, 1974, 88 Stat. 1233
				  at 1237, effective January 19, 1975) and retransferred to the Secretary of
				  Energy pursuant to section 301(a) of the Department of Energy Organization Act
				  ( Public Law 95-91, August 4, 1977, 91 Stat. 565 at 577-578,
				  42 U.S.C. 7151,
				  effective October 1, 1977). "Uncontrolled area" see "Unrestricted area."
"Unrefined and unprocessed ore" means ore in its natural form
				  prior to any processing, such as grinding, roasting, beneficiating, or
				  refining.
"Unrestricted area" (uncontrolled area) means any area access
				  to which is not controlled by the licensee or registrant for purposes of
				  protection of individuals from exposure to radiation and radioactive material
				  and any area used for residential quarters.
"Waste handling licensees" means persons licensed to receive
				  and store radioactive wastes prior to disposal and/or persons licensed to
				  dispose of radioactive waste.
"Worker" means any individual engaged in work under a license
				  or registration issued by the board and controlled by a licensee or registrant
				  but does not include the licensee or registrant.