Arizona Administrative Code › Title 9 - HEALTH SERVICES › Chapter 7 - DEPARTMENT OF HEALTH SERVICES - RADIATION CONTROL › Article 1 - GENERAL PROVISIONS › Section R9-7-102 - Definitions

Current through Register Vol. 30, No. 28, July 12, 2024
Terms defined in A.R.S. §
									30-651
				  have the same meanings when used in this Chapter, unless the context otherwise
				  requires. Additional subject-specific definitions are used in other
				  Articles.
"A1" means the maximum activity of special form radioactive
				  material permitted in a type A package. These values are either listed in 10
				  CFR 71, Appendix A, Table A-1, or may be derived in accordance with the
				  procedures prescribed in 10 CFR 71, Appendix A.
"A2" means the maximum activity of radioactive material,
				  other than special form radioactive material, low specific activity (LSA)
				  material, and surface contaminated object (SCO) material, permitted in a Type A
				  package. These values are either listed in 10 CFR 71, Appendix A, Table A-1, or
				  may be derived in accordance with the procedure prescribed in 10 CFR 71,
				  Appendix A.
"Absorbed dose" means the energy imparted by ionizing
				  radiation per unit mass of irradiated material. The units of absorbed dose are
				  the gray (Gy) and the rad.
"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. For purposes of this definition, "particle
				  accelerator" is an equivalent term.
"Accelerator produced material" means any material made
				  radioactive by irradiating it in a particle accelerator.
"Act" means A.R.S. Title 30, Chapter 4.
"Activity" means the rate of disintegration, transformation,
				  or decay of radioactive material. The units of activity are the becquerel (Bq)
				  and the curie (Ci).
"Adult" means an individual 18 or more years of age.
"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). "Nonagreement State" means any other state.
"Airborne radioactive material" means any radioactive
				  material dispersed in the air in the form of aerosols, dusts, fumes, mists,
				  vapors, or gases.
"Airborne radioactivity area" means a room, enclosure, or
				  area in which airborne radioactive materials, composed wholly or partly of
				  licensed radioactive material, exist in concentrations:
In excess of the derived air concentrations (DACs) specified
				  in Appendix B, Table I of Article 4 of these rules; or
That an individual present in the area without respiratory
				  protective equipment could exceed, during the hours an individual is pre-sent
				  in a week, an intake of 0.6 percent of the annual limit on intake (ALI) or 12
				  DAC-hours.
"ALARA" means as low as is reasonably achievable, making
				  every reasonable effort to maintain exposures to radiation as far below the
				  dose limits in these rules as is practical, consistent with the purpose for
				  which the licensed or registered activity is undertaken, taking into account
				  the state of technology, the economics of improvements in relation to state of
				  technology, the economics of improvements in relation to benefits to the public
				  health and safety, and other societal and socioeconomic considerations, and in
				  relation to utilization of nuclear energy and licensed or registered sources of
				  radiation in the public interest.
"Analytical x-ray equipment" means equipment used for x-ray
				  diffraction or x-ray-induced fluorescence analysis.
"Analytical x-ray system" means a group of components
				  utilizing x-rays to determine the elemental composition or to examine the
				  micro-structure of materials.
"Annual" means done or performed yearly. For purposes of
				  Chapter 1, any required activity done or performed within plus or minus two
				  weeks of the annual due date is considered done or performed in a timely
				  manner.
"Approved individual" means an individual whom the licensee
				  has determined to be trustworthy and reliable for unescorted access in
				  accordance with subpart B of this part and who has completed the training
				  required by
				  10 CFR
				  37.43(c).
"Associate Radiation Safety Officer" means an individual
				  who:
Meets the requirements in
				  10
				  CFR 35.50 and
				  10 CFR
				  35.59; and
Is currently identified as an Associate Radiation Safety
				  Officer for the types of use of byproduct material for which the individual has
				  been assigned duties and tasks by the Radiation Safety Officer on:
A specific medical use license issued by the NRC or an
				  Agreement State; or
A medical use permit issued by a NRC master material
				  licensee.
"Authorized medical physicist" means an individual who meets
				  the requirements in
				  R9-7-711;
				  or is identified as an authorized medical physicist or teletherapy physicist
				  on:
A specific medical use license issued by the Department, the
				  NRC, or another Agreement State;
A medical use permit issued by a NRC master material
				  licensee;
A permit issued by the Department, the NRC, or another
				  Agreement State broad scope medical use licensee; or
A permit issued by a NRC master material license broad scope
				  medical use permittee.
"Authorized nuclear pharmacist" means a pharmacist who meets
				  the requirements in
				  R9-7-712;
				  or is:
Identified as an authorized nuclear pharmacist on a specific
				  license issued by the Department, the NRC, or another Agreement State that
				  authorizes medical use or the practice of nuclear pharmacy;
Identified as an authorized nuclear pharmacist on a permit
				  issued by a NRC master material licensee that authorizes medical use or the
				  practice of nuclear pharmacy;
Identified as an authorized nuclear pharmacist on a permit
				  issued by the Department, the NRC, or another Agreement State broad scope
				  medical use licensee that authorizes medical use or the practice of nuclear
				  pharmacy; or
Identified as an authorized nuclear pharmacist on a permit
				  issued by a NRC master material license broad scope medical use permittee that
				  authorizes medical use or the practice of nuclear pharmacy; or
Identified as an authorized nuclear pharmacist by a
				  commercial nuclear pharmacy that has been authorized to identify authorized
				  nuclear pharmacists; or
Designated as an authorized nuclear pharmacist in accordance
				  with
				  R9-7-311(G).
"Authorized user" means a physician, dentist, or podiatrist
				  who meets the requirements in
				  R9-7-719,
				  R9-7-723,
				  R9-7-727,
				  R9-7-728,
				  or
				  R9-7-744;
				  or is identified as an authorized user on:
The Department, NRC, or another Agreement State license that
				  authorizes the medical use of radioactive material;
A permit issued by a NRC master material licensee that is
				  authorized to permit the medical use of radioactive material;
A permit issued by the Department, the NRC, or another
				  Agreement State specific licensee of broad scope that is authorized to permit
				  the medical use of radioactive material; or
A permit issued by a NRC master material license broad scope
				  permittee that is authorized to permit the medical use of radioactive
				  material.
"Background investigation" means an assessment of an
				  individual's prior actions and experience conducted by a licensee or applicant,
				  to support the determination of the individual's trustworthiness and
				  reliability in accordance with
				  10 CFR
				  37.25.
"Background radiation" means radiation from cosmic sources;
				  not technologically enhanced naturally occurring radioactive material,
				  including radon (except as a decay product of source or special nuclear
				  material); and global fallout as it exists in the environment from the testing
				  of nuclear explosive devices or from past nuclear accidents, such as Chernobyl,
				  that contribute to background radiation and are not under the control of a
				  licensee. "Background radiation" does not include sources of radiation
				  regulated by the Department.
"Becquerel" (Bq) means the International System (SI) unit for
				  activity and is equal to 1 disintegration per second (dps or tps).
"Bioassay" means the determination of kinds, quantities, or
				  concentrations, and in some cases, the locations of radioactive material in the
				  human body, whether by direct measurement, in vivo counting, or by analysis and
				  evaluation of materials excreted or removed from the human body. For purposes
				  of these rules, "radiobioassay" is an equivalent term.
"Brachytherapy" means a method of radiation therapy in which
				  an encapsulated source or group of sources is utilized to deliver beta or gamma
				  radiation at a distance of up to a few centimeters, by surface, intracavitary
				  or interstitial application.
"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;
The tailings or wastes produced by the extraction or
				  concentration of uranium or thorium from ore processed primarily for its source
				  material content, including discrete surface wastes resulting from uranium or
				  thorium solution extraction processes. Underground ore bodies depleted by these
				  solution extraction operations do not constitute "byproduct material" within
				  this definition;
Any discrete source of radium-226 that is produced,
				  extracted, or converted after extraction, for use for a commercial, medical, or
				  research activity; or any material that, has been made radioactive by use of a
				  particle accelerator; and is produced, extracted, or converted after
				  extraction, for use for a commercial, medical, or research activity; and
Any discrete source of naturally occurring radioactive
				  material, other than source material, that the NRC, in consultation with the
				  Administrator of the Environmental Protection Agency, the Secretary of Energy,
				  the Secretary of Homeland Security, and the head of any other appropriate
				  federal agency, determines would pose a threat similar to the threat posed by a
				  discrete source of radium-226 to the public health and safety or the common
				  defense and security and; before, on, or after August 8, 2005, is extracted or
				  converted after extraction for use in a commercial, medical, or research
				  activity.
"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. A licensee or
				  registrant shall not change the method of determining calendar quarters for
				  purposes of this Chapter except at the beginning of a calendar year.
				  "Calibration" means the determination of:
The response or reading of an instrument relative to a series
				  of known radiation values over the range of the instrument, or
The strength of a source of radiation relative to a
				  standard.
"Carrier" means a person engaged in the transportation of
				  passengers or property by land or water as a common, contract, or private
				  carrier, or by civil aircraft.
"Certifiable cabinet x-ray system" means an existing
				  uncertified x-ray system that meets or has been modified to meet the
				  certification requirements specified in
				  21 CFR
				  1020.40, revised April 1, 2019, incorporated
				  by reference, and available under
				  R9-7-101.
				  This incorporated material contains no future editions or amendments.
"Certificate holder" means a person who has been issued a
				  certificate of compliance or other package approval by the Department or
				  NRC.
"Certificate of Compliance" (CoC) means the certificate
				  issued by the NRC under 10 CFR 71, Subpart D, which authorizes the design of a
				  package for the transportation of radioactive material.
"Certified cabinet x-ray system" means an x-ray system that
				  has been certified in accordance with
				  21
				  CFR 1010.2, as being manufactured and
				  assembled on or after April 10, 1975, in accordance with the provisions of
				  21 CFR
				  1020.40, both sections revised April 1, 2019,
				  incorporated by reference, and available under
				  R9-7-101.
				  This incorporated material contains no future editions or amendments.
"CFR" means Code of Federal Regulations.
"Chelating agent" means amine polycarboxylic acids,
				  hydroxycarboxylic acids, gluconic acid, and polycarboxylic acids.
"Civil penalty" means the monetary fine which may be imposed
				  on licensees by the Department, pursuant to A.R.S. §
									30-687,
				  for violations of the Act, this Chapter, or license conditions.
"Collective dose" means the sum of the individual doses
				  received in a given period of time by a specified population from exposure to a
				  specified source of radiation.
"Committed dose equivalent" (HT,50) means the dose equivalent
				  to organs or tissues of reference (T) that will be received from an intake of
				  radioactive material by an individual during the 50-year period following the
				  intake.
"Committed effective dose equivalent" (HE,50) is the sum of
				  the products of the weighting factors applicable to each of the body organs or
				  tissues that are irradiated and the committed dose equivalent to each of these
				  organs or tissues (HE,50 = S wT,HT,50).
"Consortium" means an association of medical use licensees
				  and a PET radionuclide production facility in the same geographical area that
				  jointly own or share in the operation and maintenance cost of the PET
				  radionuclide production facility that produces PET radionuclides for use in
				  producing radioactive drugs within the consortium for noncommercial
				  distributions among its associated members for medical use. The PET
				  radionuclide production facility within the consortium must be located at an
				  educational institution or a federal facility or a medical facility.
"Contamination" means the presence of a radioactive substance
				  on a surface in quantities in excess of 0.4 Bq/cm2 (1 × 10-5 µCi/cm2) for beta
				  and gamma emitters and low toxicity alpha emitters, or 0.04 Bq/cm2 (1 × 10-6
				  µCi/cm2) for all other alpha emitters.
"Fixed contamination" means contamination that cannot be
				  removed from a surface during normal conditions of transport.
"Non-fixed contamination" means contamination that can be
				  removed from a surface during normal conditions of transport.
"Criticality Safety Index (CSI)" means the dimensionless
				  number (rounded up to the next tenth) assigned to and placed on the label of a
				  fissile material package, to designate the degree of control of accumulation of
				  packages, overpacks or freight containers containing fissile material during
				  transportation. Determination of the criticality safety index is described in
				  10 CFR
				  71.22,
				  10 CFR
				  71.23, and
				  10 CFR
				  71.59. The criticality safety index for an
				  overpack, freight container, consignment or conveyance containing fissile
				  material packages is the arithmetic sum of the criticality safety indices of
				  all the fissile material packages contained within the overpack, freight
				  container, consignment or conveyance.
"Curie" means a unit of quantity of radioactivity. One curie
				  (Ci) is that quantity of radioactive material which decays at the rate of 3.7E
				  + 1010 transformations per second (tps).
"Current license or registration" means a license or
				  registration issued by the Department and for which the licensee has paid the
				  license or registration fee for the current year according to
				  R9-7-1304.
"Deep-dose equivalent" (Hd), which applies to external whole
				  body exposure, is the dose equivalent at a tissue depth of 1 centimeter (1000
				  mg/cm2).
"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.
"Discrete source" means a radionuclide that has been
				  processed so that its concentration within a material has been purposely
				  increased for use for commercial, medical, or research activities.
"Dose" is a generic term that means absorbed dose, dose
				  equivalent, effective dose equivalent, committed dose equivalent, committed
				  effective dose equivalent, total organ dose equivalent, or total effective dose
				  equivalent. For purposes of these rules, "radiation dose" is an equivalent
				  term.
"Dose equivalent" (HT) means the product of the absorbed dose
				  in tissue, quality factor, and all other necessary modifying factors at the
				  location of interest. The units of dose equivalent are the sievert (Sv) and
				  rem.
"Dose limits" means the permissible upper bound of radiation
				  doses established in accordance with these rules. For purposes of these rules,
				  "limits" is an equivalent term.
"Dosimeter" (See "Individual monitoring device")
"Effective dose equivalent" (HE) means the sum of the
				  products of the dose equivalent to each organ or tissue (HT) and the weighting
				  factor (wT) applicable to each of the body organs or tissues that are
				  irradiated (HE = S wTHT).
"Effluent release" means any disposal or release of
				  radioactive material into the ambient atmosphere, soil, or any surface or
				  subsurface body of water.
"Embryo/fetus" means the developing human organism from
				  conception until the time of birth.
"Enclosed beam x-ray system" means an analytical x-ray system
				  constructed in such a way that access to the interior of the enclosure housing
				  the x-ray source during operation is precluded except through bypassing of
				  interlocks or other safety devices to perform maintenance or servicing.
"Enclosed radiography" means industrial radiography conducted
				  by using cabinet radiography or shielded room radiography.
"Cabinet radiography" means industrial radiography conducted
				  by using an x-ray machine in an enclosure not designed for human admittance and
				  which is so shielded that every location on the exterior meets the conditions
				  for an "unrestricted area."
"Shielded room radiography" means industrial radiography
				  conducted using an x-ray machine in an enclosure designed for human admittance
				  and which is so shielded that every location of the exterior meets the
				  conditions for an "unrestricted area."
"Entrance or access point" means any opening through which an
				  individual or extremity of an individual could gain access to radiation areas
				  or to licensed radioactive materials. This includes entry or exit portals of
				  sufficient size to permit human entry, irrespective of their intended
				  use.
"Exhibit" for purposes of these rules, is equivalent in
				  meaning to the word "Schedule" as found in previously issued rules, current
				  license conditions, and regulation guide.
"Explosive material" means any chemical compound, mixture, or
				  device which produces a substantial instantaneous release of gas and heat
				  spontaneously or by contact with sparks or flame.
"Exposure" means:
Being subjected to ionizing radiation or radioactive
				  materials.
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).
"Exposure rate" means the exposure per unit of time.
"External dose" means that portion of the dose equivalent
				  received from any source of radiation outside the body.
"Extremity" means the hand, elbow, arm below the elbow, foot,
				  knee, and leg below the knee.
"Fail-safe characteristics" means a design feature which
				  causes beam port shutters to close, or otherwise prevents emergence of the
				  primary beam, upon the failure of a safety or warning device.
"FDA" means the United States Food and Drug
				  Administration.
"Field radiography" means industrial radiography, utilizing a
				  portable or mobile x-ray system, which is not conducted in a shielded
				  en-closure.
"Field station" means a facility where radioactive sources
				  may be stored or used and from which equipment is dispatched to temporary job
				  sites.
"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.
"Generally applicable environmental radiation standards"
				  means standards issued by the U.S. Environmental Protection Agency (EPA), 40
				  CFR 190, revised December 1, 1979, and 40 CFR 191, revised December 20, 1993,
				  incorporated by reference, and available under
				  R9-7-101,
				  under the authority of the Atomic Energy Act of 1954, as amended, that impose
				  limits on radiation exposures or levels, or concentrations or quantities of
				  radioactive material, in the general environment outside the boundaries of
				  locations under the control of persons possessing or using radioactive
				  material. This incorporated material contains no future editions or
				  amendments.
"Gray" (Gy) means the International System (SI) unit of
				  absorbed dose and is equal to 1 joule per kilogram. One gray equals 100
				  rad.
"Hazardous waste" means those wastes designated as hazardous
				  in A.R.S. §
									49-921(5).
"Healing arts" means the practice of medicine, dentistry,
				  osteopathy, podiatry, chiropractic, and veterinary medicine.
"Health care institution" means every place, institution, or
				  building which provides facilities for medical services or other health-related
				  services, not including private clinics or offices which do not provide
				  overnight patient care.
"High radiation area" means an area, accessible to
				  individuals, in which radiation levels from radiation sources external to the
				  body could result in an individual receiving a dose equivalent in excess of 1
				  mSv (0.1 rem) in one hour at 30 centimeters from the radiation source or 30
				  centimeters from any surface that the radiation penetrates.
"Human use" means the internal or external administration of
				  radiation or radioactive materials to human beings.
"Impound" means to abate a radiological hazard. Actions which
				  may be taken by the Department in impounding a source of radiation include
				  seizing the source of radiation, controlling access to an area, and preventing
				  a radiation machine from being utilized.
"Indian Tribe" means an Indian or Alaska native Tribe, band,
				  nation, pueblo, village, or community that the Secretary of the Interior
				  acknowledges to exist as an Indian Tribe pursuant to the Federally Recognized
				  Indian Tribe List Act of 1994,
				  25
				  U.S.C. 479a.
"Individual" means any human being.
"Individual monitoring" means the assessment of:
Dose equivalent
By the use of individual monitoring devices, or
By the use of survey data, or
Committed effective dose equivalent
By bioassay; or
By determination of the time-weighted air concentrations to
				  which an individual has been exposed, that is, DAC-hours. (See the definition
				  of DAC-hours in Article 4).
"Individual monitoring device" means a device designed to be
				  worn by a single individual for the assessment of dose equivalent. For purposes
				  of this Chapter, "dosimeter" and "personnel dosimeter," are equivalent terms.
				  Examples of individual monitoring devices are film badges, thermoluminescence
				  dosimeters (TLDs), pocket ionization chambers, optical stimulation devices, and
				  personnel ("lapel") air sampling devices.
"Individual monitoring equipment" means one or more
				  individual monitoring devices. For purposes of this Chapter, "personnel
				  monitoring equipment" is an equivalent term.
"Industrial radiography" means the examination of the
				  macroscopic structure of materials by non-destructive methods utilizing sources
				  of ionizing radiation.
"Injection tool" means a device used for controlled
				  subsurface injection of radioactive tracer material.
"Inspection" means an examination or observation by a
				  representative of the Department, including but not limited to tests, surveys,
				  and monitoring to determine compliance with rules, orders, requirements and
				  conditions of the License or certificate of registration.
"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.
"Internal dose" means that portion of the dose equivalent
				  received from radioactive material taken into the body.
"Irradiate" means to expose to radiation.
"Laser" (light amplification by the stimulated emission of
				  radiation) means any device which can produce or amplify electromagnetic
				  radiation with wavelengths in the range of 180 nanometers to 1 millimeter
				  primarily by the process of controlled stimulated emission.
"Lens dose equivalent" (LDE) means the external exposure of
				  the lens of the eye and is taken as the dose equivalent at a tissue depth of
				  0.3 centimeters (300 mg/cm2).
"License" means the grant of authority, issued pursuant to
				  Articles 3 and 14 of this Chapter and A.R.S. §§
									30-671,
				  30-672,
				  and
				  30-721
				  et seq., to acquire, possess, transfer, and use sources of radiation. The types
				  of licenses issued by the Department are described in
				  R9-7-1302.
"Licensed material" means radioactive material received,
				  possessed, used, transferred, or disposed of under a general or specific
				  license issued by the Department.
"Licensed practitioner" means a person licensed or otherwise
				  authorized by law to practice medicine, dentistry, osteopathy, chiropractic,
				  podiatry, or naturopathy in this state.
"Licensee" means any person who is licensed by the Department
				  under this Chapter to acquire, possess, transfer, or use sources of
				  radiation.
"Licensing State" means any state having regulations
				  equivalent to this Chapter relating to, and an effective program for the
				  regulation of, naturally occurring and accelerator-produced radioactive
				  material (NARM).
"Limits" (See "Dose limits")
"Local components" means those parts of an analytical x-ray
				  system that are struck by x-rays, including radiation source housings, port and
				  shutter assemblies, collimator, sample holders, cameras, goniometer, detectors
				  and shielding but not including power supplies, trans-formers, amplifiers,
				  readout devices, and control panels.
"Logging supervisor" means the individual who provides
				  personal supervision of the utilization of sources of radiation at the well
				  site.
"Logging tool" means a device used subsurface to perform well
				  logging.
"Lost or missing licensed or registered source of radiation"
				  means licensed or registered source of radiation the location of which is
				  un-known. Included are licensed radioactive material or a registered radiation
				  source that has been shipped but has not reached its planned destination and
				  whose location cannot be readily traced or ascertained in the transportation
				  system.
"Low-level waste" means waste material which contains
				  radioactive nuclides in concentrations or quantities which exceed applicable
				  standards for unrestricted release but does not include:
High-level waste, such as irradiated reactor fuel, liquid
				  waste from reprocessing irradiated reactor fuel, or solids into which any such
				  liquid waste has been converted;
Waste material containing transuranic elements with
				  contamination levels greater than 10 nanocuries per gram (370 kilobecquerels
				  per kilogram) of waste material; or
The tailings or wastes produced by the extraction or
				  concentration of uranium or thorium from any ore processed primarily for its
				  source material content.
"Low Specific Activity (LSA) material" means radioactive
				  material with limited specific activity which is nonfissile or is excepted
				  under
				  10 CFR
				  71.15, and which satisfies the descriptions
				  and limits set forth in the following section. Shielding materials surrounding
				  the LSA material may not be considered in determining the estimated average
				  specific activity of the package contents. The LSA material must be in one of
				  three groups:
LSA-I.
Uranium and thorium ores, concentrates of uranium and thorium
				  ores, and other ores containing naturally occurring radionuclides that are
				  intended to be processed for the use of these radionuclides;
Natural uranium, depleted uranium, natural thorium or their
				  compounds or mixtures, provided they are unirradiated and in solid or liquid
				  form;
Radioactive material other than fissile material, for which
				  the A2 value is unlimited; or
Other radioactive material in which the activity is
				  distributed throughout and the estimated average specific activity does not
				  exceed 30 times the value for exempt material activity concentration determined
				  in accordance with appendix A.
LSA-II.
Water with tritium concentration up to 0.8 TBq/liter (20.0
				  Ci/liter); or
Other radioactive material in which the activity is
				  distributed throughout and the estimated average specific activity does not
				  exceed 10-4 A2/g for solids and gases, and 10-5 A2/g for liquids.
LSA-III. Solids (e.g., consolidated wastes, activated
				  materials), excluding powders, that satisfy the requirements of
				  10 CFR
				  71.77, in which:
The radioactive material is distributed throughout a solid or
				  a collection of solid objects, or is essentially uniformly distributed in a
				  solid compact binding agent (such as concrete, bitumen, ceramic, etc.);
The radioactive material is relatively insoluble, or it is
				  intrinsically contained in a relatively insoluble material, so that even under
				  loss of packaging, the loss of radioactive material per package by leaching,
				  when placed in water for 7 days will not exceed 0.1 A2; and
The estimated average specific activity of the solid,
				  excluding any shielding material, does not exceed 2 x 10- 3A2/g.
"Major processor" means a user processing, handling, or
				  manufacturing radioactive material exceeding Type A quantities as unsealed
				  sources or material or exceeding four 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
				  10
				  CFR 71.4.
"Medical dose" means a radiation dose intentionally delivered
				  to an individual for medical examination, diagnosis, or treatment.
"Member of the public" means any individual except when that
				  individual is receiving an occupational dose.
"MeV" means Mega Electron Volt which equals 1 million volts
				  (106 eV).
"Mineral logging" means any well logging performed in a
				  borehole drilled for the purpose of exploration for minerals other than oil or
				  gas.
"Minor" means an individual less than 18 years of age.
"Monitoring" means the measurement of radiation, radioactive
				  material concentrations, surface area activities, or quantities of radioactive
				  material, and the use of the results of these measurements to evaluate
				  potential exposures and doses. For purposes of these rules, "radiation
				  monitoring" and "radiation protection monitoring" are equivalent terms.
"Multiplier" means a letter representing a number. The use of
				  a multiplier is based on the code given below:
Prefix
Multiplier Symbol
Value
eka
E
1018
peta
P
1015
tera
T
1012
giga
G
109
mega
M
106
kilo
k
103
milli
m
10-3
micro
u
10-6
nano
n
10-9
pico
p
10-12
femto
f
10-15
atto
a
10-18
"NARM" means any naturally occurring or accelerator-produced
				  radioactive material. It does not include byproduct, source, or special nuclear
				  material. This term should not be confused with "NORM" which is defined as
				  naturally occurring radioactive material.
"Natural radioactivity" means the radioactivity of naturally
				  occurring radioactive substances.
"Normal operating procedures" means the entire set of
				  instructions necessary to accomplish the intended use of the source of
				  radiation. These procedures shall include, but are not limited to, sample
				  insertion and manipulation, equipment alignment, routine maintenance by the
				  licensee, and data recording procedures which are related to radiation
				  safety.
"NRC" means Nuclear Regulatory Commission, the U.S. Nuclear
				  Regulatory Commission, or its duly authorized representatives.
"NRC Document Control Desk" means the Nuclear Regulatory
				  Document Control Desk. ATTN: Document Control Desk, U.S. Nuclear Regulatory
				  Commission, Washington, DC 20555-0001.
"Nuclear waste" means any highway route controlled quantity
				  (defined in
				  49
				  CFR 173.403, revised January 8, 2015,
				  incorporated by reference, available under
				  R9-7-101,
				  and containing no future editions or amendments) of source, byproduct, or
				  special nuclear material required to be in NRC-approved packaging while
				  transported to, through, or across state boundaries to a disposal site, or to a
				  collection point for transport to a disposal site. Additional requirements
				  associated with transportation of radioactive material can be found in Article
				  15.
"Occupational dose" means the dose received by an individual
				  in the course of employment in which the individual's assigned duties involve
				  exposure to sources of radiation, whether in the possession of a licensee,
				  registrant, or other person. Occupational dose does not include a dose received
				  from background radiation, medical administration of radiation to the
				  individual, exposure to an individual who has been administered radioactive
				  material and released in accordance with
				  R9-7-717,
				  voluntary participation in a medical research pro-gram, or as a member of the
				  public.
"Open beam system" means an analytical x-ray system in which
				  an individual could place some body part in the primary beam path during normal
				  operation.
"Ophthalmic physicist" means an individual who:
Meets the requirements in
				  10 CFR
				  35.433(a)(2) and
				  10 CFR
				  35.59; and
Is identified as an ophthalmic physicist on a:
Specific medical use license issued by the Department, the
				  NRC, or another Agreement State;
Permit issued by a Department, NRC, or another Agreement
				  State broad scope medical use licensee;
Medical use permit issued by a NRC master material licensee;
				  or
Permit issued by a NRC master material license broad scope
				  medical use permittee.
"Package" means the packaging together with its radioactive
				  contents as presented for transport.
"Particle accelerator" (See "Accelerator")
"Permanent radiographic installation" means a fixed, shielded
				  installation or structure designed or intended for industrial radiography and
				  in which industrial radiography is regularly performed.
"Personnel dosimeter" (See "Individual monitoring
				  device")
"Personnel monitoring equipment" (See "Individual monitoring
				  device")
"Personal supervision" means supervision in which the
				  supervising individual is physically present at the site where sources of
				  radiation and associated equipment are being used, watching the performance of
				  the supervised individual and in such proximity that immediate assistance can
				  be given if required.
"PET" (See Positron Emission Tomography (PET))
"Pharmacist" means an individual licensed by this state to
				  compound and dispense drugs, prescriptions, and poisons.
"Physician" means an individual licensed pursuant to A.R.S.
				  Title 32, Chapters 13 or 17.
"Positron Emission Tomography (PET)" means an imaging
				  technique using radionuclides to produce high resolution images of the body's
				  biological functions.
"Positron Emission Tomography radionuclide production
				  facility" means a facility operating a cyclotron or accelerator for the purpose
				  of producing PET radionuclides.
"Preceptor" means an individual who provides, directs, or
				  verifies training and experience required for an individual to become an
				  authorized user, an authorized medical physicist, an authorized nuclear
				  pharmacist, a Radiation Safety Officer, or an Associate Radiation Safety
				  Officer.
"Primary beam" means radiation which passes through an
				  aperture of the source housing by a direct path from the x-ray tube or a
				  radio-active source located in the radiation source housing.
"Promptly" means with little or no delay.
"Public dose" means the dose received by a member of the
				  public from radiation from radioactive material released by a licensee or
				  registrant, or exposure to a source of radiation used in a licensed or
				  registered operation. It does not include an occupational dose or a dose
				  received from background radiation, medical administration of radiation to the
				  individual, exposure to an individual who has been administered radioactive
				  material and released in accordance with
				  R9-7-717,
				  or voluntary participation in a medical research program.
"Pyrophoric liquid" means any liquid that ignites
				  spontaneously in dry or moist air at or below 130° F (54.4° C).
"Pyrophoric solid" means any solid material, other than one
				  classed as an explosive, which under normal conditions is liable to cause fires
				  through friction, retained heat from manufacturing or processing, or which can
				  be ignited readily and, when ignited, burns so vigorously and persistently that
				  it creates a serious transportation, handling, or disposal hazard. Included are
				  spontaneously combustible and water-reactive materials.
"Qualified expert" means an individual certified in the
				  appropriate field by the American Board of Radiology or the American Board of
				  Health Physics, or having equivalent qualifications that provide the knowledge
				  and training to measure ionizing radiation, to evaluate safety techniques, and
				  to advise regarding radiation protection needs; or an individual certified in
				  Therapeutic Radiological Physics or X-ray and Radium Physics by the American
				  Board of Radiology, or having equivalent qualifications that provide training
				  and experience in the clinical applications of radiation physics to radiation
				  therapy, to calibrate radiation therapy equipment. The detailed requirements
				  for a particular qualified expert may be provided in the respective Articles of
				  this Chapter. For clarification purposes, a qualified expert is not always an
				  authorized medical physicist; however, an authorized medical physicist is
				  included within the definition of "qualified expert."
"Quality Factor" (Q) means the modifying factor, listed in
				  Tables I and II of this Article, that is used to derive dose equivalent from
				  absorbed dose.
"Quarter" (See "Calendar quarter")
"Rad" means the special unit of absorbed dose. One rad equals
				  100 ergs per gram, or 0.01 gray.
"Radiation" means alpha particles, beta particles, gamma
				  rays, x-rays, neutrons, high-speed electrons, high-speed protons, and other
				  particles capable of producing ions. For purposes of these rules, this term is
				  synonymous with ionizing radiation. Equivalent terminology for non-ionizing
				  radiation is defined in Article 14.
"Radiation area" means any area accessible to individuals, in
				  which radiation levels could result in an individual receiving a dose
				  equivalent in excess of 0.05 mSv (0.005 rem) in one hour at 30 centimeters from
				  the source of radiation or from any surface that the radiation
				  penetrates.
"Radiation dose" (See "Dose")
"Radiation machine" means any device capable of producing
				  radiation except those devices with radioactive material as the only source of
				  radiation.
"Radiation Safety Officer" (RSO) means the individual
				  who:
For license conditions:
Meets the requirements in
				  10
				  CFR 35.50(a) or (c)(1),
				  revised July 16, 2018, and
				  10 CFR
				  35.59, revised March 27, 2006, incorporated
				  by reference, available under R9-7-10, and containing no future editions or
				  amendments; or
Is identified as a Radiation Safety Officer on a specific
				  medical use license issued by the Department, the NRC or another Agreement
				  State; or a medical use permit issued by a NRC master material licensee;
				  or
For registration conditions, is designated by the registrant
				  as the individual who has the knowledge, authority, and responsibility to apply
				  appropriate radiation protection principles to ensure radiation safety and
				  compliance with the Act, this Chapter, and any registration conditions.
"Radiation Safety Officer" (RSO) means the individual
				  who:
For license conditions:
Meets the requirements of
				  R9-7-407,
				  and for a medical license meets the training requirements of
				  R9-7-710;
				  or
Is identified as a Radiation Safety Officer on a specific
				  medical use license issued by the Department, the NRC, or another Agreement
				  State; or a medical use permit issued by a NRC master material licensee;
				  or
Meets the requirements in
				  R9-7-512
				  on a specific industrial license issued by the Department, the NRC, or another
				  Agreement State; or an industrial use permit issued by a NRC master material
				  licensee; or
For registration conditions, is designated by the registrant
				  as the individual who has the knowledge, authority, and responsibility to apply
				  appropriate radiation protection principles to ensure radiation safety and
				  compliance with the Act, this Chapter and any registration conditions.
"Radioactive marker" means radioactive material placed
				  subsurface or on a structure intended for subsurface use for the purpose of
				  depth determination or direction orientation.
"Radioactive material" means any solid, liquid, or gas which
				  emits radiation spontaneously.
"Radioactivity" means emission of electromagnetic energy or
				  particles or both during the transformation of unstable atomic nuclei.
"Radiographer" means any individual who performs or
				  personally supervises industrial radiographic operations and who is responsible
				  to the licensee or registrant for assuring compliance with the requirements of
				  this Chapter and all conditions of the license or certificate of
				  registration.
"Radiographer's assistant" means any individual who, under
				  the personal supervision of a radiographer, uses sources of radiation,
				  radio-graphic exposure devices, related handling tools, or survey instruments
				  in industrial radiography.
"Registrant" means any person who is registered with the
				  Department and is legally obligated to register with the Department pursuant to
				  these rules and the Act.
"Registration" is the process by which a person becomes a
				  registrant pursuant to Article 2 or 14 of this Chapter. With the exception of
				  registration of persons who install or service radiation machines, the types of
				  registrations issued by the Department are described in
				  R9-7-1302.
"Regulations of the U.S. Department of Transportation" means
				  the federal regulations in 49 CFR 107, revised April 19, 2017; 49 CFR 171,
				  revised April 19, 2017; 49 CFR 172, revised November 23, 2015; 49 CFR 173,
				  revised March 6, 2019; 49 CFR 174, revised February 28, 2019; 49 CFR 175,
				  revised October 18, 2018; 49 CFR 176, November 7, 2018; 49 CFR 177, revised
				  September 25, 2013; 49 CFR 178, revised November 7, 2018; 49 CFR 179, revised
				  September 25, 2018; and 49 CFR 180, revised March 30, 2017, incorporated by
				  reference, available under
				  R9-7-101,
				  and containing no future editions or amendments.
"Rem" means the special unit of dose equivalent (see "Dose
				  equivalent"). The dose equivalent in rem is equal to the absorbed dose in rad
				  multiplied by the quality factor (1 rem - 0.01 sievert).
"Research and Development" means exploration,
				  experimentation, or 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" means any area where the licensee or
				  registrant controls access for purposes of protecting individuals from exposure
				  to radiation and radioactive material. A restricted area does not include any
				  areas used for residential quarters, although a room or separate rooms in a
				  residential building may be set apart as a restricted area.
"Roentgen" (R) means the special unit of exposure and is
				  equal to the quantity of x or gamma radiation which causes ionization in air
				  equal to 258 microcoulomb per kilogram (see "Exposure").
"Safety system" means any device, program, or administrative
				  control designed to ensure radiation safety.
"Sealed 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.
"Sealed Source and Device Registry" means the national
				  registry that contains all the registration certificates, generated by both the
				  NRC and the Agreement States, that summarize the radiation safety information
				  for the sealed sources and devices and describe the licensing and use
				  conditions approved for each source or device.
"Shallow dose equivalent" (HS), which applies to the external
				  exposure of the skin of the whole body or the skin of an extremity, is taken as
				  the dose equivalent at a tissue depth of 0.007 centimeter (7 mg/cm2).
"Shielded position" means the location within a radiographic
				  exposure device or storage container which, by manufacturer's design, is the
				  proper location for storage of the sealed source.
"Sievert" means the SI unit of dose equivalent (see "Dose
				  equivalent"). The dose equivalent in sievert is equal to the absorbed dose in
				  gray multiplied by the quality factor (1 Sv = 100 rem).
"Site boundary" means that line beyond which the land or
				  property is not owned, leased, or otherwise controlled by the licensee or
				  registrant.
"Source changer" means a device designed and used for
				  replacement of sealed sources in radiographic exposure devices, including those
				  also used for transporting and storage of sealed sources.
"Source holder" means a housing or assembly into which a
				  radioactive source is placed for the purpose of facilitating the handling and
				  use of the source in well-logging operations.
"Source material" means:
Uranium or thorium, or any combination of uranium or thorium,
				  in any physical or chemical form; or
Ores that contain by weight 1/20 of 1 percent (0.05 percent)
				  or more of uranium, thorium, or any combination of uranium and thorium.
Source material does not include special nuclear
				  material.
"Source material milling" means any activity that results in
				  the production of byproduct material as defined by the second subsection under
				  the definition of "Byproduct material."
"Source of radiation" or "source" means any radioactive
				  material or any device or equipment emitting, or capable of producing,
				  radiation.
"Special form radioactive material" means radioactive
				  material that satisfies all of the following conditions:
It is either a single solid piece or is contained in a sealed
				  capsule that can be opened only by destroying the capsule;
The piece or capsule has at least one dimension not less than
				  5 millimeters (0.2 inch); and
It satisfies the test requirements specified in
				  10 CFR
				  71.75. A special form encapsulation designed
				  in accordance with the U.S. Nu-clear Regulatory Commission requirements in
				  effect on June 30, 1983, and constructed prior to July 1, 1985, may continue to
				  be used. A special form encapsulation designed in accordance with the
				  requirements of
				  10
				  CFR 71.4 in effect on March 31, 1996 (see 10
				  CFR part 71 , revised as of January 1, 1996), and constructed before April 1,
				  1998; and special form material that was success-fully tested before September
				  10, 2015 in accordance with the requirements of
				  10 CFR
				  71.75(d) in effect before
				  September 10, 2015 may continue to be used. Any other special form
				  encapsulation must meet the specifications of this definition.
"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; Uranium-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 one. For example, the
				  following quantities in combination would not exceed the limitation and are
				  within the formula:
Click here
				  to view
"Storage area" means any location, facility, or vehicle which
				  is used to store, transport, or secure a radiographic exposure device, storage
				  container, sealed source, or other source of radiation when it is not in
				  use.
"Storage container" means a device in which sealed sources
				  are transported or stored.
"Subsurface tracer study" means the release of a substance
				  tagged with radioactive material for the purpose of tracing the movement or
				  position of the tagged substance in the well-bore or adjacent formation.
"Survey" means an evaluation of the production, use, release,
				  disposal, or presence of sources of radiation or any combination thereof under
				  a specific set of conditions to determine actual or potential radiation
				  hazards. Such evaluations include, but are not limited to, tests, physical
				  examination and measurements of levels of radiation or concentration of
				  radioactive material present.
"TEDE" (See "Total Effective Dose Equivalent")
"Teletherapy" means therapeutic irradiation in which the
				  source of radiation is at a distance from the body.
"Temporary job site" means any location where sources of
				  radiation are used other than the specified locations listed on a license
				  document. Storage of sources of radiation at a temporary jobsite shall not
				  exceed six months unless the Department has granted an amendment authorizing
				  storage at that jobsite.
"Test" means the process of verifying compliance with an
				  applicable rule, order, or license condition.
"These rules" means all Articles of 9 A.A.C. 7.
"Total Effective Dose Equivalent" (TEDE) means the sum of the
				  effective dose equivalent (for external exposures) and the committed effective
				  dose equivalent (for internal exposures).
"Total Organ Dose Equivalent" (TODE) means the sum of the
				  deep-dose equivalent and the committed dose equivalent to the organ receiving
				  the highest dose. Determination of TODE is described in
				  R9-7-411.
"Tribal official" means the highest ranking individual that
				  represents Tribal leadership, such as the Chief, President, or Tribal Council
				  leadership.
"Unrefined and unprocessed ore" means ore in its natural form
				  prior to any processing, such as grinding, roasting, beneficiating, or
				  re-fining. Processing does not include sieving or encapsulation of ore or
				  preparation of samples for laboratory analysis.
"Unrestricted area" means any area access to which is not
				  controlled by the licensee for purposes of protection of individuals from
				  expo-sure to radiation and radioactive material. Any area used for residential
				  quarters is an unrestricted area.
"Uranium - natural, depleted, enriched."
Natural uranium means uranium (which may be chemically
				  separated) with the naturally occurring distribution of uranium isotopes
				  (approximately 0.711 weight percent uranium-235, and the remainder by weight
				  essentially uranium-238).
Depleted uranium means uranium containing less uranium-235
				  than the naturally occurring distribution of uranium isotopes.
Enriched uranium means uranium containing more uranium-235
				  than the naturally occurring distribution of uranium isotopes.
"U.S. Department of Energy" means the Department of Energy
				  established by P.L. 95-91, August 4, 1977, 91 Stat. 565,
				  42
				  U.S.C. 7101 et seq., to the extent that the
				  Department of Energy 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 of that agency under sections 104(b), (c), and (d) of the
				  Energy Reorganization Act of 1974 (P.L. 93-438, October 11, 1974, 88 Stat. 1233
				  at 1237,
				  42 U.S.C.
				  5814, effective January 19, 1975) and
				  retransferred to the Secretary of Energy under Section 301(a) of the Department
				  of Energy Organization Act (P.L. 95-91, August 4, 1977, 91 Stat. 565 at
				  577-578,
				  42 U.S.C. 7151,
				  effective October 1, 1977).
"Very high radiation area" means an area, accessible to
				  individuals, in which radiation levels from radiation sources external to the
				  body could result in an individual receiving an absorbed dose that exceeds 5
				  grays (500 rads) in one hour at one meter from a radiation source or one meter
				  from any surface that the radiation penetrates.
"Waste" (See "Low-level waste")
"Waste handling licensees" means persons licensed to receive
				  and store radioactive wastes prior to disposal and persons licensed to dis-pose
				  of radioactive waste.
"Week" means seven consecutive days starting on
				  Sunday.
"Well-bore" means a drilled hole in which wireline service
				  operations and subsurface tracer studies are performed.
"Well-logging" means the lowering and raising of measuring
				  devices or tools which may contain sources of radiation into wellbores or
				  cavities for the purpose of obtaining information about the well and adjacent
				  formations.
"Whole body" means, for purposes of external exposure, head,
				  trunk including male gonads, arms above the elbow, or legs above the
				  knee.
"Wireline" means an armored cable containing one or more
				  electrical conductors which is used to lower and raise logging tools in the
				  well-bore.
"Wireline service operation" means any evaluation or
				  mechanical service which is performed in the well-bore using devices on a
				  wireline.
"Worker" means any individual engaged in work under a license
				  or registration issued by the Department and controlled by employment or
				  contract with a licensee or registrant.
"WL" means working level, any combination of short-lived
				  radon daughters in 1 liter of air that will result in the ultimate emission of
				  1.3E + 5 MeV of potential alpha particle energy. The short-lived radon
				  daughters are - for radon-222: polonium-218, lead-214, bismuth-214, and
				  polonium-214; and for radon-220: polonium-216, lead-212, bismuth-212, and
				  polonium-212.
"WLM" means working level month, an exposure to one working
				  level for 170 hours (2,000 working hours per year divided by 12 months per year
				  is approximately equal to 170 hours per month).
"Workload" means the degree of use of an x-ray or gamma-ray
				  source per unit time.
"Year" means the period of time beginning in January used to
				  determine compliance with the provisions of these rules. The licensee or
				  registrant may change the starting date of the year used to determine
				  compliance by the licensee or registrant provided that the change is made at
				  the beginning of the year and that no day is omitted or duplicated in
				  consecutive years.