Section R12-1-102. Definitions

Terms defined in A.R.S. § 30-651 have the same meanings when used in this Chapter, unless the context otherwise requires. Addi- tional 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, revised January 1, 2013, incorporated by reference, and available under R12-1-101. This incorpo- rated material contains no future editions or amendments.

“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, revised January 1, 2013, incorporated by reference, and available under R12-1-101. This incorpo- rated material contains no future editions or amendments.

“Absorbed dose” means the energy imparted by ionizing radi- ation 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 bec- querel (Bq) and the curie (Ci).

“Adult” means an individual 18 or more years of age.

“Agency,” or “ARRA” means the Arizona Radiation Regula- tory Agency.

“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). “Nonagree- ment State” means any other state.

“Airborne radioactive material” means any radioactive mate- rial 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 present 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, consis- tent with the purpose for which the licensed or registered activity is undertaken, taking into account the state of technol- ogy, the economics of improvements in relation to state of technology, the economics of improvements in relation to ben- efits 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 uti- lizing x-rays to determine the elemental composition or to examine the microstructure 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.

“Authorized medical physicist” means an individual who meets the requirements in R12-1-711; or is identified as an authorized medical physicist or teletherapy physicist on:

A specific medical use license issued by the Agency, NRC, or another Agreement State;

A medical use permit issued by a NRC master material licensee;

A permit issued by an Agency, NRC, or another Agree- ment 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 R12-1-712; or is identified as an authorized nuclear pharmacist on:

A specific license issued by an Agency, NRC, or another Agreement State that authorizes medical use or the prac- tice of nuclear pharmacy;

A permit issued by a NRC master material licensee that authorizes medical use or the practice of nuclear phar- macy;

A permit issued by an Agency, NRC, or another Agree- ment State broad scope medical use licensee that autho- rizes medical use or the practice of nuclear pharmacy; or 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

Is identified as an authorized nuclear pharmacist by a commercial nuclear pharmacy that has been authorized to identify authorized nuclear pharmacists; or

Is designated as an authorized nuclear pharmacist in accordance with R12-1-311(G).

“Authorized user” means a physician, dentist, or podiatrist who meets the requirements in R12-1-719, R12-1-723, R12-1- 727, R12-1-728, or R12-1-744; or is identified as an autho- rized user on:

An Agency, 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 mate- rial;

A permit issued by an Agency, NRC, or another Agree- ment State specific licensee of broad scope that is autho- rized 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 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 con- tribute to background radiation and are not under the control of a licensee. “Background radiation” does not include sources of radiation regulated by the Agency.

“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 radia- tion incident to the process of producing or utilizing spe- cial nuclear material;

The tailings or wastes produced by the extraction or con- centration of uranium or thorium from ore processed pri- marily for its source material content, including discrete surface wastes resulting from uranium or thorium solu- tion    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 com- mercial, medical, or research activity; or any material that, has been made radioactive by use of a particle accel- erator;  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.

“Certifiable cabinet x-ray system” means an existing uncerti- fied x-ray system that meets or has been modified to meet the certification requirements specified in 21 CFR 1020.40, revised April 1, 2013, incorporated by reference, and available under R12-1-101. This incorporated material contains no future editions or amendments.

“Certificate holder” means a person who has been issued a cer- tificate of compliance or other package approval by the Agency or NRC.

“Certificate of Compliance” (CoC) means the certificate issued by the NRC under 10 CFR 71, Subpart D, (Revised Jan- uary 1, 2010, incorporated by reference, and available under R12-1-101. This incorporated material contains no future edi- tions or amendments.), which authorizes the design of a pack- age 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 sec- tions revised April 1, 2013, incorporated by reference, and available under R12-1-101. This incorporated material con- tains 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 Agency, pursuant to A.R.S. § 30- 687, for violations of the Act, this Chapter, or license condi- tions.

“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 equiva- lent 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 geo- graphical 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 radioac- tive drugs within the consortium for noncommercial distribu- tions 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.

“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 registra- tion issued by the Agency and for which the licensee has paid the license or registration fee for the current year according to R12-1-1304.

“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 per- cent of the total uranium present. Depleted uranium does not include special nuclear material.

“Discrete source” means a radionuclide that has been pro- cessed so that its concentration within a material has been pur- posely 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 equiva- lent, 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 modify- ing factors at the location of interest. The units of dose equiva- lent 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 prod- ucts 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 sys- tem constructed in such a way that access to the interior of the enclosure housing the x-ray source during operation is pre- cluded except through bypassing of interlocks or other safety devices to perform maintenance or servicing.

“Enclosed radiography” means industrial  radiography con- ducted by using cabinet radiography or shielded room radiog- raphy.

“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 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 Administra- tion.

“Field radiography” means industrial radiography, utilizing a portable or mobile x-ray system, which is not conducted in a shielded enclosure.

“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, ura- nium enrichment plants, or critical mass experimental facili- ties 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 and 191, revised July 1, 2013, incorporated by reference, and available under R12-1-101, 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 hazard- ous in A.R.S. § 49-921(5).

“Healing arts” means the practice of medicine, dentistry, oste- opathy, 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 Agency 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.

“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 concen- trations 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 equiva- lent. For purposes of this Chapter, “dosimeter” and “personnel dosimeter,” are equivalent terms. Examples of individual mon- itoring devices are film badges, thermoluminescence dosime- ters (TLDs), pocket ionization chambers, optical stimulation devices, and personal (“lapel”) air sampling devices.

“Individual monitoring equipment” means one or more indi- vidual monitoring devices. For purposes of this Chapter, “per- sonnel monitoring equipment” is an equivalent term.

“Industrial radiography” means the examination of the macro- scopic structure of materials by non-destructive methods uti- lizing 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 repre- sentative of the Agency, including but not limited to tests, sur- veys, and monitoring to determine compliance with rules, orders, requirements and conditions of the License or certifi- cate 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 wave lengths 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 tis- sue 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 Agency are described in R12-1-1302.

“Licensed material” means radioactive material received, pos- sessed, used, transferred, or disposed of under a general or specific license issued by the Agency.

“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 Agency under this Chapter to acquire, possess, transfer, or use sources of radiation.

“Licensing State” means any state having regulations equiva- lent 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

which is unknown. 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;

The tailings or wastes produced by the extraction or concentration of uranium or thorium from any ore processed primarily for its source material content.

“Major processor” means a user processing, handling, or man- ufacturing 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 medi- cine programs, universities, industrial radiographers, or small industrial programs. Type A and B quantities are defined in 10 CFR 71.4, revised January 1, 2013, incorporated by reference, and available under R12-1-101. This incorporated material contains no future editions or amendments.

“Medical dose” means a radiation dose intentionally delivered to an individual for medical examination, diagnosis, or treat- ment.

“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, radio active material concentrations, surface area activities, or quan- tities 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:

system that are struck by x-rays, including radiation source housings, port and shutter assemblies, collimator, sample hold-

Prefix            Multiplier

Symbol

Value

ers, cameras, goniometer, detectors and shielding but not including power supplies, transformers, amplifiers, readout devices, and control panels.

“Logging supervisor” means the individual who provides per- sonal 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

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

Radiation Regulatory Agency

femto           f                     10-15

atto              a                    10-18

“NARM” means any naturally occurring or accelerator-pro- duced 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 occur- ring radioactive material.

“Normal operating procedures” means the entire set of instruc- tions 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 proce- dures which are related to radiation safety.

“Natural radioactivity” means the radioactivity of naturally occurring radioactive substances.

“NRC” means Nuclear Regulatory Commission, the U.S. Nuclear Regulatory Commission, or its duly authorized repre- sentatives.

“Nuclear waste” means any highway route controlled quantity (defined in 49 CFR 173.403, revised October 1, 2012, incorpo- rated by reference, and available under R12-1-101; this incor- porated material contains 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 per- son. 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 admin- istered radioactive material and released in accordance with R12-1-717, 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.

“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 monitor- ing device”)

“Personal supervision” means supervision in which the super- vising individual is physically present at the site where sources of radiation and associated equipment are being used, watch- ing 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 ver- ifies training and experience required for an individual to become an authorized user, an authorized medical physicist, an authorized nuclear pharmacist, or a 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 radioactive source located in the radiation source housing.

“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 radia- tion, medical administration of radiation to the individual, exposure to an individual who has been administered radioac- tive material and released in accordance with R12-1-717, or voluntary participation in a medical research program.

“Pyrophoric liquid” means any liquid that ignites sponta- neously 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 lia- ble to cause fires through friction, retained heat from manufac- turing 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 appro- priate field by the American Board of Radiology or the Ameri- can Board of Health Physics, or having equivalent qualifications that provide the knowledge and training to mea- sure 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 hav- ing equivalent qualifications that provide training and experi- ence 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 clar- ification purposes, a qualified expert is not always an autho- rized 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 equiv- alent 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 sur- face 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 and who for license conditions:

Meets the requirements in 10 CFR 35.50(a) or (c)(1) and 10 CFR 35.59, (revised January 1, 2010, incorporated by reference, and available under R12-1-101. This incorporated material contains no future editions or amendments.); or is identified as a 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;

Or, who, 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 and who for license conditions:

Meets the requirements of R12-1-407, and for a medical license meets the training requirements of R12-1-710 or is identified as a Radiation Safety Officer on a specific medical use license issued by the Agency, NRC, or another Agreement State; or a medical use permit issued by a NRC master material licensee;

Or, who meets the requirements in R12-1-512 on a spe- cific industrial license issued by the Agency, NRC, or another Agreement State; or an industrial use permit issued by a NRC master material licensee;

Or, who, 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 sub- surface 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 per- sonally supervises industrial radiographic operations and who

is responsible to the licensee or registrant for assuring compli- ance 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, radiographic exposure devices, related handling tools, or survey instruments in industrial radiography.

“Registrant” means any person who is registered with the Agency and is legally obligated to register with the Agency pursuant to these rules and the Act.

“Registration” is the process by which a person becomes a reg- istrant pursuant to Article 2 of this Chapter. With the exception of registration of persons who install or service radiation machines, the types of registrations issued by the Agency are described in R12-1-1302.

“Regulations of the U.S. Department of Transportation” means the federal regulations in 49 CFR 107, 171 through 180, revised October 1, 2013, incorporated by reference, and avail- able under R12-1-101. This incorporated material contains 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, experimen- tation, 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, equip- ment, materials, and processes. Research and Development does not include the internal or external administration of radi- ation or radioactive material to human beings.

“Restricted area” means any area where the licensee or regis- trant 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 perma- nently bonded or fixed in a capsule or matrix designed to pre- vent 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 reg- istry 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

rial in combination shall not exceed one. For example, the fol- lowing quantities in combination would not exceed the limitation and are within the formula:

X-----g---m-----s--U-----2---3---5-- + Y----g----m----s---U-----2---3---3-- + Z----g----m----s---P----u-- £ I

equivalent”). The dose equivalent in sievert is equal to the

absorbed dose in gray multiplied by the quality factor (1 Sv =

350

200

200

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 mate- rial or any device or equipment emitting, or capable of produc- ing, radiation.

“Special form radioactive material” means radioactive mate- rial 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, revised January 1, 2013, incorporated by reference, available under R12-1-101. This incorporated material contains no future editions or amendments. A special form encapsulation designed in accordance with the U.S. Nuclear 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 constructed after June 30, 1985, shall meet requirements of this definition applicable at the time of its construction.

“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; Ura- nium-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 spec- ified above for the same kind of special nuclear material. The sum of such ratios for all of the kinds of special nuclear mate-

“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 combina- tion 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 mea- surements 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 tempo- rary jobsite shall not exceed six months unless the Agency 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 12 A.A.C. 1.

“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 R12-1-411.

“Unrefined and unprocessed ore” means ore in its natural form prior to any processing, such as grinding, roasting, beneficiat- ing, or refining.

“Unrestricted area” means any area access to which is not con- trolled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive material. Any area used for residential quarters is an unrestricted area.

“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 exercises functions formerly vested in the U.S. Atomic Energy Commission, its Chairman, members, officers, and compo- nents; and transferred to the U.S. Energy Research and Devel- opment Administration and to the administrator of that agency under sections 104(b), (c), and (d) of the Energy Reorganiza- tion 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 indi- viduals, in which radiation levels from radiation sources exter- nal 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 sur- face 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 dispose 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 well-bores 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 mechan- ical service which is performed in the well-bore using devices on a wireline.

“Worker” means any individual engaged in work under a license issued by the Agency and controlled by employment or contract with a licensee.

“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: polo- nium-218, lead-214, bismuth-214, and polonium-214; and for radon-220: polonium-216, lead-212, bismuth-212, and polo- nium-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 pro- vided that the change is made at the beginning of the year and that no day is omitted or duplicated in consecutive years.

Historical Note

Former Rule Section A.2. Former Section R12-1-102 repealed, new Section R12-1-102 adopted effective June 30, 1977 (Supp. 77-3). Amended effective November 19,

1982 (Supp. 82-6). Amended effective February 25, 1985

(Supp. 85-1). Amended by adding a new paragraph (31), subparagraph (w) and renumbering the former paragraph (31), subparagraphs (w) through (z) accordingly effective November 28, 1986 (Supp. 86-6). Amended by adding a new paragraph (34) and renumbering the former para- graphs (34) through (68) accordingly effective June 26,

1987 (Supp. 87-2). Amended effective April 2, 1990

(Supp. 90-2). Amended effective November 5, 1993

(Supp. 93-4). Amended effective February 18, 1994

(Supp. 94-1). Amended effective August 10, 1994 (Supp.

94-3). Amended effective January 2, 1996 (Supp. 96-1).

Amended effective June 13, 1997 (Supp. 97-2). Amended by final rulemaking at 5 A.A.R. 1817, effective May 12, 1999 (Supp. 99-2). Amended by final rulemaking at 7

A.A.R. 2584, effective June 8, 2001 (Supp. 01-2). Amended by final rulemaking at 9 A.A.R. 1126, effective May 9, 2003 (Supp. 03-1). Amended by final rulemaking at 10 A.A.R. 2122, effective July 3, 2004 (Supp. 04-2). Amended by final rulemaking at 10 A.A.R. 4458, effec- tive December 4, 2004 (Supp. 04-4). Amended by final rulemaking at 12 A.A.R. 75, effective February 7, 2006 (Supp. 05-4). Amended by final rulemaking at 13 A.A.R. 1217, effective May 5, 2007 (Supp. 07-1). Amended by final rulemaking at 15 A.A.R. 1023, effective August 1, 2009 (Supp. 09-2). Amended by final rulemaking at 18

A.A.R. 1895, effective September 10, 2012 (Supp. 12-3). Amended by final rulemaking at 20 A.A.R. 324, effective

March 8, 2014 (Supp. 14-1).