Louisiana Administrative Code
Title 33 - ENVIRONMENTAL QUALITY
Part XV - Radiation Protection
Chapter 1 - General Provisions
Section XV-102 - Definitions and Abbreviations

Universal Citation: LA Admin Code XV-102

Current through Register Vol. 50, No. 9, September 20, 2024

A. As used in these regulations, these terms have the definitions set forth below. Additional definitions used only in a certain chapter may be found in that Chapter.

A1- the maximum activity of special form radioactive material permitted in a Type A package.

A2- the maximum activity of radioactive material, other than special form, LSA, and SCO material, permitted in a Type A package. These values are either listed in, or may be derived in accordance with the procedure prescribed in, Appendix A of 10 CFR Part 71.

Absorbed Dose- the energy imparted by ionizing radiation per unit mass of irradiated material. The units of absorbed dose are the rad and the gray (Gy).

Accelerator-Produced Radioactive Material-any material made radioactive by a particle accelerator.

Act-the Louisiana Environmental Quality Act, (R.S. 30:2001 etseq).

Activity- the rate of disintegration or transformation or decay of radioactive material. The units of activity are the becquerel (Bq) and the curie (Ci).

Address of Use- the building or buildings that are identified on the license and where radioactive material may be received, prepared, used, or stored.

Administrative Authority-the Secretary of the Department of Environmental Quality or his designee or the appropriate assistant secretary or his designee.

Adult-an individual 18 or more years of age.

Agreement State-any state with which the U.S. Nuclear Regulatory Commission or the U.S. Atomic Energy Commission has entered into an effective agreement under subsection 274. b of the Atomic Energy Act of 1954, as amended. Non-agreement State means any other state.

Airborne Radioactive Material-any radioactive material dispersed in the air in the form of dusts, fumes, particulates, mists, vapors, or gases.

Airborne Radioactivity Area-a room, enclosure, or area in which airborne radioactive materials exist in concentrations:

1. in excess of the derived air concentrations (DACs) specified in LAC 33:XV.499.Appendix B, Table I of these regulations; or

2. to such a degree 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 12DAC-hours.

Alert- events that may occur, are in progress, or have occurred that could lead to a release of radioactive material but that the release is not expected to require a response by off-site response organizations to protect persons off-site.

Area of Use- a portion of a physical structure that has been set aside for the purpose of receiving, using, or storing radioactive material.

As Low As Is Reasonably Achievable (ALARA)- making every reasonable effort to maintain exposures to radiation as far below the dose limits in these regulations 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.

Atomic Energy Act-Atomic Energy Act of 1954 (68 Stat. 919), including any amendments thereto.

Associate Radiation Safety Officer-an individual who:

a. meets the requirements in LAC 33:XV.763.A and M; and

b. 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:
i. a specific medical use license issued by the NRC or an agreement state; or

ii. a medical use permit issued by a NRC master material licensee.

Authorized Medical Physicist- an individual who meets the requirements in LAC 33:XV.763.J. 1 and M, or who is identified as an authorized medical physicist or teletherapy physicist on:

1. a specific medical use license issued by the department, the U.S. Nuclear Regulatory Commission, or an agreement state;

2. a medical use permit issued by a U.S. Nuclear Regulatory Commission master material licensee;

3. a permit issued by the department, the U.S. Nuclear Regulatory Commission, or an agreement state broad scope medical use licensee; or

4. a permit issued by a U.S. Nuclear Regulatory Commission master material license broad scope medical use permittee.

Authorized Nuclear Pharmacist-a pharmacist who:

1. is board certified as a nuclear pharmacist by the Board of Pharmaceutical Specialties; or

2. is identified as an authorized nuclear pharmacist on a departmental, licensing state, Nuclear Regulatory Commission, or agreement state specific license that authorizes medical use or the practice of nuclear pharmacy; or

3. is identified as an authorized nuclear pharmacist on a permit issued by the department, licensing state, Nuclear Regulatory Commission, or agreement state broad scope medical use licensee that authorizes medical use or the practice of nuclear pharmacy; or

4. is identified as an authorized nuclear pharmacist on a permit issued by a Nuclear Regulatory Commission master material licensee that authorizes medical use or the practice of nuclear pharmacy; or

5. is identified as an authorized nuclear pharmacist on a permit issued by a Nuclear Regulatory Commission master material license broad scope medical use permittee that authorizes medical use or the practice of nuclear pharmacy; or

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

7. is designated as an authorized nuclear pharmacist in accordance with LAC 33:XV.328.J.2.d; or

8. meets the requirements specified in LAC 33:XV.763.K and M.

Authorized User- a physician, dentist, or podiatrist who is:

1. board certified by at least one of the boards listed in LAC 33:XV.763.C.l, D.l, E.l, F.l, H.l, or 1.1;

2. identified as an authorized user on a department, licensing state, Nuclear Regulatory Commission, or agreement state license that authorizes the medical use of radioactive material; or

3. identified as an authorized user on a permit issued by the department, licensing state, Nuclear Regulatory Commission, or agreement state specific licensee of broad scope authorized to permit the medical use of radioactive material.

Background Radiation- radiation from cosmic sources; naturally occurring radioactive materials, including radon, except as a decay product of source or special nuclear material, and including 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 the licensee. Background radiation does not include radiation from source, byproduct, or special nuclear materials regulated by the department.

Becquerel-the SI unit of measurement of radioactivity; it is equal to one disintegration per second. One curie is equal to 3.7 x 10 becquerels (bq).

Bioassay- 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 regulations, radiobioassay is an equivalent term.

Brachytherapy-a method of radiation therapy in which sealed sources are utilized to deliver a radiation dose at a distance of up to a few centimeters, by surface, intracavitary, or interstitial application.

Brachytherapy Source-a radioactive source or a manufacturer-assembled source train or a combination of these sources that is designed to deliver a therapeutic dose within a distance of a few centimeters.

Byproduct Material-

1. 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;

2. the tailings or wastes produced by the extraction or concentration of uranium or thorium (R.S. 30:2103) 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;

3. any discrete source of radium-226 that is produced, extracted, or converted after extraction, before, on, or after August 8, 2005, for use for a commercial, medical, or research activity; or

4. any material that has been made radioactive by use of a particle accelerator, and is produced, extracted, or converted after extraction, before, on, or after August 8, 2005, for use for a commercial, medical, or research activity; and

5. any discrete source of naturally occurring radioactive material, other than source material that the U. S. Nuclear Regulatory Commission, 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 the use in a commercial, medical, or research activity.

Calendar Quarter- any period consisting of 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 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. The method observed by the licensee or registrant for determining calendar quarters shall only be changed at the beginning of a year.

Calibration- the determination of:

1. the response or reading of an instrument relative to a series of known radiation values over the range of the instrument; or

2. the strength of a source of radiation relative to a standard.

CFR- Code of Federal Regulations.

Chelating Agents- amine polycarboxylie acids, hydroxy-carboxylic acids, gluconic, and polycarboxylic acids.

Chiropractor- an individual licensed in the practice of chiropractic, as provided in R.S. 37:2801 et seq.

Client's Address- the area of use or a temporary jobsite for the purpose of providing mobile medical service in accordance with LAC 33:XV.726.

Collective Dose- 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.

Commission-the U.S. Nuclear Regulatory Commission or its duly authorized representatives.

Committed Dose Equivalent (Ht,50)- 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)- 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 = [SIGAM]WT,HT,50)-

Consortium-an association of medical use licensees and a positron emission tomography (PET) radionuclide production facility as defined in this Section located in the same geographical area. They shall 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 as defined in this Section. The PET radionuclide production facility within the consortium shall be located at an educational institution, a federal facility, or a medical facility.

Controlled Area- an area, outside a restricted area but inside the site boundary, to which access can be limited by the licensee for any reason.

Curie-the amount of radioactive material that disintegrates at the rate of 37 billion atoms per second or 3.7 x 1010 disintegrations per second (dps). Commonly used submultiples of the curie are the millicurie and the microcurie. One millicurie (mCi) is equal to 0.001 curie, which is equal to 3.7 x 107 dps. One microcurie (µCi) is equal to 0.000001 curie, which is equal to 3.7 x 104 dps. One curie is equal to 3.7 x 1010 becquerels.

Decommission- to remove (as a facility) safely from service and reduce residual radioactivity to a level that permits:

1. release of the property for unrestricted use and termination of license; or

2. release of the property under restricted conditions and termination of the license.

Dedicated Check Source- a radioactive source that is used to assure the constant operation of a radiation detection or measurement device over several months or years. This source may also be used for other purposes.

Deep Dose Equivalent (Hd)- the dose equivalent at a tissue depth of 1 centimeter (1000 mg/cm), which applies to external whole body exposure.

Dentist- an individual licensed by a state or territory of the United States, the District of Columbia, or the Commonwealth of Puerto Rico to practice dentistry.

Department- the Department of Environmental Quality.

Depleted Uranium- 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-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.

Distinguishable from Background- the detectable concentration of a radionuclide that is statistically different from the background concentration of that radionuclide in the vicinity of the site or, in the case of structures, in similar materials using adequate measurement technology, survey, and statistical techniques.

Dose- 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 regulations, radiation dose is an equivalent term.

Dose Commitment- the total radiation dose to a part of the body that will result from retention in the body of radioactive material. For purposes of estimating the dose commitment, it is assumed that from the time of intake the period of exposure to retained material will not exceed 50 years.

Dose Equivalent (HT)- 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 sivert (Sv) and rem.

Effective Dose Equivalent (HE)- 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 =[SIGMA] wTHT).

Embryo/Fetus- the developing human organism from conception until the time of birth.

Emergency- any condition existing outside of the bounds of nuclear operating sites owned or licensed by a federal agency, and further any condition existing within or outside of the jurisdictional confines of a facility licensed or registered by the department and arising from the presence of byproduct material, source material, special nuclear material, or any other radioactive material or source of radiation that is endangering or could reasonably be expected to endanger the health and safety of the public or to contaminate the environment (R.S. 30:2105).

Entrance or Access Points- any opening through which an individual or extremity of an individual could gain access to radiation areas or to licensed or registered radioactive materials. This includes entry or exit portals of sufficient size to permit human entry, irrespective of their intended use.

Explosive Material- any chemical compound, mixture, or device that produces a substantial instantaneous release of gas and heat spontaneously or by contact with sparks or flame as referenced in 49 CFR 173.53 - 173.114(a).

Exposure- being exposed to ionizing radiation or to radioactive material.

Exposure Rate- the exposure per unit of time, such as Roentgen per minute (R/min) and milliroentgen per hour (mR/hr).

External Dose- that portion of the dose equivalent received from any source of radiation outside the body.

Extremity- hand, elbow, arm below the elbow, foot, knee, and leg below the knee.

Former U.S. Atomic Energy Commission (AEC) or U.S. Nuclear Regulatory Commission (NRC) Licensed Facilities- 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- standards issued by the U.S. Environmental Protection Agency (EPA) 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.

Government Agency-any executive department, commission, independent establishment, corporation, wholly or partly owned by the United States of America which is an instrumentality of the United States, or any board, bureau, division, service, office, officer, authority, administration, or other establishment in the executive branch of the government.

Gray- the SI unit of absorbed dose; it is equal to one Joule per kilogram. One rad is equal to 0.01 gray (Gy).

Hazardous Waste- those wastes designated as hazardous by U.S. Environmental Protection Agency regulations in 40 CFR 261 and by Louisiana Administrative Code regulations inLAC33:V.

Healing Art- the professional disciplines authorized by the laws of this state to use radiation or radioactive material in the diagnosis or treatment of human or animal disease.

High Dose-Rate Remote Afterloader- a brachytherapy device that remotely delivers a dose rate in excess of 12 gray (1200 rads) per hour at the point or surface where the dose is prescribed.

High-Level Waste- unreprocessed spent fuel rods or that waste resulting from the reprocessing of spent fuel rods.

High-Radiation Area- 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 100 millirems (one millisievert) in one hour at 30 centimeters from the radiation source or 30 centimeters from any surface that the radiation penetrates.

Human Use- the internal or external administration of radiation or radioactive materials to human beings.

Indian Tribe-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. 5130.

Individual- any human being.

Individual Monitoring- the assessment of:

1. dose equivalent by the use of individual monitoring devices or by the use of survey data; or

2. committed effective dose equivalent by bioassay or by determination of the time-weighted air concentration to which an individual has been exposed, that is, DAC-hours. (See the definition of DAC-Hours in LAC 33:XV.Chapter 4.)

Individual Monitoring Devices- devices designed to be worn by a single individual for the assessment of dose equivalent. For purposes of these regulations, personnel dosimeter and dosimeter are equivalent terms. Examples of individual monitoring devices are film badges, thermoluminescence dosimeters (TLDs), pocket ionization chambers, and personal air sampling devices.

Inspection-an official examination or observation including, but not limited to, tests, surveys, and monitoring to determine compliance with rules, regulations, orders, requirements, and conditions of the department and/or administrative authority.

Instrument Traceability-the ability to show that an instrument has been calibrated at specified time intervals using a national standard or a transfer standard. If a transfer standard is used, the calibration must be at a laboratory accredited by a program that requires continuing participation in measurement quality assurance with the National Institute of Standards and Technology or other equivalent national or international programs.

Interlock-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-that portion of the dose equivalent received from radioactive material taken into the body.

Ionizing Radiation-any electromagnetic or particulate radiation capable of producing ions, directly or indirectly, in its passage through matter. It includes any or all of the following: alpha rays, beta rays, gamma rays, X-rays, neutrons, high-speed electrons, high-speed protons, and other atomic particles, but not sound or radio waves, or visible, infrared, or ultraviolet light.

Lens Dose Equivalent (LDE)- the external exposure of the lens of the eye, which is taken as the dose equivalent at a tissue depth of 0.3 centimeter (300 mg/cm2).

License Issuing Authority-the licensing agency that issued the license, i.e. the department, the U.S. Nuclear Regulatory Commission, or the appropriate agency of an agreement state.

Licensed (or Registered) Material- radioactive material received, possessed, used, transferred, or disposed of under a general or specific license (or registration) issued by the department.

Licensee-any person who is licensed by the department in accordance with the act and regulations promulgated by the administrative authority (R.S. 30:2105).

Licenses-general licenses and specific licenses.

1. General License-a license effective pursuant to regulations promulgated by the administrative authority without the filing of an application to transfer, acquire, own, possess, or use quantities of, or devices or equipment utilizing, byproduct, source or special nuclear materials, technologically enhanced natural radioactive material, or other radioactive material occurring naturally or produced artificially.

2. Specific License-a license issued after application to the department to use, manufacture, produce, transfer, receive, acquire, own, or possess quantities of, or devices or equipment utilizing byproduct, source, or special nuclear materials, technologically enhanced natural radioactive material, or other radioactive material occurring naturally or produced artificially (R.S. 30:2105).

Licensing State-any state with regulations equivalent to or more stringent than "Suggested State Regulations for Control of Radiation" relating to, and an effective program for, the regulatory control of naturally occurring or accelerator-produced radioactive material (NARM).

Limits (Dose Limits)-the permissible upper bounds of radiation doses.

Lost or Missing Licensed ( or Registered) Material-licensed (or registered) material whose location is unknown. It includes material that has been shipped but has not reached its destination and whose location cannot be readily traced in the transportation system.

Lost or Missing Licensed (or Registered) Source of Radiation-licensed (or registered) source of radiation whose location is unknown. This definition includes but is not limited to, radioactive material that has been shipped but has not reached its planned destination and whose location cannot be readily traced in the transportation system.

Low Dose-Rate Remote Afterloader-a brachytherapy device that remotely delivers a dose rate of less than or equal to 2 gray (200 rads) per hour at the point or surface where the dose is prescribed.

Major Processor-a user processing, handling, or manufacturing radioactive material exceeding Type A quantities as unsealed sources of material, or exceeding four times Type B quantities as sealed sources, but not including nuclear medicine programs, universities, industrial radiographers, or small industrial programs. Type A and B quantities are defined in 10 CFR 71.4.

Management-the chief executive officer or that individual's designee.

Manual Brachytherapy-a type of brachytherapy in which the brachytherapy sources (e.g., seeds, ribbons) are manually placed topically on or inserted either into the body cavities that are in close proximity to a treatment site or directly into the tissue volume.

Medical Event-an event that meets the criteria in LAC 33:XV.613.A, 712.A, or 915.A.

Medical Institution-an organization in which several medical disciplines are practiced and that has inpatient facilities.

Medical Use-the intentional internal or external administration of radioactive material, or the radiation therefrom, to patients or human research subjects under the supervision of an authorized user as defined in this Section.

Medium Dose-Rate Remote Afterloader-a brachytherapy device that remotely delivers a dose rate of greater than 2 gray (200 rads), but less than 12 gray (1200 rads), per hour at the point or surface where the dose is prescribed.

Member of the Public-any individual, except when that individual is receiving an occupational dose.

Metric Prefixes and Abbreviations-

c

centi

(=10-2)

f

femto

(=10-15)

m

milli

(=10-3)

k

kilo

(=103)

µ

micro

(=10-6)

M

mega

(=106)

n

nano

(=10-9)

G

giga

(=109)

P

pico

(=10-12)

T

tera

(=1012)

Minor- an individual less than 18 years of age.

Mobile Medical Service- the transportation of radioactive material to, and its medical use at, the client's address.

Mobile Nuclear Medicine Service- the transportation and medical use of radioactive material.

Monitoring- 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 regulations, radiation monitoring and radiation protection monitoring are equivalent terms.

Nationally Tracked Source- a sealed source containing a quantity equal to or greater than the Category 1 or Category 2 levels of any radioactive material listed in LAC 33:XV.399.Appendix G. In this context a sealed source is defined as radioactive material that is sealed in a capsule or closely bonded, in a solid form, and that is not exempt from regulatory control. It does not mean material encapsulated solely for disposal, or nuclear material contained in any fuel assembly, subassembly, fuel rod, or fuel pellet. Category 1 nationally tracked sources are those containing radioactive material at a quantity equal to or greater than the Category 1 threshold. Category 2 nationally tracked sources are those containing radioactive material at a quantity equal to or greater than the Category 2 threshold but less than the Category 1 threshold.

Natural Radioactivity- radioactivity from naturally occurring radioactive materials (NORM).

Naturally Occurring or Accelerator-Produced Radioactive Material (NARM)- any nuclide that is radioactive in its natural physical state (i.e., not man-made) or that has been made radioactive by exposure to an accelerator beam. This material does not include source, byproduct, or special nuclear material.

Nuclear Regulatory Commission (NRC)- the U.S. Nuclear Regulatory Commission or its duly authorized representatives.

Occupational Dose- the dose received by an individual in the course of employment in which the individual's assigned duties for the licensee or registrant involve exposure to sources of radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee, registrant, or other person. Occupational dose does not include dose received: from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released in accordance with LAC 33:XV.725, from voluntary participation in medical research programs, or as a member of the public.

Ophthalmic Physicist-an individual who:

a. meets the requirements in LAC 33:XV.719.N.1.b and 763.M; and

b. is identified as an ophthalmic physicist on a:
i. specific medical use license issued by the NRC or an agreement state;

ii. permit issued by a NRC or agreement state broad scope medical use licensee;

iii. medical use permit issued by a NRC master material licensee; or

iv. permit issued by a NRC master material licensee broad scope medical use permittee.

Ore Refineries- all processors of ore containing natural radioactivity.

Output- the exposure rate, dose rate, or a quantity related in a known manner to these rates from a brachytherapy source or a teletherapy unit, a remote afterloader, or a gamma stereotactic radiosurgery unit for a specified set of exposure conditions.

Package- the packaging together with its radioactive contents as presented for transport.

Particle Accelerator-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 megaelectron volt.

Patient Intervention-actions by the patient or human research subject, whether intentional or unintentional, such as dislodging or removing treatment devices or prematurely terminating the administration.

Person- any individual, corporation, partnership, firm, association, trust, estate, public or private institution, group, agency, political subdivision of this state or any other state or political subdivision or agency thereof, and any legal successor, representative, agent, or agency of the foregoing, other than the U.S. Nuclear Regulatory Commission or federal government agencies licensed by the U.S. Nuclear Regulatory Commission (R.S. 30:2105).

Personnel-Monitoring Equipment- devices such as film badges, pocket dosimeters, or thermoluminescent dosimeters designed to be worn or carried by an individual for the purpose of estimating the dose received by the individual.

Pharmacist- any individual licensed by a state or territory of the United States, the District of Columbia, or the Commonwealth of Puerto Rico to practice pharmacy.

Physician- a medical doctor or doctor of osteopathy licensed by a state or territory of the United States, the District of Columbia, or the Commonwealth of Puerto Rico to prescribe drugs in the practice of medicine, or who is authorized to practice medicine under the provisions of R.S. 37:1261 etseq.

Podiatrist- an individual licensed by a state or territory of the United States, the District of Columbia, or the Commonwealth of Puerto Rico to practice podiatry.

Positron Emission Tomography (PET) Radionuclide Production Facility-a facility operating a cyclotron or accelerator for the purpose of producing PET radionuclides.

Preceptor- an individual who provides, directs, or verifies the training and experience required for an individual to become an authorized user, an authorized medical physicist, an authorized nuclear pharmacist, or a radiation safely officer.

Prescribed Dosage- the quantity of radiopharmaceutical activity as documented:

1. in a written directive; or

2. either in the diagnostic clinical procedures manual or in any appropriate record in accordance with the directions of the authorized user for diagnostic procedures.

Prescribed Dose-

1. for gamma stereotactic radiosurgery, the total dose as documented in the written directive;

2. for teletherapy, the total dose and dose per fraction as documented in the written directive; or

3. for manual brachytherapy, either the total source strength and exposure time or the total dose, as documented in the written directive; or

4. for remote brachytherapy afterloaders, the total dose and dose per fraction in the written directive.

Principal Activities- activities authorized by the license that are essential to achieving the purpose(s) for which the license was issued or amended. Storage during which no licensed material is accessed for use or disposal and activities incidental to decontamination or decommissioning are not principal activities.

Protective Apron- an apron made of radiation-attenuating materials used to reduce exposure to radiation.

Public Dose- the dose received by a member of the public from exposure to sources of radiation and/or radioactive material released from licensed or registered operations. Public dose does not include occupational dose, dose received from background radiation, dose received from any medical administration the individual has received, dose received from exposure to individuals administered radioactive material and released in accordance with LAC 33:XV.725, or dose received from voluntary participation in medical research programs.

Pulsed Dose-Rate Remote Afterloader- a special type of remote afterloading brachytherapy device that uses a single source capable of delivering dose rates in the "high dose-rate" range, but:

1. is approximately one-tenth of the activity of typical high dose-rate remote afterloader sources; and

2. is used to simulate the radiobiology of a low dose-rate treatment by inserting the source for a given fraction of each hour.

Pyrophoric Liquid- any liquid that ignites spontaneously in dry or moist air at or below 130°F (54.4°C), or any solid material, other than one classed as an explosive, that under normal conditions is liable to cause fires through friction, retained heat from manufacturing or processing, or that can be ignited readily and, when ignited, burns so vigorously and persistently as to create a serious transportation, handling, or disposal hazard. Included are spontaneously combustible and water-reactive materials.

Qualified Expert- an individual who has demonstrated to the satisfaction of the department that he or she possesses the knowledge and training to measure ionizing radiation parameters, to evaluate safety techniques, and to advise regarding radiation protection needs.

Quality Factor (Q)- the modifying factor, listed in Tables I and II of this Section, that is used to derive dose equivalent from absorbed dose.

Rad- a special unit of absorbed dose. One rad equals one hundredth (0.01) of a Joule per kilogram of material. For example, if tissue is the material of interest, then 1 rad equals 100 ergs per gram of tissue. The SI unit of absorbed dose is the gray (Gy). One gray is equal to one Joule per kilogram.

Radiation- any electromagnetic or ionizing radiation including gamma rays and X-rays, alpha and beta particles, high-speed electrons, neutrons, high-speed protons, and other nuclear particles, but not sound waves. (R.S. 30:2105.) Unless specifically stated otherwise, these regulations apply only to ionizing radiation.

Radiation Area-an area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of five millirems (0.05 millisievert) in one hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates.

Radiation Machine- any device capable of producing radiation except those which produce radiation only from radioactive material.

Radiation Safety Officer- an individual who:

1. meets the requirements in LAC 33:XV.763.A. 1 or 3.a and M; or

2. is identified as a radiation safety officer on:
a. a specific medical use license issued by the agreement state or Nuclear Regulatory Commission; or

b. a medical use permit issued by a Nuclear Regulatory Commission master material licensee.

Radiation Therapy Simulation System- a radiographic or fluoroscopic X-ray system intended for localizing the volume to be exposed during radiation therapy and confirming the position and size of the therapeutic irradiation field.

Radioactive Material- any material, whether solid, liquid, or gas, that emits radiation spontaneously (R.S. 30:2105).

Radioactivity- the transformation of unstable atomic nuclei by the emission of radiation. A unit of quantity of radioactivity is the curie (Ci). The SI unit of measurement of radioactivity is the Becquerel (Bq), which is equal to one transformation per second (tps). One curie is equal to 3.7 x 1010Bq.

Radiological Physicist- an individual who:

1. is certified in Therapeutic Radiological Physics or Radiological Physics by the American Board of Radiology,or in radiation oncology physics by the American Board of Medical Physics; or

2. has a master's or a doctor's degree in physics, biophysics, radiological physics, health physics, or nuclear engineering; has had one year's full-time training in therapeutic radiological physics; and has had one year's full-time work experience in a radiotherapy facility where the individual's duties involved calibration and spot checks of a medical accelerator or a sealed source teletherapy unit; or

3. has a bachelor's degree in physics, biophysics, radiological physics, health physics, or nuclear engineering; and has performed full-time radiation physics work for a period of at least five years in therapeutic radiological physics in radiotherapy facilities where the individual's duties involved calibration and spot checks of a medical accelerator or sealed source teletherapy unit.

Recordable Events- in medical procedures, the administration of:

1. a radiopharmaceutical or radiation without a written directive when a written directive is required;

2. a radiopharmaceutical or radiation when a written directive is required, without daily recording of each administered radiopharmaceutical dosage or radiation dose in the appropriate record;

3. a radiopharmaceutical dosage greater that 30 microcuries of either sodium iodide I-125 or I-131 when both:
a. the administered dosage differs from the prescribed dosage by more than 10 percent of the prescribed dosage; and

b. the difference between the administered dosage and prescribed dosage exceeds 15 microcuries;

4. a therapeutic radiopharmaceutical dosage, other than sodium iodide I-125 or I-131, when the administered dosage differs from the prescribed dosage by more than 10 percent of the prescribed dosage;

5. a teletherapy radiation dose when the calculated weekly administered dose exceeds the weekly prescribed dose by 15 percent or more; or

6. a brachytherapy radiation dose when the calculated administered dose differs from the prescribed dose by more than 10 percent of the prescribed dose.

Registrant- any person who owns or possesses any radioactive material or device capable of emitting radiation and who is legally obligated to register with the department pursuant to these regulations and the act.

Registration- the identification of any material or device capable of emitting radiation, together with such other information as the owner of such material or device is required to furnish by rules and regulations adopted hereunder (R.S. 30:2105).

Regulations of the U.S. Department of Transportation (U. S. DOT)- the regulations in 49 CFR 100- 189.

Rem- a measure of the dose of any radiation to body tissue in terms of its estimated biological effect relative to a dose received from an exposure to one Roentgen (R) of X-rays. One millirem (mRem) is equal to 0.001 Rem. Rem is a special unit of dose equivalent. (See dose equivalent) For the purpose of these regulations, any of the following is considered to be equivalent to a dose of one Rem:

1. an exposure of one Roentgen of X or gamma radiation;

2. absorbed dose of one rad due to X, gamma, or beta radiation;

3. an absorbed dose of 0.05 rad due to particles heavier than protons and with sufficient energy to reach the lens of the eye; or

4. an absorbed dose of 0.1 rad due to neutrons or high-energy protons.

(NOTE: If it is more convenient to measure the neutron flux, or equivalent, than to determine the neutron absorbed dose in rads, one Rem of neutron radiation may, for purposes of these regulations, be assumed to be equivalent to 14 million (1.4 x 107) neutrons per sjuare centimeter incident upon the body; or, if there exists sufficient information to estimate with reasonable accuracy the approximate distribution in energy of the neutrons, the incident number of neutrons per square centimeter equivalent to one Rem may be estimated from the table in LAC 33:XV.199.Appendix A.)

Research and Development- theoretical analysis, exploration, or 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.

Residual Radioactivity- radioactivity in structures, materials, soils, groundwater, and other media at a site resulting from activities under the licensee's control. This includes radioactivity from all licensed and unlicensed sources used by the licensee, but excludes background radiation. It also includes radioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site and previous burials at the site, even if those burials were made in accordance with the provisions of LAC 33:XV.Chapter 4.

Restricted Area- an area, access to which is limited by the licensee or registrant for the purpose of protecting individuals against undue risks from exposure to sources of radiation. A restricted area does not include areas used as residential quarters, but separate rooms in a residential building may be set apart as a restricted area.

Roentgen (R)- a special unit of exposure. One Roentgen equals 2.58 x 10-4 Coulomb/kilogram of air. (See exposure)

Sealed Source-any byproduct material that is encased in a capsule designed to prevent leakage or escape of the byproduct material.

Sealed Source and Device Registry- the national registry that contains all the registration certificates, generated by both the U.S. Nuclear Regulatory Commission 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 the products.

Shallow Dose Equivalent (Hs)- applies to the external exposure of the skin of the whole body or the skin of an extremity, and is taken as the dose equivalent at a tissue depth of 0.007 centimeter (7 mg/cm2).

SI- the International System of Units.

Sievert (Sv)-the SI unit of any of the quantities expressed as dose equivalent; it is equal to one Joule per kilogram. One Rem is equal to 0.01 Sievert. The dose equivalent in sieverts is equal to the absorbed dose in grays multiplied by the quality factor (1 Sv = 100 rems).

Site Area Emergency- events that may occur, are in progress, or have occurred that could lead to a significant release of radioactive material and that could require a response by off-site response organizations to protect persons off-site.

Site Boundary- that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee or registrant.

Source Material- uranium or thorium, or any combination thereof, in any physical or chemical form; or ores that contain by weight 0.05 percent or more of uranium, thorium, or any combination thereof. Source material does not include special nuclear material as hereinafter defined (R.S. 30:2105).

Source of Radiation- any radioactive material or any device or equipment emitting or capable of producing radiation (R.S. 30:2105).

Source Traceability- the ability to show that a radioactive source has been calibrated either by the national standards laboratory of the National Institute of Standards and Technology (NIST) or by a laboratory that participates in a continuing measurement quality assurance program with NIST or other equivalent national or international programs.

Special Form Material- radioactive material which satisfies the following:

1. it is either a single solid piece or is contained in a sealed capsule that can be opened only by destroying the capsule;

2. the piece or capsule has at least one dimension not less than 5 millimeters (0.197 inch);

3. it satisfies the test requirements of 10 CFR 71.75; and

4. a special form encapsulation designed in accordance with the requirements of 10 CFR 71.4(o) in effect on June 30, 1983, and constructed prior to July 1, 1985, may continue to be used. A special form encapsulation either designed or constructed after June 30, 1985, must meet requirements of this Section applicable at the time of its design or construction.

Special Nuclear Material- either of the following types of material:

1. plutonium, uranium-233, uranium enriched in the isotope U-233 or in the isotope U-235, and any other material that the U.S. Nuclear Regulatory Commission, pursuant to the provisions of Section 51 of the Atomic Energy Act of 1954, as amended, determines to be special nuclear material, but does not include source material; or

2. any material artificially enriched by any of the foregoing, but not including source material. (R.S. 30:2105)

Special Nuclear Material in Quantities Not Sufficient to Form Critical Mass- 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 "1" (i.e., unity). For example, the following quantities in combination would not exceed the limitation and are within the formula:

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SPOC-the Office of Environmental Compliance, Emergency and Radiological Services Division, Single Point of Contact (SPOC).

State-a state of the United States, the District of Columbia, the Commonwealth of Puerto Rico, the Virgin Islands, Guam, American Samoa, and the Commonwealth of the Northern Mariana Islands.

Stereotactic Radiosurgery- the use of external radiation in conjunction with a stereotactic guidance device to very precisely deliver a therapeutic dose to a tissue volume.

Structured Educational Program- an educational program designed to impart particular knowledge and practical education through interrelated studies and supervised training.

Survey- an evaluation of the production, use, release, disposal, transfer, and/or presence of sources of radiation under a specific set of conditions to determine actual or potential radiation hazards. When appropriate, such evaluation includes, but is not limited to, tests, physical examination, and measurements of levels of radiation or concentrations of radioactive materials present.

Technologically Enhanced Natural Radioactive Material (hereinafter referred to as TENR)- natural sources of radiation that would not normally appear without some technological activity not expressly designed to produce radiation (R.S. 30:2105).

Teletherapy- therapeutic irradiation in which the source of radiation is at a distance from the body.

Teletherapy Physicist- refer to radiological physicist.

Temporary Jobsite- any location where sources of radiation are used other than the location(s) listed in a license or registration certificate for nonlicensed sources of radiation.

Test- the process of verifying compliance with an applicable regulation.

Therapeutic Dosage- a dosage of unsealed radioactive material that is intended to deliver a radiation dose to a patient or human research subject for palliative or curative treatment.

Therapeutic Dose- a radiation dose delivered from a source containing radioactive material to a patient or human research subject for palliative or curative treatment.

These Regulations- all chapters of the Louisiana Radiation Protection Regulations (LAC 33:XV).

Total Effective Dose Equivalent (TEDE)-the sum of the effective dose equivalent for external exposures and the committed effective dose equivalent for internal exposures.

Traceable to National Standards- see Instrument Traceability or Source Traceability.

Treatment Site- the anatomical description of the tissue intended to receive a radiation dose, as described in a written directive.

Tribal Official-the highest ranking individual that represents tribal leadership, such as the chief, president, or tribal council leadership.

Type of Use- use of radioactive material as described in LAC 33:XV.729, 731, 735, 739, 741, or 747.

Unit Dosage- a dosage prepared for medical use for administration as a single dosage to a patient or human research subject without any further manipulation of the dosage after it is initially prepared.

United States-when this term is used in a geographical sense, it includes Puerto Rico, all territories, and possessions of the United States.

Units of Activity- for purposes of these regulations, activity is expressed in the SI unit of becquerel (Bq) or in the special unit of curie (Ci), or their multiples, or disintegrations or transformations per unit of time:

1. one becquerel (Bq) = 1 disintegration or transformation per second (dps or tps).

2. one curie (Ci) = 3.7E+10 disintegrations or transformations per second (dps or tps) = 3.7E+10 becquerel (Bq) = 2.22E+12 disintegrations or transformations per minute (dpm or tpm).

Units of Exposure and Dose-

1. As used in these regulations, the unit of exposure is the coulomb per kilogram (C/kg) of air. One roentgen is equal to 2.58E-4 coulomb per kilogram of air.

2. As used in these regulations, the units of dose are:
a. Gray (Gy)- the SI unit of absorbed dose. One gray is equal to an absorbed dose of 1 joule per kilogram (100 rad).

b. Rad- the special unit of absorbed dose. One rad is equal to an absorbed dose of 100 erg per gram or 0.01 joule per kilogram (0.01 Gy).

c. Rem- the special unit of any of the quantities expressed as dose equivalent. Lhe dose equivalent in rem is equal to the absorbed dose in rad multiplied by an appropriate quality factor (1 rem = 0.01 Sv).

d. Sievert- the SI unit of any of the quantities expressed as dose equivalent. Lhe dose equivalent in sieverts is equal to the absorbed dose in gray multiplied by an appropriate quality factor (1 Sv = 100 rem).

3. As used in these regulations, the quality factors for converting absorbed dose to dose equivalent are shown in Table I.

Table I

Quality Factors and Absorbed Dose Equivalencies

Type of Radiation

Quality Factor (Q)

Absorbed Dose Equal to a Unit Dose Equivalenta

X, gamma, or beta radiation and high speed electrons

1

1.0

Alpha particles, multiple-charged particles, fission fragments, and heavy particles of unknown charge

20

0.05

Neutrons of unknown energy

10

0.1

High energy protons

10

0.1

aThis value is the absorbed dose in gray equal to 1 Sv or the absorbed dose in rad equal to 1 rem.

4. If it is more convenient to measure the neutron fluence rate than to determine the neutron dose equivalent rate in sievert per hour or rem per hour, as provided in Paragraph 3 of this definition, 0.01 Sv (1 rem) of neutron radiation of unknown energies may, for purposes of these regulations, be assumed to result from a total fluence of 25 million neutrons per square centimeter incident upon the body. If sufficient information exists to estimate the approximate energy distribution of the neutrons, the licensee or registrant may use the fluence rate per unit dose equivalent or the appropriate Q value from Lable II to convert a measured tissue dose in gray or rad to dose equivalent in sievert or rem.

Table II

Mean Quality Factors, Q, and Fluence Per Unit Dose Equivalent For Monoenergetic Neutrons

Neutron Energy (MeV)

Quality Factora(Q)

Fluence per Unit Dose Equivalent (neutrons cm -2 rem-1)

Fluence per Unit Dose Equivalentb (neutrons cm -2 Sv-1)

2.5E-8 (Thermal)

2

980E+6

980E+8

1E-7

2

980E+6

980E+8

1E-6

2

810E+6

810E+8

1E-5

2

810E+6

810E+8

1E-4

2

840E+6

840E+8

1E-3

2

980E+6

980E+8

1E-2

2.5

1010E+6

1010E+8

1E-1

7.5

170E+6

170E+8

5E-1

11

39E+6

39E+8

1

11

27E+6

27E+8

2.5

9

29E+6

29E+8

5

8

23E+6

23E+8

7

7

24E+6

24E+8

10

6.5

24E+6

24E+8

14

7.5

17E+6

17E+8

20

8

16E+6

16E+8

40

7

14E+6

14E+8

60

5.5

16E+6

16E+8

1E+2

4

20E+6

20E+8

2E+2

3.5

19E+6

19E+8

3E+2

3.5

16E+6

16E+8

4E+2

3.5

14E+6

14E+8

aValue of quality factor (Q) at the point where the dose equivalent is maximum in a 30-centimeter diameter cylinder tissue -equivalent phantom.

bMonoenergetic neutrons incident normally on a 30-centimeter diameter cylinder tissue-equivalent phantom.

Unrefined and Unprocessed Ore-ore in its natural form prior to any processing, such as grinding, roasting, beneficiating, or refining. Processing does not include sieving or encapsulation of ore, or preparation of samples for laboratory analysis.

Unrestricted Area (an Uncontrolled Area) - an area, access to which is neither limited nor controlled by the licensee or registrant. For purposes of these regulations, uncontrolled area is an equivalent term.

U.S. Department of Energy- the Department of Energy established by Public Law 95-91, August 4, 1977, 91 Stat. 565, 42 U.S.C. 7101 et seq., to the extent that the Department 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 thereof pursuant to Section 104(b), (c), and (d) of the Energy Reorganization Act of 1974 (Public Law 93-438, October 11, 1974, 88 Stat. 1233 at 1237, effective January 19, 1975) and retransferred to the Secretary of Energy pursuant to Section 301(a) of the Department of Energy Organization Act (Public Law 95-91, August 4, 1977, 91 Stat. 565 at 577-578, 42 U.S.C. 7151, effective October 1, 1977).

Waste-those low-level radioactive wastes that are acceptable for disposal in a land disposal facility. For the purposes of this definition, low-level waste has the same meaning as in the Low-Level Radioactive Waste Policy Act, PL. 96-573, as amended by P.L. 99-240, effective January 15, 1986; that is, radioactive waste:

1. not classified as high-level radioactive waste, transuranic waste, spent nuclear fuel, or byproduct material as defined in section ll.e.(2) of the Atomic Energy Act (uranium or thorium tailings and waste) and Paragraphs 3, 4,and 5 in the definition of byproduct material of this Section; and

2. classified as low-level radioactive waste consistent with existing law and in accordance with Paragraph 1 above by the U.S. Nuclear Regulatory Commission.

Waste-Handling Licensees- persons licensed to receive and store radioactive wastes prior to disposal and/or persons licensed to dispose of radioactive waste.

Week- seven consecutive days starting on Sunday.

Whole Body- for purposes of external exposure, head, trunk, including male gonads, arms above the elbow, or legs above the knee.

Worker- an individual engaged in work under a license or registration issued by the department and controlled by a licensee or registrant, but not including the licensee or registrant.

Working Level (WL)- any combination of short-lived radon daughters (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) in one liter of air, without regard to the degree of equilibrium, that will result in the ultimate emission of 1.3 x 105 MeV of alpha particle energy.

Working-Level Month (WLM) - the occupational exposure incurred in one working month of 170 hours by individuals in an atmosphere containing radon daughter products; e.g., one working month in a mine atmosphere containing one working level of radon daughter products equals one WLM.

Written Directive- an order in writing for a specific patient or human research subject, dated and signed by an authorized user prior to the administration of a radiopharmaceutical or radiation, except as specified in Paragraph 6 of this definition, containing the following information:

1. for any administration of quantities greater than 30 microcuries of either sodium iodide L125 or 1-131: the dosage;

2. for a therapeutic administration of a radiopharmaceutical other than sodium iodide 1-125 or 1-131: the radiopharmaceutical, dosage, and route of administration;

3. for gamma stereotactic radiosurgery: target coordinates, collimator size, plug pattern, and total dose;

4. for teletherapy: the total dose, dose per fraction, treatment site, and overall treatment period;

5. for high-dose-rate remote afterloading brachytherapy: the radioisotope, treatment site, and total dose; or

6. for all other brachy therapy:
a. prior to implantation: the radioisotope, number of sources, and source strengths; and

b. after implantation but prior to completion of the procedure: the radioisotope, treatment site, and total source strength and exposure time (or, equivalently, the total dose).

Year- the period of time beginning in January used to determine compliance with the provisions of these regulations. 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.

AUTHORITY NOTE: Promulgated in accordance with R.S. 30:2001 et seq., and 2104.B.

Disclaimer: These regulations may not be the most recent version. Louisiana may have more current or accurate information. We make no warranties or guarantees about the accuracy, completeness, or adequacy of the information contained on this site or the information linked to on the state site. Please check official sources.
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