The following words and terms, when used in this chapter, shall
have the following meanings, or as described in Chapter 3 of this
title (relating to Definitions), unless the context clearly indicates
otherwise. Additional definitions used only in a certain subchapter
will be found in that subchapter.
(1) 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).
(2) Accelerator-produced radioactive material--Any
material made radioactive by a particle accelerator.
(3) Access control--A system for allowing only approved
individuals to have unescorted access to the security zone and for
ensuring that all other individuals are subject to escorted access.
(4) Activity--The rate of disintegration (transformation)
or decay of radioactive material. The units of activity are the curie
(Ci) and the becquerel (Bq).
(5) Adult--An individual 18 or more years of age.
(6) Aggregated--Accessible by the breach of a single
physical barrier that allows access to radioactive material in any
form, including any devices containing the radioactive material, when
the total activity equals or exceeds a category 2 quantity of radioactive
material.
(7) Agreement state--Any state with which the United
States Nuclear Regulatory Commission (NRC) or the Atomic Energy Commission
has entered into an effective agreement under the Atomic Energy Act
of 1954, §274b, as amended. Non-agreement State means any other
State.
(8) Airborne radioactive material--Any radioactive
material dispersed in the air in the form of dusts, fumes, particulates,
mists, vapors, or gases.
(9) Airborne radioactivity area--A room, enclosure,
or area in which airborne radioactive materials, composed wholly or
partly of licensed material, exist in concentrations:
(A) in excess of the derived air concentrations (DACs)
specified in Table I of §336.359(d) of this title (relating to
Appendix B. Annual Limits on Intake (ALI) and Derived Air Concentrations
(DAC) of Radionuclides for Occupational Exposure; Effluent Concentrations;
Concentrations for Release to Sanitary Sewerage); or
(B) to 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% of the
ALI or 12 DAC-hours.
(10) Air-purifying respirator--A respirator with an
air-purifying filter, cartridge, or canister that removes specific
air contaminants by passing ambient air through the air-purifying
element.
(11) Annual limit on intake (ALI)--The derived limit
for the amount of radioactive material taken into the body of an adult
worker by inhalation or ingestion in a year. ALI is the smaller value
of intake of a given radionuclide in a year by the "reference
man" that would result in a committed effective dose equivalent
of 5 rems (0.05 sievert) or a committed dose equivalent of 50 rems
(0.5 sievert) to any individual organ or tissue. ALI values for intake
by ingestion and by inhalation of selected radionuclides are given
in Table I, Columns 1 and 2 of §336.359(d) of this title (relating
to Appendix B. Annual Limits on Intake (ALI) and Derived Air Concentrations
(DAC) of Radionuclides for Occupational Exposure; Effluent Concentrations;
Concentrations for Release to Sanitary Sewerage).
(12) Approved individual--An individual whom the licensee
has determined to be trustworthy and reliable for unescorted access
in accordance with §336.357(b) - (h) of this title (relating
to Physical Protection of Category 1 and Category 2 Quantities of
Radioactive Material) and who has completed the training required
by §336.357(j)(3) of this title.
(13) As low as is reasonably achievable--Making every
reasonable effort to maintain exposures to radiation as far below
the dose limits in this chapter as is practical, consistent with the
purpose for which the licensed activity is undertaken, taking into
account the state of technology, the economics of improvements in
relation to the 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 ionizing radiation and licensed radioactive materials in the public
interest.
(14) Assigned protection factor (APF)--The expected
workplace level of respiratory protection that would be provided by
a properly functioning respirator or a class of respirators to properly
fitted and trained users. Operationally, the inhaled concentration
can be estimated by dividing the ambient airborne concentration by
the APF.
(15) Atmosphere-supplying respirator--A respirator
that supplies the respirator user with breathing air from a source
independent of the ambient atmosphere, and includes supplied-air respirators
and self-contained breathing apparatus units.
(16) Background investigation--The investigation conducted
by a licensee or applicant to support the determination of trustworthiness
and reliability.
(17) Background radiation--Radiation from cosmic sources;
non-technologically enhanced naturally-occurring radioactive material,
including radon (except as a decay product of source or special nuclear
material) and global fallout as it exists in the environment from
the testing of nuclear explosive devices or from past nuclear accidents
such as Chernobyl that contribute to background radiation and are
not under the control of the licensee. "Background radiation"
does not include radiation from radioactive materials regulated by
the commission, Texas Department of State Health Services, United
States Nuclear Regulatory Commission, or an Agreement State.
(18) Becquerel (Bq)--See §336.4 of this title
(relating to Units of Radioactivity).
(19) 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 the rules in this chapter, "radiobioassay"
is an equivalent term.
(20) Byproduct material--
(A) a radioactive material, other than special nuclear
material, that is produced in or made radioactive by exposure to radiation
incident to the process of producing or using special nuclear material;
(B) the tailings or wastes produced by or resulting
from the extraction or concentration of uranium or thorium from ore
processed primarily for its source material content, including discrete
surface wastes resulting from uranium solution extraction processes,
and other tailings having similar radiological characteristics. Underground
ore bodies depleted by these solution extraction processes do not
constitute "byproduct material" within this definition;
(C) any discrete source of radium-226 that is produced,
extracted, or converted after extraction, for use for a commercial,
medical, or research activity;
(D) any material that has been made radioactive by
use of a particle accelerator, and is produced, extracted, or converted
for use for a commercial, medical, or research activity; and
(E) any discrete source of naturally occurring radioactive
material, other than source material, that is extracted or converted
after extraction for use in a commercial, medical, or research activity
and that the United States Nuclear Regulatory Commission, in consultation
with the Administrator of the United States Environmental Protection
Agency, the United States Secretary of Energy, the United States 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.
(21) CFR--Code of Federal Regulations.
(22) Carrier--A person engaged in the transportation
of passengers or property by land or water as a common, contract,
or private carrier, or by civil aircraft.
(23) Category 1 quantity of radioactive material--A
quantity of radioactive material meeting or exceeding the category
1 threshold in accordance with §336.357(z) of this title (relating
to Physical Protection of Category 1 and Category 2 Quantities of
Radioactive Material). This is determined by calculating the ratio
of the total activity of each radionuclide to the category 1 threshold
for that radionuclide and adding the ratios together. If the sum is
equal to or exceeds 1, the quantity would be considered a category
1 quantity. Category 1 quantities of radioactive material do not include
the radioactive material contained in any fuel assembly, subassembly,
fuel rod, or fuel pellet.
(24) Category 2 quantity of radioactive material--A
quantity of radioactive material meeting or exceeding the category
2 threshold but less than the category 1 threshold in accordance with §336.357(z)
of this title (relating to Physical Protection of Category 1 and Category
2 Quantities of Radioactive Material). This is determined by calculating
the ratio of the total activity of each radionuclide to the category
2 threshold for that radionuclide and adding the ratios together.
If the sum is equal to or exceeds 1, the quantity would be considered
a category 2. Category 2 quantities of radioactive material do not
include the radioactive material contained in any fuel assembly, subassembly,
fuel rod, or fuel pellet.
(25) Class--A classification scheme for inhaled material
according to its rate of clearance from the pulmonary region of the
lung. Materials are classified as D, W, or Y, which applies to a range
of clearance half-times: for Class D (Days) of less than ten days,
for Class W (Weeks) from 10 to 100 days, and for Class Y (Years) of
greater than 100 days. For purposes of the rules in this chapter, "lung
class" and "inhalation class" are equivalent terms.
(26) 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.
(27) Committed dose equivalent (HT , 50 ) (CDE)--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.
(28) Committed effective dose equivalent (HE ,50 ) (CEDE)--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.
(29) Compact--The Texas Low-Level Radioactive Waste
Disposal Compact established under Texas Health and Safety Code, §403.006
and Texas Low-Level Radioactive Waste Disposal Compact Consent Act,
Public Law Number 105-236 (1998).
(30) Compact waste--Low-level radioactive waste that:
(A) is generated in a host state or a party state;
or
(B) is not generated in a host state or a party state,
but has been approved for importation to this state by the compact
commission under §3.05 of the compact established under Texas
Health and Safety Code, §403.006.
(31) Compact waste disposal facility--The low-level
radioactive waste land disposal facility licensed by the commission
under Subchapter H of this chapter (relating to Licensing Requirements
for Near-Surface Land Disposal of Low-Level Radioactive Waste) for
the disposal of compact waste.
(32) Constraint (dose constraint)--A value above which
specified licensee actions are required.
(33) Critical group--The group of individuals reasonably
expected to receive the greatest exposure to residual radioactivity
for any applicable set of circumstances.
(34) Curie (Ci)--See §336.4 of this title (relating
to Units of Radioactivity).
(35) Declared pregnant woman--A woman who has voluntarily
informed the licensee, in writing, of her pregnancy and the estimated
date of conception. The declaration remains in effect until the declared
pregnant woman withdraws the declaration in writing or is no longer
pregnant.
(36) Decommission--To remove (as a facility) safely
from service and reduce residual radioactivity to a level that permits:
(A) release of the property for unrestricted use and
termination of license; or
(B) release of the property under restricted conditions
and termination of the license.
(37) Deep-dose equivalent (Hd )
(which applies to external whole-body exposure)--The dose equivalent
at a tissue depth of one centimeter (1,000 milligrams/square centimeter).
(38) Demand respirator--An atmosphere-supplying respirator
that admits breathing air to the facepiece only when a negative pressure
is created inside the facepiece by inhalation.
(39) Depleted uranium--The source material uranium
in which the isotope uranium-235 is less than 0.711%, by weight, of
the total uranium present. Depleted uranium does not include special
nuclear material.
Cont'd... |
