| (40) Derived air concentration (DAC)--The concentration
of a given radionuclide in air which, if breathed by the "reference
man" for a working year of 2,000 hours under conditions of light
work (inhalation rate of 1.2 cubic meters of air/hour), results in
an intake of one ALI. DAC values are given in Table I, Column 3, 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
(41) Derived air concentration-hour (DAC-hour)--The
product of the concentration of radioactive material in air (expressed
as a fraction or multiple of the derived air concentration for each
radionuclide) and the time of exposure to that radionuclide, in hours.
A licensee shall take 2,000 DAC-hours to represent one, equivalent
to a committed effective dose equivalent of 5 rems (0.05 sievert).
(42) 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.
(43) Disposal--With regard to low-level radioactive
waste, the isolation or removal of low-level radioactive waste from
mankind and mankind's environment without intent to retrieve that
low-level radioactive waste later.
(44) Disposable respirator--A respirator for which
maintenance is not intended and that is designed to be discarded after
excessive breathing resistance, sorbent exhaustion, physical damage,
or end-of-service-life renders it unsuitable for use. Examples of
this type of respirator are a disposable half-mask respirator or a
disposable escape-only Self-Contained breathing apparatus.
(45) Distinguishable from background--The detectable
concentration of a radionuclide 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.
(46) Diversion--The unauthorized movement of radioactive
material subject to §336.357 of this title (relating to Physical
Protection of Category 1 and Category 2 Quantities of Radioactive
Material) to a location different from the material's authorized destination
inside or outside of the site at which the material is used or stored.
(47) 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 the rules in this
chapter, "radiation dose" is an equivalent term.
(48) 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 rem and sievert (Sv ).
(49) Dose limits--The permissible upper bounds of radiation
doses established in accordance with the rules in this chapter. For
purposes of the rules in this chapter, "limits" is an equivalent
(50) Dosimetry processor--An individual or organization
that processes and evaluates individual monitoring devices in order
to determine the radiation dose delivered to the monitoring devices.
(51) 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.
(52) Embryo/fetus--The developing human organism from
conception until the time of birth.
(53) Entrance or access point--Any opening through
which an individual or extremity of an individual could gain access
to radiation areas or to licensed radioactive materials. This includes
portals of sufficient size to permit human access, irrespective of
their intended use.
(54) Environmental Radiation and Perpetual Care Account--An
account in the general revenue fund established for the purposes specified
in the Texas Health and Safety Code, §401.306.
(55) Escorted access--Accompaniment while in a security
zone by an approved individual who maintains continuous direct visual
surveillance at all times over an individual who is not approved for
(56) Exposure--Being exposed to ionizing radiation
or to radioactive material.
(57) Exposure rate--The exposure per unit of time.
(58) External dose--That portion of the dose equivalent
received from any source of radiation outside the body.
(59) Extremity--Hand, elbow, arm below the elbow, foot,
knee, and leg below the knee. The arm above the elbow and the leg
above the knee are considered part of the whole body.
(60) Federal facility waste--Low-level radioactive
waste that is the responsibility of the federal government under the
Low-Level Radioactive Waste Policy Act, as amended by the Low-Level
Radioactive Waste Policy Amendments Act of 1985 (42 United States
Code, §2021b - 2021j). Excluded from this definition is low-level
radioactive waste that is classified as greater than Class C in §336.362
of this title (relating to Appendix E. Classification and Characteristics
of Low-Level Radioactive Waste).
(61) Federal facility waste disposal facility--A low-level
radioactive waste land disposal facility for the disposal of federal
facility waste licensed under Subchapters H and J of this chapter
(relating to Licensing Requirements for Near-Surface Land Disposal
of Low-Level Radioactive Waste, and Federal Facility Waste Disposal
(62) Filtering facepiece (dust mask)--A negative pressure
particulate respirator with a filter as an integral part of the facepiece
or with the entire facepiece composed of the filtering medium, not
equipped with elastomeric sealing surfaces and adjustable straps.
(63) Fingerprint Orders--Orders issued by the Nuclear
Regulatory Commission or the legally binding requirements issued by
Agreement States that require fingerprints and criminal history records
checks for individuals with unescorted access to category 1 and category
2 quantities of radioactive material or safeguards information-modified
(64) Fit factor--A quantitative estimate of the fit
of a particular respirator to a specific individual, and typically
estimates the ratio of the concentration of a substance in ambient
air to its concentration inside the respirator when worn.
(65) Fit test--The use of a protocol to qualitatively
or quantitatively evaluate the fit of a respirator on an individual.
(66) General license--An authorization granted by an
agency under its rules which is effective without the filing of an
application with that agency or the issuance of a licensing document
to the particular person.
(67) Generally applicable environmental radiation standards--Standards
issued by the EPA under the authority of the Atomic Energy Act of
1954, as amended through October 4, 1996, 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.
(68) Gray (Gy)--See §336.3 of this title (relating
to Units of Radiation Exposure and Dose).
(69) Hazardous waste--Hazardous waste as defined in §335.1
of this title (relating to Definitions).
(70) Helmet--A rigid respiratory inlet covering that
also provides head protection against impact and penetration.
(71) 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 0.1 rem (1 millisievert) in one hour at 30 centimeters from the
radiation source or 30 centimeters from any surface that the radiation
(72) Hood--A respiratory inlet covering that completely
covers the head and neck and may also cover portions of the shoulders
(73) Host state--A party state in which a compact facility
is located or is being developed. The state of Texas is the host state
under the Texas Low-Level Radioactive Waste Disposal Compact, §2.01,
established under Texas Health and Safety Code, §403.006.
(74) Individual--Any human being.
(75) Individual monitoring--The assessment of:
(A) dose equivalent by the use of individual monitoring
(B) committed effective dose equivalent by bioassay
or by determination of the time-weighted air concentrations to which
an individual has been exposed, that is, derived air concentration-hour;
(C) dose equivalent by the use of survey data.
(76) Individual monitoring devices--Devices designed
to be worn by a single individual for the assessment of dose equivalent
such as film badges, thermoluminescence dosimeters, pocket ionization
chambers, and personal ("lapel") air sampling devices.
(77) Inhalation class--See "Class."
(78) Inspection--An official examination and/or observation
including, but not limited to, records, tests, surveys, and monitoring
to determine compliance with the Texas Radiation Control Act and rules,
orders, and license conditions of the commission.
(79) Internal dose--That portion of the dose equivalent
received from radioactive material taken into the body.
(80) Land disposal facility--The land, buildings and
structures, and equipment which are intended to be used for the disposal
of low-level radioactive wastes into the subsurface of the land. For
purposes of this chapter, a "geologic repository" as defined
in 10 Code of Federal Regulations §60.2 as amended through October
27, 1988 (53 FR 43421) (relating to Definitions - high-level radioactive
wastes in geologic repositories) is not considered a "land disposal
(81) Lens dose equivalent (LDE)--The external exposure
of the lens of the eye and is taken as the dose equivalent at a tissue
depth of 0.3 centimeter (300 mg/cm2 ).
(82) License--See "Specific license."
(83) Licensed material--Radioactive material received,
possessed, used, processed, transferred, or disposed of under a license
issued by the commission.
(84) Licensee--Any person who holds a license issued
by the commission in accordance with the Texas Health and Safety Code,
Chapter 401 (Radioactive Materials and Other Sources of Radiation)
and the rules in this chapter. For purposes of the rules in this chapter, "radioactive
material licensee" is an equivalent term. Unless stated otherwise, "licensee"
as used in the rules of this chapter means the holder of a "specific
(85) Licensing state--Any state with rules equivalent
to the Suggested State Regulations for Control of Radiation relating
to, and having an effective program for, the regulatory control of
naturally occurring or accelerator-produced radioactive material (NARM)
and which has been designated as such by the Conference of Radiation
Control Program Directors, Inc.
(86) Local law enforcement agency (LLEA)--A public
or private organization that has been approved by a federal, state,
or local government to carry firearms; make arrests; and is authorized
and has the capability to provide an armed response in the jurisdiction
where the licensed category 1 or category 2 quantity of radioactive
material is used, stored, or transported.
(87) Loose-fitting facepiece--A respiratory inlet covering
that is designed to form a partial seal with the face.
(88) Lost or missing licensed radioactive material--Licensed
material whose location is unknown. This definition includes material
that has been shipped but has not reached its planned destination
and whose location cannot be readily traced in the transportation
(89) Low-level radioactive waste--
(A) Except as provided by subparagraph (B) of this
paragraph, low-level radioactive waste means radioactive material
(i) is discarded or unwanted and is not exempt by a
Texas Department of State Health Services rule adopted under the Texas
Health and Safety Code, §401.106;
(ii) is waste, as that term is defined by 10 Code of
Federal Regulations (CFR) §61.2; and
(iii) is subject to:
(I) concentration limits established under this chapter;
(II) disposal criteria established under this chapter.
(B) Low-level radioactive waste does not include:
(i) high-level radioactive waste defined by 10 CFR §60.2;
(ii) spent nuclear fuel as defined by 10 CFR §72.3;
(iii) transuranic waste as defined in this section;
(iv) byproduct material as defined by paragraph (20)(B)
- (E) of this section;
(v) naturally occurring radioactive material (NORM)