| personal air sampling devices.
(58) Inspection--An official examination and/or observation
including, but not limited to, records, tests, surveys, and monitoring
to determine compliance with the Act and rules, orders, requirements,
and conditions of the agency.
(59) Internal dose--That portion of the dose equivalent
received from radioactive material taken into the body.
(60) Ionizing radiation--Any electromagnetic or particulate
radiation capable of producing ions, directly or indirectly, in its
passage through matter. Ionizing radiation includes gamma rays and
x rays, alpha and beta particles, high-speed electrons, neutrons,
and other nuclear particles.
(61) Land disposal facility--The land, buildings, and
equipment that are intended to be used for the disposal of low-level
radioactive waste (LLRW) into the subsurface of the land.
(62) Lens dose equivalent--The external dose equivalent
to the lens of the eye at a tissue depth of 0.3 cm (300 mg/cm2 ).
(63) License--A form of permission given by the agency
to an applicant who has met the requirements for licensing set out
in the Act and this chapter.
(64) Licensed material--Radioactive material received,
possessed, used, or transferred under a general or specific license
issued by the agency.
(65) Licensee--Any person who is licensed by the agency
in accordance with the Act and this chapter.
(66) 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 has been designated as such by the Conference of Radiation Control
Program Directors, Inc. For the purposes of evaluation and/or distribution
of sealed sources, this includes Licensing State Status: Product Review
Only.
(67) Local law enforcement agency (LLEA)--A public
or private organization that has been approved by a federal, state,
or local government to carry firearms and 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.
(68) Lost or missing radioactive material--Radioactive
material whose location is unknown. This definition includes licensed
material that has been shipped but has not reached its planned destination
and whose location cannot be readily traced in the transportation
system.
(69) Low-level radioactive waste (LLRW)--Radioactive
material that meets the following criteria:
(A) LLRW is radioactive material that is:
(i) discarded or unwanted and is not exempt by rule
adopted under the Texas Radiation Control Act (Act), HSC, §401.106;
(ii) waste, as that term is defined in Title 10, CFR, §61.2;
and
(iii) subject to:
(I) concentration limits established in Title 10, CFR, §61.55,
or compatible rules adopted by the agency or the Texas Commission
on Environmental Quality (TCEQ), as applicable; and
(II) disposal criteria established in Title 10, CFR,
or established by the agency or TCEQ, as applicable.
(B) LLRW does not include:
(i) high-level radioactive waste as defined by Title
10, CFR, §60.2;
(ii) spent nuclear fuel as defined by Title 10, CFR, §72.3;
(iii) byproduct material defined in the Act, HSC, §401.003(3)(B);
(iv) naturally occurring radioactive material (NORM)
waste that is not oil and gas NORM waste;
(v) oil and gas NORM waste; or
(vi) transuranics greater than 100 nanocuries per gram.
(70) Manufacture--To fabricate or mechanically produce.
(71) Member of the public--Any individual, except when
that individual is receiving an occupational dose.
(72) Minor--An individual less than 18 years of age.
(73) Mobile device--A piece of equipment containing
licensed radioactive material that either is mounted on a permanent
base with wheels and/or casters, or otherwise equipped for moving
while completely assembled and without dismounting; or is a portable
device. Mobile devices do not include stationary equipment installed
in a fixed location.
(74) 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 this chapter,
"radiation monitoring" and "radiation protection monitoring" are equivalent
terms.
(75) Movement control center--An operations center
that is remote from transport activity and that maintains position
information on the movement of radioactive material, receives reports
of attempted attacks or thefts, provides a means for reporting these
and other problems to appropriate agencies and can request and coordinate
appropriate aid.
(76) NARM--Any naturally occurring or accelerator-produced
radioactive material except source material or special nuclear material.
(77) Natural radioactivity--Radioactivity of naturally
occurring nuclides whose location and chemical and physical form have
not been altered by man.
(78) No-later-than arrival time--The date and time
that the shipping licensee and receiving licensee have established
as the time at which an investigation will be initiated if the shipment
has not arrived at the receiving facility. The no-later-than arrival
time may not be more than 6 hours after the estimated arrival time
for shipments of category 2 quantities of radioactive material.
(79) NRC--The United States Nuclear Regulatory Commission
or its duly authorized representatives.
(80) Occupational dose--The dose received by an individual
in the course of employment in which the individual's assigned duties
involve exposure to sources of radiation from licensed/registered
and unlicensed/unregistered 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
this chapter, from voluntary participation in medical research programs,
or as a member of the public.
(81) Particle accelerator--Any machine capable of accelerating
electrons, protons, deuterons, or other charged particles in a vacuum
and designed to discharge the resultant particulate or other associated
radiation at energies usually in excess of 1 million electron volts
(MeV).
(82) Person--Any individual, corporation, partnership,
firm, association, trust, estate, public or private institution, group,
agency, local government, any other state or political subdivision
or agency thereof, or any other legal entity, and any legal successor,
representative, agent, or agency of the foregoing, other than NRC,
and other than federal government agencies licensed or exempted by
NRC.
(83) Personnel monitoring equipment (See definition
for individual monitoring devices.)
(84) Pharmacist--An individual licensed by the Texas
State Board of Pharmacy to compound and dispense drugs, prescriptions,
and poisons.
(85) Physician--An individual licensed by the Texas
Medical Board.
(86) Portable device--A piece of equipment containing
licensed radioactive material that is designed by the manufacturer
to be hand carried during use.
(87) Positron emission tomography (PET) radionuclide
production facility--A facility operating a cyclotron or accelerator
for the purpose of producing PET radionuclides.
(88) 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.
(89) Public dose--The dose received by a member of
the public from exposure to sources of radiation released by a licensee,
or to any other source of radiation under the control of a licensee/registrant.
It does not include occupational dose or doses received from background
radiation, from any medical administration the individual has received,
from exposure to individuals administered radioactive material and
released in accordance with this chapter, or from voluntary participation
in medical research programs.
(90) Quality factor (Q)--The modifying factor listed
in subsection (n)(1) and (2) of this section that is used to derive
dose equivalent from absorbed dose.
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