| (96) Planned special exposure--An infrequent exposure
to radiation, separate from and in addition to the annual occupational
(97) Positive pressure respirator--A respirator in
which the pressure inside the respiratory inlet covering exceeds the
ambient air pressure outside the respirator.
(98) Powered air-purifying respirator (PAPR)--An air-purifying
respirator that uses a blower to force the ambient air through air-purifying
elements to the inlet covering.
(99) Pressure demand respirator--A positive pressure
atmosphere-supplying respirator that admits breathing air to the facepiece
when the positive pressure is reduced inside the facepiece by inhalation.
(100) Principal activities--Activities authorized by
the license which are essential to achieving the purpose(s) for which
the license is 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.
(101) Public dose--The dose received by a member of
the public from exposure to radiation and/or radioactive material
released by a licensee, or to any other source of radiation under
the control of the licensee. It does not include occupational dose
or doses received from background radiation, as a patient from medical
practices, or from voluntary participation in medical research programs.
(102) Qualitative fit test (QLFT)--A pass/fail test
to assess the adequacy of respirator fit that relies on the individual's
response to the test agent.
(103) Quality factor (Q)--The modifying factor listed
in Table I or II of §336.3 of this title that is used to derive
dose equivalent from absorbed dose.
(104) Quantitative fit test (QNFT)--An assessment of
the adequacy of respirator fit by numerically measuring the amount
of leakage into the respirator.
(105) Quarter (Calendar quarter)--A period of time
equal to one-fourth of the year observed by the licensee (approximately
13 consecutive weeks), providing that the beginning of the first quarter
in a year coincides with the starting date of the year and that no
day is omitted or duplicated in consecutive quarters.
(106) Rad--See §336.3 of this title.
(107) Radiation--Alpha particles, beta particles, gamma
rays, x-rays, neutrons, high-speed electrons, high-speed protons,
and other particles capable of producing ions. For purposes of the
rules in this chapter, "ionizing radiation" is an equivalent term.
Radiation, as used in this chapter, does not include non-ionizing
radiation, such as radio- or microwaves or visible, infrared, or ultraviolet
(108) Radiation and Perpetual Care Account--An account
in the general revenue fund established for the purposes specified
in the Texas Health and Safety Code, §401.305.
(109) Radiation area--Any area, accessible to individuals,
in which radiation levels could result in an individual receiving
a dose equivalent in excess of 0.005 rem (0.05 millisievert) in one
hour at 30 centimeters from the source of radiation or from any surface
that the radiation penetrates.
(110) Radiation machine--Any device capable of producing
ionizing radiation except those devices with radioactive material
as the only source of radiation.
(111) Radioactive material--A naturally-occurring or
artificially-produced solid, liquid, or gas that emits radiation spontaneously.
(112) Radioactive substance--Includes byproduct material,
radioactive material, low-level radioactive waste, source material,
special nuclear material, source of radiation, and NORM waste, excluding
oil and gas NORM waste.
(113) Radioactivity--The disintegration of unstable
atomic nuclei with the emission of radiation.
(114) Radiobioassay--See "Bioassay."
(115) Reference man--A hypothetical aggregation of
human physical and physiological characteristics determined by international
consensus. These characteristics shall be used by researchers and
public health workers to standardize results of experiments and to
relate biological insult to a common base. A description of "reference
man" is contained in the International Commission on Radiological
Protection report, ICRP Publication 23, "Report of the Task Group
on Reference Man."
(116) Rem--See §336.3 of this title.
(117) 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 10 CFR Part 20.
(118) Respiratory protection equipment--An apparatus,
such as a respirator, used to reduce an individual's intake of airborne
radioactive materials. For purposes of the rules in this chapter,
"respiratory protective device" is an equivalent term.
(119) Restricted area--An area, access to which is
limited by the licensee for the purpose of protecting individuals
against undue risks from exposure to radiation and radioactive materials.
Restricted area does not include areas used as residential quarters,
but separate rooms in a residential building shall be set apart as
a restricted area.
(120) Roentgen (R)--See §336.3 of this title.
(121) Sanitary sewerage--A system of public sewers
for carrying off waste water and refuse, but excluding sewage treatment
facilities, septic tanks, and leach fields owned or operated by the
(122) Sealed source--Radioactive material that is permanently
bonded or fixed in a capsule or matrix designed to prevent release
and dispersal of the radioactive material under the most severe conditions
that are likely to be encountered in normal use and handling.
(123) Self-contained breathing apparatus (SCBA)--An
atmosphere-supplying respirator for which the breathing air source
is designed to be carried by the user.
(124) Shallow-dose equivalent (Hs )
(which applies to the external exposure of the skin of the whole body
or the skin of an extremity)--The dose equivalent at a tissue depth
of 0.007 centimeter (seven milligrams/square centimeter).
(125) SI--The abbreviation for the International System
(126) Sievert (Sv)--See §336.3 of this title.
(127) Site boundary--That line beyond which the land
or property is not owned, leased, or otherwise controlled by the licensee.
(128) Source material--
(A) Uranium or thorium, or any combination thereof,
in any physical or chemical form; or
(B) ores that contain, by weight, 0.05% or more of
uranium, thorium, or any combination thereof. Source material does
not include special nuclear material.
(129) Special form radioactive material--Radioactive
material which is either a single solid piece or is contained in a
sealed capsule that can be opened only by destroying the capsule and
which has at least one dimension not less than five millimeters and
which satisfies the test requirements of 10 CFR §71.75 as amended
through September 28, 1995 (60 FR 50264) (Transportation of License
(130) Special nuclear material--
(A) Plutonium, uranium-233, uranium enriched in the
isotope 233 or in the isotope 235, and any other material that the
NRC, under the provisions of the Atomic Energy Act of 1954, §51,
as amended through November 2, 1994 (Public Law 103-437), determines
to be special nuclear material, but does not include source material;
(B) any material artificially enriched by any of the
foregoing, but does not include source material.
(131) Special nuclear material in quantities not sufficient
to form a critical mass--Uranium enriched in the isotope 235 in quantities
not exceeding 350 grams of contained uranium-235; uranium-233 in quantities
not exceeding 200 grams; plutonium in quantities not exceeding 200
grams; or any combination of these 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. For example, the following quantities
in combination would not exceed the limitation: (175 grams contained
U-235/350 grams) + (50 grams U-233/200 grams) + (50 grams Pu/200 grams)
(132) Specific license--A licensing document issued
by an agency upon an application filed under its rules. For purposes
of the rules in this chapter, "radioactive material license" is an
equivalent term. Unless stated otherwise, "license" as used in this
chapter means a "specific license."
(133) State--The State of Texas.
(134) Stochastic effect--A health effect that occurs
randomly and for which the probability of the effect occurring, rather
than its severity, is assumed to be a linear function of dose without
threshold. Hereditary effects and cancer incidence are examples of
stochastic effects. For purposes of the rules in this chapter, "probabilistic
effect" is an equivalent term.
(135) Supplied-air respirator (SAR) or airline respirator--An
atmosphere-supplying respirator for which the source of breathing
air is not designed to be carried by the user.
(136) Survey--An evaluation of the radiological conditions
and potential hazards incident to the production, use, transfer, release,
disposal, and/or presence of radioactive materials or other sources
of radiation. When appropriate, this evaluation includes, but is not
limited to, physical examination of the location of radioactive material
and measurements or calculations of levels of radiation or concentrations
or quantities of radioactive material present.
(137) Termination--As applied to a license, a release
by the commission of the obligations and authorizations of the licensee
under the terms of the license. It does not relieve a person of duties
and responsibilities imposed by law.
(138) Tight-fitting facepiece--A respiratory inlet
covering that forms a complete seal with the face.
(139) Total effective dose equivalent (TEDE)--The sum
of the effective dose equivalent for external exposures and the committed
effective dose equivalent for internal exposures.
(140) Total organ dose equivalent (TODE)--The sum of
the deep-dose equivalent and the committed dose equivalent to the
organ receiving the highest dose as described in §336.346(a)(6)
of this title (relating to Records of Individual Monitoring Results).
(141) Transuranic waste--For the purposes of this chapter,
wastes containing alpha emitting transuranic radionuclides with a
half-life greater than five years at concentrations greater than 100
(142) Type A quantity (for packaging)--A quantity of
radioactive material, the aggregate radioactivity of which does not
exceed A 1 for special form radioactive
material or A2 for normal form radioactive
material, where A1 and A2 are given in or shall be determined by procedures
in Appendix A to 10 CFR Part 71 as amended through September 28, 1995
(60 FR 50264) (Packaging and Transportation of Radioactive Material).
(143) Type B quantity (for packaging)--A quantity of
radioactive material greater than a Type A quantity.
(144) Unrefined and unprocessed ore--Ore in its natural
form before any processing, such as grinding, roasting, beneficiating,
(145) Unrestricted area--Any area that is not a restricted
(146) User seal check (fit check)--An action conducted
by the respirator user to determine if the respirator is properly
seated to the face. Examples include negative pressure check, positive
pressure check, irritant smoke check, or isoamyl acetate check.
(147) Very 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 an absorbed dose
in excess of 500 rads (five grays) in one hour at one meter from a
source of radiation or one meter from any surface that the radiation
(148) Violation--An infringement of any provision of
the Texas Radiation Control Act (TRCA) or of any rule, order, or license
condition of the commission issued under the TRCA or this chapter.
(149) Waste--Low-level radioactive wastes containing
source, special nuclear, or byproduct material that are acceptable
for disposal in a land disposal facility. For the purposes of this
definition, low-level radioactive waste means radioactive waste not
classified as high-level radioactive waste, transuranic waste, spent
nuclear fuel, or byproduct material as defined in paragraph (16)(B)
- (E) of this section.
(150) Week--Seven consecutive days starting on Sunday.