| (107) Residual radioactivity--The 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 Title 10, CFR, Part 20.
(108) Restricted area--An area, access to which is
limited by the licensee for the purpose of protecting individuals
against undue risks from exposure to sources of radiation. 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.
(109) Reviewing official--The individual who shall
make the trustworthiness and reliability determination of an individual
to determine whether the individual may have, or continue to have,
unescorted access to the category 1 or category 2 quantities of radioactive
materials that are possessed by the licensee.
(110) Roentgen (R)--The special unit of exposure. One
roentgen (R) equals 2.58 x 10-4 C/kg
of air. (See definition for exposure.)
(111) Rule (as defined in the Government Code, Chapters
2001 and 2002, as amended)--Any agency statement of general applicability
that implements, interprets, or prescribes law or policy, or describes
the procedure or practice requirements of an agency. The term includes
the amendment or repeal of a prior section but does not include statements
concerning only the internal management or organization of any agency
and not affecting private rights or procedures. The word "rule" was
formerly referred to as "regulation."
(112) Sabotage--The deliberate damage, with malevolent
intent, to a category 1 or category 2 quantity of radioactive material,
a device that contains a category 1 or category 2 quantity of radioactive
material, or the components of the security system.
(113) Safe haven--A readily recognizable and readily
accessible site at which security is present or from which, in the
event of an emergency, the transport crew can notify and wait for
the local law enforcement authorities.
(114) 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.
(115) Security zone--Any temporary or permanent area
determined and established by the licensee for the physical protection
of category 1 or category 2 quantities of radioactive material.
(116) Shallow dose equivalent (Hs )
(that 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 cm (7 mg/cm2 ).
(117) SI--The abbreviation for the International System
of Units.
(118) Sievert--The SI unit of any of the quantities
expressed as dose equivalent. The dose equivalent in sievert is equal
to the absorbed dose in gray multiplied by the quality factor (1 Sv
= 100 rem).
(119) Site boundary--That line beyond which the land
or property is not owned, leased, or otherwise controlled by the licensee.
(120) Source material--Source material is defined as:
(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; and
(C) does not include special nuclear material.
(121) Source of radiation--Any radioactive material,
or any device or equipment emitting or capable of producing radiation.
(122) Special form radioactive material--Radioactive
material that satisfies the following conditions.
(A) It is either a single solid piece or is contained
in a sealed capsule that can be opened only by destroying the capsule;
(B) The piece or capsule has at least one dimension
not less than 5 millimeters (mm) (0.2 inch); and
(C) It satisfies the requirements specified by NRC.
A special form encapsulation designed in accordance with NRC requirements
in effect on June 30, 1983, and constructed prior to July 1, 1985,
may continue to be used. A special form encapsulation designed in
accordance with NRC requirements in effect on March 31, 1996, and
constructed prior to April 1, 1998, may continue to be used. A special
form encapsulation either designed or constructed after April 1, 1998,
must meet the requirements of this definition applicable at the time
of its design or construction.
(123) Special nuclear material--Special nuclear material
is defined as:
(A) plutonium (Pu), uranium-233 (U-233), uranium enriched
in the isotope 233 or in the isotope 235, and any other material that
NRC, in accordance with the provisions of the Atomic Energy Act of
1954, §51 as amended, determines to be special nuclear material,
but does not include source material; or
(B) any material artificially enriched by any of the
foregoing, but does not include source material.
(124) Special nuclear material in quantities not sufficient
to form a critical mass--Uranium enriched in the isotope 235 in quantities
not exceeding 350 grams (g) of contained uranium-235; uranium-233
in quantities not exceeding 200 g; plutonium in quantities not exceeding
200 g; or any combination of them in accordance with the following
formula.
(A) 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).
(B) For example, the following quantities in combination
would not exceed the limitation and are within the formula:
Attached Graphic
(125) Special units--The conventional units historically
used by licensees, for example, curie (activity), rad (absorbed dose),
and rem (dose equivalent).
(126) Stationary device--A piece of equipment containing
licensed radioactive material that is installed in a fixed location.
(127) Survey--An evaluation of the radiological conditions
and potential hazards incident to the production, use, transfer, release,
disposal, and/or presence of sources of radiation. When appropriate,
such survey includes, but is not limited to, tests, physical examination
of location of materials and equipment, measurements of levels of
radiation or concentration of radioactive material present, and evaluation
of administrative and/or engineered controls.
(128) Telemetric position monitoring system--A data
transfer system that captures information by instrumentation and/or
measuring devices about the location and status of a transport vehicle
or package between the departure and destination locations.
(129) Termination--A release by the agency 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.
(130) Test--A method of determining the characteristics
or condition of sources of radiation or components thereof.
(131) Texas Regulations for Control of Radiation (TRCR)--All
sections of Title 25, TAC, Chapter 289.
(132) Total effective dose equivalent (TEDE)--The sum
of the effective dose equivalent for external exposures and the committed
effective dose equivalent for internal exposures.
(133) 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 §289.202(rr)(1)(F)
of this title.
(134) Transport index--The dimensionless number (rounded
up to the next tenth) placed on the label of a package, to designate
the degree of control to be exercised by the carrier during transportation.
The transport index is determined as follows:
(A) For non-fissile material packages, the number determined
by multiplying the maximum radiation level in millisievert per hour
(mSv/hr) at 1 meter (m) (3.3 feet) from the external surface of the
package by 100 (equivalent to the maximum radiation level in millirem
per hour (mrem/hr) at 1 m (3.3 feet); or
(B) For fissile material packages, the number determined
by multiplying the maximum radiation level in mSv/hr at 1 m (3.3 feet)
from the external surface of the package by 100 (equivalent to the
maximum radiation level in mrem/hr at 1 m (3.3 feet), or, for criticality
control purposes, the number obtained as described in Title 10, CFR, §71.59
whichever is larger.
Cont'd... |
