As used in these regulations, these terms have the
definitions set forth below. Additional definitions used only in a certain
section will be found in that section.
1. "A1" means the maximum activity of special
form radioactive material permitted in a Type A package. "A2" means the maximum
activity of radioactive material, other than special form, LSA and SCO
material, permitted in a Type A package. These values are either listed in
Appendix A, Table A-1 of Subchapter 13 of these regulations or may be derived
in accordance with the procedure prescribed in Appendix A of Subchapter 13 of
these regulations.
2. "Absorbed
dose" means the energy imparted to matter by ionizing radiation per unit mass
of irradiated material at the place of interest. The units of absorbed dose are
the rad and the gray (Gy).
3.
"Accelerator" means any machine capable of accelerating electrons, protons,
deuterons, or other charged particles in a vacuum and of discharging the
resultant particulate or other radiation into a medium at energies usually in
excess of 1 MeV. For purposes of this definition, "particle accelerator" is an
equivalent term.
4.
"Accelerator-produced radioactive material" means any material made radioactive
by a particle accelerator.
5.
"Acute" as used in this part, means a single radiation dose or multiple
radiation dose occurring within a short time (24 hours or less).
6. "Act" means the Mississippi Radiation
Protection Law of 1976.
7.
"Activity" means the rate of disintegration (transformation) or decay of
radioactive material. The units of activity are the curie (Ci) and the
becquerel (Bq).
8. "Adult" means an
individual 18 or more years of age.
9. "Agency" means the Mississippi State
Department of Health.
10.
"Agreement State" means any State with which the U.S. Nuclear Regulatory
Commission or the U.S. Atomic Energy Commission has entered into an effective
agreement under Subchapter 274b. of the Atomic Energy Act of 1954, as amended
(73 Stat.
689).
11. "Airborne
radioactive material" means any radioactive material dispersed in the air in
the form of dusts, fumes, particulates, mists, vapors, or gases.
12. "Airborne radioactivity area" means a
room, enclosure, or area in which airborne radioactive materials exist in
concentrations:
a. in excess of the derived
air concentrations (DACs) specified in Subchapter 4 (10 CFR Part
20, Appendix
B, Table 1) of these regulations; or
b. to such 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 percent
of the annual limit on intake (ALI) or 12 DAC- hours.
13. "Alert" means events may occur, are in
progress, or have occurred that could lead to a release of radioactive material
but that the release is not expected to require a response by offsite response
organizations to protect persons offsite.
14. "As low as is reasonably achievable"
(ALARA) means making every reasonable effort to maintain exposures to radiation
as far below the dose limits in these regulations as is practical, consistent
with the purpose for which the licensed or registered activity is undertaken,
taking into account the state of technology, the economics of improvements in
relation to 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 nuclear energy and licensed
or registered sources of radiation in the public interest.
15. "Becquerel" (Bq) means the SI unit of
activity. One becquerel is equal to 1 disintegration or transformation per
second (dps or tps).
16. "Bioassay"
means 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 these
regulations, "radiobioassay" is an equivalent term.
17. "Brachytherapy" means a method of
radiation therapy in which sealed sources are utilized to deliver a radiation
dose at a distance of up to a few centimeters, by surface, intracavitary, or
interstitial application.
18.
"Byproduct material" means:
a. Any radioactive
material, except special nuclear material, yielded in or made radioactive by
exposure to the radiation incident to the process of producing or utilizing
special nuclear material;
b. The
tailings or wastes produced by 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.
Underground ore bodies depleted by these solution extraction operations 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 after extraction, for use for a
commercial, medical, or research activity; ande. Any discrete source of
naturally occurring radioactive material, other than source material, that the
Nuclear Regulatory Commission, in consultation with the Administrator of the
Environmental Protection Agency, the Secretary of Energy, the 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; and is extracted or converted after extraction for use in a
commercial, medical, or research activity.
19. "Calendar quarter" means not less than 12
consecutive weeks nor more than 14 consecutive weeks. The first calendar
quarter of each year shall begin in January and subsequent calendar quarters
shall be so arranged such that no day is included in more than one calendar
quarter and no day in any one year is omitted from inclusion within a calendar
quarter. No licensee or registrant shall change the method observed by him of
determining calendar quarters for purposes of these regulations except at the
beginning of a year.
20.
"Calibration" means the determination of (1) the response or reading of an
instrument relative to a series of known radiation values over the range of the
instrument, or (2) the strength of a source of radiation relative to a
standard.
21. "CFR" means Code of
Federal Regulations"
22. "Chelating
agent" means amine polycarboxylic acids, hydroxycarboxylic acids, gluconic
acid, and polycarboxylic acids.
23.
"Collective dose" means 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.
24. "Committed dose
equivalent" (HT,50) means 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. "Committed effective
dose equivalent" (H
E, 50) is 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
(H
E,50 =
(HE,50 = [SIGMA]
WTHT,50).
).
25. "Consortium" means an association of
medical use licensees and a PET radionuclide production facility in the same
geographical area that jointly own or share in the operation and maintenance
cost of the PET radionuclide production facility that produces PET
radionuclides for use in producing radioactive drugs within the consortium for
noncommercial distributions among its associated members for medical use. The
PET radionuclide production facility within the consortium must be located at
an educational institution or a Federal facility or a medical
facility.
26. "Controlled area"
means an area, outside of a restricted area but inside the site boundary,
access to which can be limited by the licensee or registrant for any
reason.
27. "Critical Group" means
the group of individuals reasonably expected to receive the greatest exposure
to residual radioactivity for any applicable set of circumstances.
28. "Curie" means a unit of quantity of
radioactivity. One curie (Ci) is that quantity of radioactive material which
decays at the rate of 3.7E+10 transformations per second (tps). Commonly used
submultiples of the curie are the millicurie and the microcurie. One millicurie
(mCi) = 0.001 curie = 3.7E+7 tps. One microcurie (Ci) = 0.000001 curie = 3.7E+4
tps (See 1.1.16 for SI equivalent becquerel).
29. "Decommission" means to remove a facility
or site safely from service and reduce residual radioactivity to a level that
permits:
a. Release of the property for
unrestricted use and termination of the license; or
b. Release of the property under restricted
conditions and termination of the license.
30. "Deep dose equivalent" (Hd), which
applies to external whole body exposure, means the dose equivalent at a tissue
depth of 1 centimeter (1000 mg/cm2).
31. "Depleted uranium" means the source
material uranium in which the isotope uranium-235 is less than 0.711 weight
percent of the total uranium present. Depleted uranium does not include special
nuclear material.
32. "Discrete
source" means 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.
33.
"Distinguishable from background" means that 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 measurements technology, survey, and
statistical techniques.
34. "Dose"
is 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 these regulations, "radiation dose" is an equivalent term.
35. "Dose Commitmenf means the total
radiation dose to a part of the body that will result from retention in the
body of radioactive material. For purposes of estimating the dose commitment,
it is assumed that from the time of intake the period of exposure to retained
material will not exceed 50 years.
36. "Dose equivalent (Ht)" means 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 the sievert (Sv).
37.
"Dose limits" means the permissible upper bounds of radiation doses established
in accordance with these regulations. For purposes of these regulations,
"limits" is an equivalent term.
38.
"Effective dose equivalent (HE)" means 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 (H E =
[SIGMA] wTH T).
39. "Embryo/fetus" means the developing human
organism from conception until the time of birth.
40. "Entrance or access point" means any
opening through which an individual or extremity of an individual could gain
access to radiation areas or to sources of radiation. This includes entry or
exit portals of sufficient size to permit human entry, irrespective of their
intended use.
41. "Explosive
material" means any chemical compound, mixture, or device which produces a
substantial instantaneous release of gas and heat spontaneously or by contact
with sparks or flame.
42.
"Exposure" means being exposed to ionizing radiation or to radioactive
material.
43. "Exposure" means the
quotient of dQ by dm where "dQ" is the absolute value of the total charge of
the ions of one sign produced in air when all the electrons (negatrons and
positrons) liberated by photons in a volume element of air having mass "dm" are
completely stopped in air. The SI unit of exposure is the coulomb per kilogram
(C/kg). The special unit of exposure is the roentgen (R) (See 1.1.15 for SI
equivalent coulomb per kilogram).2
44. "Exposure rate" means the exposure per
unit of time, such as roentgen per minute and milliroentgen per hour.
45. "External dose" means that portion of the
dose equivalent received from any source of radiation outside the
body.
46. "Extremity" means hand,
elbow, arm below the elbow, foot, knee, and leg below the knee.
47. "Former U.S. Atomic Energy Commission
(AEC) or U.S. Nuclear Regulatory Commission (NRC) licensed facilities" means
nuclear reactors, nuclear fuel reprocessing plants, uranium enrichment plants,
or critical mass experimental facilities where AEC or NRC licenses have been
terminated.
48. "Generally
applicable environmental radiation standards" means standards issued by the
U.S. Environmental Protection Agency (EPA) under the authority of the Atomic
Energy Act of 1954, as amended, that impose limits on radiation exposuresor
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.
49. "Gray" (Gy) means the SI unit of absorbed
dose. One gray is equal to an absorbed dose of 1 joule per kilogram (100
rads).
50. "Hazardous waste" means
those wastes designated as hazardous by the U.S. Environmental Protection
Agency regulations in 40 CFR Part
261.
51. "Healing arts" means the professional
disciplines authorized by the laws of this state to use sources of radiation in
the diagnosis or treatment of human or animal diseases.
52. "High radiation area" means 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 1 hour at 30 centimeters from any
source of radiation or 30 centimeters from any surface that the radiation
penetrates.
53. "Human use" means
the internal or external administration of radiation or radioactive material to
human beings.
54. "Individual"
means any human being.
55.
"Individual monitoring" means the assessment of:
a. Dose equivalent:
(a) by the use of individual monitoring
devices, or
(b) by the use of
survey data; or
b.
Committed effective dose equivalent:
(a) by
bioassay, or
(b) by determination
of the time-weighted air concentrations to which an individual has been
exposed, that is, DAC-hours. (See the definition of DAC-hours in Subchapter
4).
56.
"Individual monitoring devices" (individual monitoring equipment) means devices
designed to be worn by a single individual for the assessment of dose
equivalent such as film badges, thermoluminescence dosimeters (TLDs), optically
stimulated luminescence dosimeters (OSLs), pocket ionization chambers, and
personal ("lapel") air sampling devices
57. "Inspection" means an official
examination or observation including, but not limited to, tests, surveys, and
monitoring to determine compliance with rules, regulations, orders,
requirements, and conditions of the Agency.
58. "Interlock" means a device arranged or
connected such that the occurrence of an event or condition is required before
a second event or condition can occur or continue to occur.
59. "Internal dose" means that portion of the
dose equivalent received from radioactive material taken into the
body
60. "Lens dose equivalent"
(LDE) applies to 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).
61. "License" means a license issued by the
Agency in accordance with the regulations adopted by the Agency.
62. "Licensed material" means radioactive
material received, possessed, used, transferred or disposed of under a general
or specific license issued by the Agency.
63. "Licensee" means any person who is
licensed by the Agency in accordance with these regulations and the
Act.
64. "Licensing State" means
any State with regulations equivalent to the Suggested State Regulations for
Control of Radiation relating to, and an effective program for, the regulatory
control of NARM and which has been granted final designation by the Conference
of Radiation Control Program Directors, Inc.
65. "Limits" See "Dose limits".
66. "Lost or missing source of radiation"
means a source of radiation 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.
67. "Lot Tolerance Percent
Defective" means the poorest quality in an individual inspection lot that
should be accepted, expressed in percent defective.
68. "Major processor" means a user
processing, handling, or manufacturing radioactive material exceeding Type A
quantities as unsealed sources or material, or exceeding 4 times Type B
quantities as sealed sources, but does not include nuclear medicine programs,
universities, industrial radiographers, or small industrial programs. Type A
and B quantities are defined in Subchapter 13 (
10
CFR
71.4) of these regulations.
69. "Member of the public" means any
individual except when that individual is receiving an occupational
dose.
70. "Minor" means an
individual less than 18 years of age.
71. "NARM" means any naturally occurring or
accelerator-produced radioactive material. It does not include byproduct,
source, or special nuclear material.
72. "Nationally tracked source" means a
sealed source containing a quantity equal to or greater than Category 1 or
Category 2 levels of any radioactive material listed in Subchapter 4 (10 CFR
Part
20, Appendix E) of these regulations. In this context a sealed source is
defined as radioactive material that is sealed in a capsule or closely bonded,
in a solid form and which is not exempt from regulatory control. It does not
mean material encapsulated solely for disposal, or nuclear material contained
in any fuel assembly, subassembly, fuel rod, or fuel pellet. Category 1
nationally tracked sources are those containing radioactive material at a
quantity equal to or greater than the Category 1 threshold. Category 2
nationally tracked sources are those containing radioactive material at a
quantity equal to or greater than the Category 2 threshold but less than the
Category 1 threshold.
73. "Natural
radioactivity" means radioactivity of naturally occurring nuclides.
74. "Nuclear Regulatory Commission" (NRC)
means the U.S. Nuclear Regulatory Commission or its duly authorized
representatives.
75. "Occupational
dose" means the dose received by an individual in the course of employment in
which the individual's assigned duties involve exposure to radiation and/or
radioactive material from licensed and unlicensed sources of radiation, whether
in the possession of the licensee, registrant, or other person. Occupational
dose does not include doses from background radiation, from any medical
administration the individual has received, from exposure to individuals
administered radioactive material and released in accordance with Subchapter 7
(
10
CFR
35.75) of these regulations, from
voluntary participation in medical research programs, or as a member of the
public.
76. "Offshore Waters" means
that area of land and water, beyond Agreement States' Submerged Lands Act
jurisdiction, on or above the U.S. Outer Continental Shelf
77. "Package" means the packaging together
with its radioactive contents as presented for transport.
78. "Particle accelerator" See
"Accelerator".
79. "Person" means
any individual, corporation, partnership, firm, association, trust, estate,
public or private institution, group, agency, political subdivision of this
State, any other State or political subdivision or agency thereof, and any
legal successor, representative, agent, or agency of the foregoing, other than
the NRC and federal government agencies licensed or exempted by the
NRC.
80. "Personnel monitoring
equipment" See "Individual monitoring devices".
81. "Pharmacist" means an individual licensed
by this State to compound and dispense drugs, prescriptions, and
poisons.
82. "Physician" means an
individual licensed by this State to dispense drugs in the practice of
medicine.
83. "Principal
activities" means activities authorized by the license which 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.
84. "Public dose" means
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 or registrant. Public dose 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
Subchapter 7 (
10
CFR
35.75) of these regulations, or from
voluntary participation in medical research programs.
85. "Pyrophoric liquid" means any liquid that
ignites spontaneously in dry or moist air at or below 130 ºF (54.4
ºC). A pyrophoric solid is any solid material, other than one classed as
an explosive, which under normal conditions is liable to cause fires through
friction, retained heat from manufacturing or processing, or which can be
ignited readily and, when ignited, burns so vigorously and persistently as to
create a serious transportation, handling, or disposal hazard. Included are
spontaneously combustible and water-reactive materials.
86. "Qualified expert" means an individual
having the knowledge and training to measure ionizing radiation, to evaluate
safety techniques, and to advise regarding radiation protection needs, for
example, individuals certified in the appropriate field by the American Board
of Radiology or the American Board of Health Physics, or those having
equivalent qualifications. With reference to the calibration of radiation
therapy equipment, an individual having, in addition to the above
qualifications, training and experience in the clinical applications of
radiation physics to radiation therapy, for example, individuals certified in
Therapeutic Radiological Physics or X-Ray and Radium Physics by the American
Board of Radiology, or those having equivalent qualifications.
87. "Quality factor" (Q) means the modifying
factor, listed in Tables I and II of 1.1.15, that is used to derive dose
equivalent from absorbed dose.
88.
"Rad" means the special unit of absorbed dose. One rad is equal to an absorbed
dose of 100 ergs per gram or 0.01 joule per kilogram (0.01 gray).
89. "Radiation" means gamma rays and x-rays,
alpha and beta particles, high speed electrons, neutrons, high speed protons
and other atomic particles and electromagnetic radiation consisting of
associated and interacting electric and magnetic waves and ultrasonic
waves.
90. "Radiation area" means
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 1 hour at 30 centimeters from the source of radiation or from
any surface that the radiation penetrates.
91. "Radiation dose" See "Dose".
92. "Radiation machine" means any device
capable of producing radiation except, those devices with radioactive material
as the only source of radiation.
93. "Radioactive material" means any solid,
liquid, or gas which emits radiation spontaneously.
94. "Radioactivity" means the transformation
of unstable atomic nuclei by the emission of radiation.
95. "Radiobioassay" See "Bioassay".
96. "Registrant" means any person who is
registered with the Agency and is legally obligated to register with the Agency
pursuant to these regulations and the Act.
97. "Registration" means registration with
the Agency in accordance with the regulations adopted by the Agency.
98. "Regulations of the U.S. Department of
Transportation" means the regulations in 49 CFR Parts
100-
189.
99. "Residual radioactivity" means
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 Subchapter 4 of
these regulations.
100. "Rem" means
the special unit of any of the quantities expressed as dose equivalent.
The dose equivalent in rem is equal to the absorbed dose
in rad multiplied by the quality factor (1 rem = 0.01 sievert).
101. "Research and development"
means
(1) theoretical analysis, exploration,
or experimentation; or
(2) the
extension of investigative findings and theories of a scientific or technical
nature into practical application for experimental and demonstration purposes,
including the experimental production and testing of models, devices,
equipment, materials, and processes. Research and development does not include
the internal or external administration of radiation or radioactive material to
human beings.
102.
"Roentgen" means the special unit of exposure. One roentgen (R) equals 2.58E-4
coulomb per kilogram of air (see "Exposure" and 1.1.15).
103. "Sealed source" means any radioactive
material that is encased in a capsule designed to prevent leakage or escape of
the radioactive material.
104.
"Shallow dose equivalent" (Hs), which applies to the external exposure of the
skin of the whole body or the skin of an extremity, means the dose equivalent
at a tissue depth of 0.007 centimeter (7
mg/cm2).
105. "SI" means the abbreviation for the
International System of Units
106.
"Sievert" (Sv) means 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 sievert = 100 rems).
107. "Site area emergency" means events may
occur, are in progress, or have occurred that could lead to a significant
release of radioactive material and that could require a response by offsite
response organizations to protect persons offsite.
108. "Site boundary" means that line beyond
which the land or property is not owned, leased, or otherwise controlled by the
licensee or registrant.
109.
"Source material" means:
a. Uranium or
thorium, or any combination thereof, in any physical or chemicalform;
or
b. Ores that contain by weight
one-twentieth of 1 percent (0.05 percent) or moreof uranium, thorium or any
combination of uranium and thorium. Source material does not include special
nuclear material.
110.
"Source material milling" means any activity that results in the production of
byproduct material as defined by definition (2) of byproduct
material.
111. "Source of
radiation" means any radioactive material or any device or equipment emitting,
or capable of producing, radiation.
112. "Special form radioactive material"
means radioactive material that satisfies the following conditions:
a. It is either a single solid piece or is
contained in a sealed capsule that can beopened only by destroying the
capsule;
b. The piece or capsule
has at least one dimension not less than 5 millimeters (0.2 inch);
and
c. It satisfies the test
requirements specified by the U.S. Nuclear Regulatory Commission. A special
form encapsulation designed in accordance with the U.S. Nuclear Regulatory
Commission 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 the Nuclear Regulatory Commission 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 requirements of this definition applicable at the time of
its design or construction.
113. "Special nuclear material" means:
a. Plutonium, uranium-233, uranium enriched
in the isotope 233 or in the isotope 235, and any other material that the U.S.
Nuclear Regulatory Commission, pursuant to the provisions of section 51 of the
Atomic Energy Act of 1954, 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 includesource material.
114. "Special nuclear material in quantities
not sufficient to form a critical mass" means uranium enriched in the isotope
U-235 in quantities not exceeding 350 grams of contained U-235; uranium-233 in
quantities not exceeding 200 grams; plutonium in quantities not exceeding 200
grams; or any combination of them 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 and are
within the formula:
|
175(grams contained U - 235)
|
50 (grams U - 233)
|
50 (grams
Pu)1
|
|
350
|
200
|
200
|
115. "Survey" means an evaluation of the
radiological conditions and potential hazards incident to the production, use,
transfer, release, disposal, or presence of sources of radiation. When
appropriate, such evaluation includes, but is not limited to, tests, physical
examinations, calculations, and measurements of levels of radiation or
concentrations of radioactive material present.
116. "Test" means the process of verifying
compliance with an applicable regulation.
117. "These regulations" mean all sections of
the Mississippi State Department of Health Regulations for Control of
Radiation, Subpart 78 - Radiological Health.
118. "Total effective dose equivalent" (TEDE)
means the sum of the effective dose equivalent for external exposures and the
committed effective dose equivalent for internal exposures.
119. "Total organ dose equivalent" (TODE)
means the sum of the deep dose equivalent and the committed dose equivalent to
the organ receiving the highest dose as described in Subchapter 4 (
10 CFR
20.2104) of these regulations.
120. "U.S. Department of Energy" means the
Department of Energy established by Public Law
95-91, August 4, 1977, 91 Stat.
565, 42 U.S.C.
7101 et
seq., to the extent that the Department exercises functions formerly vested in
the U.S. Atomic Energy Commission, its Chairman, members, officers and
components and transferred to the U.S. Energy Research and Development
Administration and to the Administrator thereof pursuant to sections 104(b),
(c) and (d) of the Energy Reorganization Act of 1974 ( Public Law
93-438,
October 11, 1974, 88 Stat.
1233 at 1237,
42 U.S.C.
5814, effective January 19, 1975) and
retransferred to the Secretary of Energy pursuant to section 301(a) of the
Department of Energy Organization Act ( Public Law
95-91, August 4, 1977, 91
Stat.
565 at 577-578,
42 U.S.C.
7151,
effective October 1, 1977).
121.
"Unrefined and unprocessed ore" means ore in its natural form prior to any
processing, such as grinding, roasting, beneficiating, or refining.
122. "Unrestricted area" means any area
access to which is neither limited nor controlled by the licensee or registrant
for purposes of protection of individuals from exposure to radiation and
radioactive material. For purposes of these regulations, "uncontrolled area" is
an equivalent term.
123. "Very high
radiation area" means 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 (5 grays) in 1 hour
at 1 meter from a source of radiation or from any surface that the radiation
penetrates.3
124. "Waste" means those 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 paragraphs (b.), (c.), (d.) and (e.)
of the definition of byproduct material set forth in this section.
125. "Waste handling licensees" mean persons
licensed to receive and store radioactive wastes prior to disposal and/or
persons licensed to dispose of radioactive waste.
126. "Week" means 7 consecutive days starting
on Sunday.
127. "Whole body" means,
for purposes of external exposure, head, trunk including male gonads, arms
above the elbow, or legs above the knee.
128. "Worker" means an individual engaged in
work under a license or registration issued by the Agency and controlled by a
licensee or registrant, but does not include the licensee or
registrant.
129. "Working level"
(WL) means any combination of short-lived radon daughters in 1 liter of air
that will result in the ultimate emission of 1.3E+5 MeV of potential alpha
particle energy. The short-lived radon daughters are -- for radon-222:
polonium-218, lead-214, bismuth-214, and polonium-214; and for radon-220:
polonium-216, lead-212, bismuth-212, and polonium-212.
130. "Working level month" (WLM) means an
exposure to 1 working level for 170 hours (2,000 working hours per year divided
by 12 months per year is approximately equal to 170 hours per month).
131. "Year" means the period of time
beginning in January used to determine compliance with the provisions of these
regulations. The licensee or registrant may change the starting date of the
year used to determine compliance by the licensee or registrant provided that
the change is made at the beginning of the year and that no day is omitted or
duplicated in consecutive years.
1 Attention is directed to the
fact that regulation by the State of source material, byproduct material, and
special nuclear material in quantities not sufficient to form a critical mass
is subject to the provisions of the agreement between State and the U.S.
Nuclear Regulatory Commission and to 10 CFR Part 150 of the Commission's
regulations.
2 "When not underlined as above or
indicated as 'exposure' (x), the term 'exposure' has a more general meaning in
these regulations."
3 "Very high radiation area"
means an area, accessible to individuals, in which radiation levels from
radiation sources external to the body could result in an individual receiving
an absorbed