| (26) Powered air-purifying respirator--An air-purifying
respirator that uses a blower to force the ambient air through air-purifying
elements to the inlet covering.
(27) 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.
(28) Qualitative fit test--A pass/fail fit test to
assess the adequacy of respirator fit that relies on the individual's
response to the test agent.
(29) Quantitative fit test--An assessment of the adequacy
of respirator fit by numerically measuring the amount of leakage into
the respirator.
(30) 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.
(31) Reference man--A hypothetical aggregation of human
physical and physiological characteristics determined by international
consensus. These characteristics may be used by researchers and public
health employees 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."
(32) Respiratory protective equipment--An apparatus,
such as a respirator, used to reduce an individual's intake of airborne
radioactive materials.
(33) 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
licensee or registrant.
(34) Self-contained breathing apparatus--An atmosphere-supplying
respirator for which the breathing air source is designed to be carried
by the user.
(35) 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 this section probabilistic effect
is an equivalent term.
(36) Supplied-air respirator or airline respirator--An
atmosphere-supplying respirator for which the source of breathing
air is not designed to be carried by the user.
(37) Tight-fitting facepiece--A respiratory inlet covering
that forms a complete seal with the face.
(38) 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.
(39) Weighting factor wT for
an organ or tissue (T)--The proportion of the risk of stochastic effects
resulting from irradiation of that organ or tissue to the total risk
of stochastic effects when the whole body is irradiated uniformly.
For calculating the effective dose equivalent, the values of wT are:
Attached Graphic
(d) Implementation.
(1) Any existing license condition that is more restrictive
than this section remains in force until there is an amendment or
renewal of the license that modifies or removes this condition.
(2) If a license condition exempts a licensee from
a provision of this section in effect on or before January 1, 1994,
it also exempts the licensee from the corresponding provision of this
section.
(3) If a license condition cites provisions of this
section in effect before January 1, 1994, that do not correspond to
any provisions of this section, the license condition remains in force
until there is an amendment or renewal of the license that modifies
or removes this condition.
(e) Radiation protection programs.
(1) Each licensee must develop, document, and implement
a radiation protection program sufficient to ensure compliance with
the provisions of this section. See subsection (mm) of this section
for recordkeeping requirements relating to these programs. Documentation
of the radiation protection program may be incorporated in the licensee's
operating, safety, and emergency procedures.
(2) The licensee must use, to the extent practicable,
procedures and engineering controls based upon sound radiation protection
principles to achieve occupational doses and public doses that are
as low as is reasonably achievable (ALARA).
(3) The licensee must, at intervals not to exceed 12
months, ensure the radiation protection program content and implementation
is reviewed. The review must include a reevaluation of the assessments
made to determine monitoring is not required, as specified in subsection
(q)(1) and (3) of this section in conjunction with the licensee's
current operating conditions.
(4) To implement the ALARA requirement in paragraph
(2) of this subsection and notwithstanding the requirements in subsection
(n) of this section, a constraint on air emissions of radioactive
material to the environment, excluding radon-222 and its daughters,
must be established by licensees such that the individual member of
the public likely to receive the highest dose will not be expected
to receive a total effective dose equivalent (TEDE) more than 10 millirem
(mrem) (0.1 millisievert (mSv)) per year, from these emissions. If
a licensee subject to this requirement exceeds this dose constraint,
the licensee must report the exceedance as required in subsection
(yy) of this section and promptly take appropriate corrective action
to ensure against recurrence.
(5) If monitoring is not required as specified in subsection
(q)(1) and (3) of this section, the licensee must document assessments
made to determine the requirements of subsection (q)(1) and (3) of
this section are not applicable. The licensee must maintain the documentation
as specified in subsection (rr)(5) of this section.
(f) Occupational dose limits for adults.
(1) The licensee must control the occupational dose
to individuals, except for planned special exposures as specified
in subsection (k) of this section, to the following dose limits.
(A) An annual limit that is the lesser of:
(i) the total effective dose equivalent being equal
to 5 rem (0.05 Sv); or
(ii) the sum of the deep dose equivalent and the committed
dose equivalent to any individual organ or tissue, other than the
lens of the eye, being equal to 50 rem (0.5 Sv).
(B) The annual limits to the lens of the eye, to the
skin of the whole body, and to the skin of the extremities are:
(i) a lens dose equivalent of 15 rem (0.15 Sv); and
(ii) a shallow dose equivalent of 50 rem (0.5 Sv) to
the skin of the whole body or to the skin of any extremity.
(2) Doses received over the annual limits, including
doses received during accidents, emergencies, and planned special
exposures, must be subtracted from the limits for planned special
exposures that the individual may receive during the current year
and during the individual's lifetime. See subsection (k)(6)(A) and
(B) of this section.
(3) When the external exposure is determined by measurement
with an external personal monitoring device, the deep-dose equivalent
must be used in place of the effective dose equivalent, unless the
effective dose equivalent is determined by a dosimetry method approved
by the department. The assigned deep dose equivalent must be for the
part of the body receiving the highest exposure. The assigned shallow-dose
equivalent must be the dose averaged over the contiguous 10 square
centimeters (cm2 ) of skin receiving the
highest exposure.
(4) The deep dose equivalent, lens dose equivalent,
and shallow dose equivalent may be assessed from surveys or other
radiation measurements for the purpose of demonstrating compliance
with the occupational dose limits, if the individual monitoring device
was not in the region of highest potential exposure, or the results
of individual monitoring are unavailable.
(5) DAC and ALI values are specified in Table I of
subsection (ggg)(2) of this section and may be used to determine the
individual's dose and to demonstrate compliance with the occupational
dose limits. See subsection (rr) of this section.
(6) Notwithstanding the annual dose limits, the licensee
must limit the soluble uranium intake by an individual to 10 milligrams
(mg) in a week, in consideration of chemical toxicity. See footnote
3 of subsection (ggg)(2) of this section.
Cont'd... |
