| Safety Code, Chapter 361.
Any licensed material included in subsection (ggg)(7) of this section
and which is a hazardous waste as defined in the Solid Waste Disposal
Act may be discarded at a facility authorized to manage hazardous
waste by the authorized regulatory agency.
(5) Each licensee who discards material described in
paragraphs (1) or (4) of this subsection shall:
(A) make surveys adequate to assure that the limits
of paragraphs (1) or (4) of this subsection are not exceeded; and
(B) remove or otherwise obliterate or obscure all labels,
tags, or other markings that would indicate that the material or its
contents is radioactive.
(6) Prior to authorizations in accordance with paragraph
(4) of this subsection, a licensee shall submit procedures to the
agency for:
(A) the physical delivery of the material to the disposal
site;
(B) surveys to be performed for compliance with paragraph
(5)(A) of this subsection;
(C) maintaining secure packaging during transportation
to the site; and
(D) maintaining records of any discards made under
paragraph (4) of this subsection.
(7) Nothing in this section relieves the licensee of
maintaining records showing the receipt, transfer, and discard of
such radioactive material as specified in §289.201(d) of this
title.
(8) Nothing in this section relieves the licensee from
complying with other applicable federal, state, and local regulations
governing any other toxic or hazardous property of these materials.
(9) Licensed material discarded under this section
is exempt from the requirements of §289.252(ff) of this title.
(ggg) Appendices.
(1) Assigned protection factors for respirators. The
following table contains assigned protection factors for respiratorsa :
Attached Graphic
(2) Annual limits on intake (ALI) and derived air concentrations
(DAC) of radionuclides for occupational exposure; effluent concentrations;
concentrations for release to sanitary sewerage.
(A) Introduction.
(i) For each radionuclide, Table I of subparagraph
(F) of this paragraph indicates the chemical form that is to be used
for selecting the appropriate ALI or DAC value. The ALIs and DACs
for inhalation are given for an aerosol with an activity median aerodynamic
diameter (AMAD) of 1 micron, and for three classes (D, W, Y) of radioactive
material, which refer to their retention (approximately days, weeks,
or years) in the pulmonary region of the lung. This classification
applies to a range of clearance half-times for D if less than 10 days,
for W from 10 to 100 days, and for Y greater than 100 days. Table
II of subparagraph (F) of this paragraph provides concentration limits
for airborne and liquid effluents released to the general environment.
Table III of subparagraph (F) of this paragraph provides concentration
limits for discharges to sanitary sewerage.
(ii) The values in Tables I, II, and III of subparagraph
(F) of this paragraph are presented in the computer "E" notation.
In this notation a value of 6E-02 represents a value of 6 x 10-2 or 0.06, 6E+2 represents 6 x 102 or 600, and 6E+0 represents 6 x 100 or 6.
(B) Occupational values.
(i) Note that the columns in Table I of subparagraph
(F) of this paragraph captioned "Oral Ingestion ALI," "Inhalation
ALI," and "DAC," are applicable to occupational exposure to radioactive
material.
(ii) The ALIs in subparagraph (F) of this paragraph
are the annual intakes of given radionuclide by "Reference Man" that
would result in either a committed effective dose equivalent of 5
rems (0.05 Sv), stochastic ALI, or a committed dose equivalent of
50 rems (0.5 Sv) to an organ or tissue, non-stochastic ALI. The stochastic
ALIs were derived to result in a risk, due to irradiation of organs
and tissues, comparable to the risk associated with deep dose equivalent
to the whole body of 5 rems (0.05 Sv). The derivation includes multiplying
the committed dose equivalent to an organ or tissue by a weighting
factor, wT . This weighting factor is
the proportion of the risk of stochastic effects resulting from irradiation
of the organ or tissue, T, to the total risk of stochastic effects
when the whole body is irradiated uniformly. The values of wT are listed under the definition of "weighting
factor" in subsection (c) of this section. The non-stochastic ALIs
were derived to avoid non-stochastic effects, such as prompt damage
to tissue or reduction in organ function.
(iii) A value of wT =
0.06 is applicable to each of the five organs or tissues in the "remainder"
category receiving the highest dose equivalents, and the dose equivalents
of all other remaining tissues may be disregarded. The following portions
of the GI tract; stomach, small intestine, upper large intestine,
and lower large intestine, are to be treated as four separate organs.
(iv) The dose equivalents for an extremity, skin, and
lens of the eye are not considered in computing the committed effective
dose equivalent, but are subject to limits that shall be met separately.
(v) When an ALI is defined by the stochastic dose limit,
this value alone is given. When an ALI is determined by the non-stochastic
dose limit to an organ, the organ or tissue to which the limit applies
is shown, and the ALI for the stochastic limit is shown in parentheses.
Abbreviated organ or tissue designations are used as follows:
(I) LLI wall = lower large intestine wall;
(II) St. wall = stomach wall;
(III) Blad wall = bladder wall; and
(IV) Bone surf = bone surface.
(vi) Attached Graphic
(vii) The dose equivalents for an extremity, skin,
and lens of the eye are not considered in computing the committed
effective dose equivalent, but are subject to limits that must be
met separately.
(viii) The DAC values are derived limits intended to
control chronic occupational exposures. The relationship between the
DAC and the ALI is given by:
Attached Graphic
(ix) The DAC values relate to one of two modes of exposure:
either external submersion or the internal committed dose equivalents
resulting from inhalation of radioactive materials. DACs based upon
submersion are for immersion in a semi-infinite cloud of uniform concentration
and apply to each radionuclide separately.
(x) The ALI and DAC values include contributions to
exposure by the single radionuclide named and any in-growth of daughter
radionuclides produced in the body by decay of the parent. However,
intakes that include both the parent and daughter radionuclides should
be treated by the general method appropriate for mixtures.
(xi) The values of ALI and DAC do not apply directly
when the individual both ingests and inhales a radionuclide, when
the individual is exposed to a mixture of radionuclides by either
inhalation or ingestion or both, or when the individual is exposed
to both internal and external irradiation. See subsection (g) of this
section. When an individual is exposed to radioactive materials which
fall under several of the translocation classifications of the same
radionuclide, such as, Class D, Class W, or Class Y, the exposure
may be evaluated as if it were a mixture of different radionuclides.
(xii) It should be noted that the classification of
a compound as Class D, W, or Y is based on the chemical form of the
compound and does not take into account the radiological half-life
of different radionuclides. For this reason, values are given for
Class D, W, and Y compounds, even for very short-lived radionuclides.
(C) Effluent concentrations.
(i) The columns in Table II of subparagraph (F) of
this paragraph captioned "Effluents," "Air," and "Water" are applicable
to the assessment and control of dose to the public, particularly
in the implementation of the provisions of subsection (o) of this
section. The concentration values given in Columns 1 and 2 of Table
II of subparagraph (F) of this paragraph are equivalent to the radionuclide
concentrations which, if inhaled or ingested continuously over the
course of a year, would produce a total effective dose equivalent
of 0.05 rem (0.5 mSv).
(ii) Consideration of non-stochastic limits has not
been included in deriving the air and water effluent concentration
limits because non-stochastic effects are presumed not to occur at
or below the dose levels established for individual members of the
public. For radionuclides, where the non-stochastic limit was governing
in deriving the occupational DAC, the stochastic ALI was used in deriving
the corresponding airborne effluent limit in Table II of subparagraph
(F) of this paragraph. For this reason, the DAC and airborne effluent
limits are not always proportional as they were in the previous radiation
protection standards.
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