[Title 40 CFR F]
[Code of Federal Regulations (annual edition) - July 1, 1996 Edition]
[Title 40 - PROTECTION OF ENVIRONMENT]
[Chapter I - ENVIRONMENTAL PROTECTION AGENCY (CONTINUED)]
[Subchapter F - RADIATION PROTECTION PROGRAMS]
[From the U.S. Government Publishing Office]
40
PROTECTION OF ENVIRONMENT
12
1996-07-01
1996-07-01
false
RADIATION PROTECTION PROGRAMS
F
SUBCHAPTER F
PROTECTION OF ENVIRONMENT
ENVIRONMENTAL PROTECTION AGENCY (CONTINUED)
SUBCHAPTER F--RADIATION PROTECTION PROGRAMS
PART 190--ENVIRONMENTAL RADIATION PROTECTION STANDARDS FOR NUCLEAR POWER OPERATIONS--Table of Contents
Subpart A--General Provisions
Sec.
190.01 Applicability.
190.02 Definitions.
Subpart B--Environmental Standards for the Uranium Fuel Cycle
190.10 Standards for normal operations.
190.11 Variances for unusual operations.
190.12 Effective date.
Authority: Atomic Energy Act of 1954, as amended; Reorganization
Plan No. 3, of 1970.
Source: 42 FR 2860, Jan. 13, 1977, unless otherwise noted.
Subpart A--General Provisions
Sec. 190.01 Applicability.
The provisions of this part apply to radiation doses received by
members of the public in the general environment and to radioactive
materials introduced into the general environment as the result of
operations which are part of a nuclear fuel cycle.
Sec. 190.02 Definitions.
(a) Nuclear fuel cycle means the operations defined to be associated
with the production of electrical power for public use by any fuel cycle
through utilization of nuclear energy.
(b) Uranium fuel cycle means the operations of milling of uranium
ore, chemical conversion of uranium, isotopic enrichment of uranium,
fabrication of uranium fuel, generation of electricity by a light-water-
cooled nuclear power plant using uranium fuel, and reprocessing of spent
uranium fuel, to the extent that these directly support the production
of electrical power for public use utilizing nuclear energy, but
excludes mining operations, operations at waste disposal sites,
transportation of any radioactive material in support of these
operations, and the reuse of recovered non-uranium special nuclear and
by-product materials from the cycle.
(c) General environment means the total terrestrial, atmospheric and
aquatic environments outside sites upon which any operation which is
part of a nuclear fuel cycle is conducted.
(d) Site means the area contained within the boundary of a location
under the control of persons possessing or using radioactive material on
which is conducted one or more operations covered by this part.
(e) Radiation means any or all of the following: Alpha, beta, gamma,
or X-rays; neutrons; and high-energy electrons, protons, or other atomic
particles; but not sound or radio waves, nor visible, infrared, or
ultraviolet light.
(f) Radioactive material means any material which spontaneously
emits radiation.
(g) Curie (Ci) means that quantity of radioactive material producing
37 billion nuclear transformations per second. (One millicurie
(mCi)=0.001 Ci.)
(h) Dose equivalent means the product of absorbed dose and
appropriate factors to account for differences in biological
effectiveness due to the quality of radiation and its spatial
distribution in the body. The unit of dose equivalent is the ``rem.''
(One millirem (mrem)= 0.001 rem.)
(i) Organ means any human organ exclusive of the dermis, the
epidermis, or the cornea.
(j) Gigawatt-year refers to the quantity of electrical energy
produced at the busbar of a generating station. A gigawatt is equal to
one billion watts. A gigawatt-year is equivalent to the amount of energy
output represented by an average electric power level of one gigawatt
sustained for one year.
(k) Member of the public means any individual that can receive a
radiation dose in the general environment, whether he may or may not
also be exposed to radiation in an occupation associated with a nuclear
fuel cycle. However, an individual is not considered a member of the
public during any
[[Page 6]]
period in which he is engaged in carrying out any operation which is
part of a nuclear fuel cycle.
(l) Regulatory agency means the government agency responsible for
issuing regulations governing the use of sources of radiation or
radioactive materials or emissions therefrom and carrying out inspection
and enforcement activities to assure compliance with such regulations.
Subpart B--Environmental Standards for the Uranium Fuel Cycle
Sec. 190.10 Standards for normal operations.
Operations covered by this subpart shall be conducted in such a
manner as to provide reasonable assurance that:
(a) The annual dose equivalent does not exceed 25 millirems to the
whole body, 75 millirems to the thyroid, and 25 millirems to any other
organ of any member of the public as the result of exposures to planned
discharges of radioactive materials, radon and its daughters excepted,
to the general environment from uranium fuel cycle operations and to
radiation from these operations.
(b) The total quantity of radioactive materials entering the general
environment from the entire uranium fuel cycle, per gigawatt-year of
electrical energy produced by the fuel cycle, contains less than 50,000
curies of krypton-85, 5 millicuries of iodine-129, and 0.5 millicuries
combined of plutonium-239 and other alpha-emitting transuranic
radionuclides with half-lives greater than one year.
Sec. 190.11 Variances for unusual operations.
The standards specified in Sec. 190.10 may be exceeded if:
(a) The regulatory agency has granted a variance based upon its
determination that a temporary and unusual operating condition exists
and continued operation is in the public interest, and
(b) Information is promptly made a matter of public record
delineating the nature of unusual operating conditions, the degree to
which this operation is expected to result in levels in excess of the
standards, the basis of the variance, and the schedule for achieving
conformance with the standards.
Sec. 190.12 Effective date.
(a) The standards in Sec. 190.10(a) shall be effective December 1,
1979, except that for doses arising from operations associated with the
milling of uranium ore the effective date shall be December 1, 1980.
(b) The standards in Sec. 190.10(b) shall be effective December 1,
1979, except that the standards for krypton-85 and iodine-129 shall be
effective January 1, 1983, for any such radioactive materials generated
by the fission process after these dates.
PART 191--ENVIRONMENTAL RADIATION PROTECTION STANDARDS FOR MANAGEMENT AND DISPOSAL OF SPENT NUCLEAR FUEL, HIGH-LEVEL AND TRANSURANIC RADIOACTIVE WASTES--Table of Contents
Subpart A--Environmental Standards for Management and Storage
Sec.
191.01 Applicability.
191.02 Definitions.
191.03 Standards.
191.04 Alternative standards.
191.05 Effective date.
Subpart B--Environmental Standards for Disposal
191.11 Applicability.
191.12 Definitions.
191.13 Containment requirements.
191.14 Assurance requirements.
191.15 Individual protection requirements.
191.16 Alternative provisions for disposal.
191.17 Effective date.
Subpart C--Environmental Standards for Ground-Water Protection
191.21 Applicability.
191.22 Definitions.
191.23 General provisions.
191.24 Disposal standards.
191.25 Compliance with other Federal regulations.
191.26 Alternative provisions.
191.27 Effective date.
Appendix A to Part 191--Table for Subpart B
Appendix B to Part 191--Calculation of Annual Committed Effective Dose
Appendix C to Part 191--Guidance for Implementation of Subpart B
[[Page 7]]
Authority: The Atomic Energy Act of 1954, as amended, 42 U.S.C.
2011-2296; Reorganization Plan No. 3 of 1970, 5 U.S.C. app. 1; the
Nuclear Waste Policy Act of 1982, as amended, 42 U.S.C. 10101-10270; and
the Waste Isolation Pilot Plant Land Withdrawal Act, Pub. L. 102-579,
106 Stat. 4777.
Source: 50 FR 38084, Sept. 19, 1985, unless otherwise noted.
Subpart A--Environmental Standards for Management and Storage
Sec. 191.01 Applicability.
This subpart applies to:
(a) Radiation doses received by members of the public as a result of
the management (except for transportation) and storage of spent nuclear
fuel or high-level or transuranic radioactive wastes at any facility
regulated by the Nuclear Regulatory Commission or by Agreement States,
to the extent that such management and storage operations are not
subject to the provisions of part 190 of title 40; and
(b) Radiation doses received by members of the public as a result of
the management and storage of spent nuclear fuel or high-level or
transuranic wastes at any disposal facility that is operated by the
Department of Energy and that is not regulated by the Commission or by
Agreement States.
Sec. 191.02 Definitions.
Unless otherwise indicated in this subpart, all terms shall have the
same meaning as in Subpart A of Part 190.
(a) Agency means the Environmental Protection Agency.
(b) Administrator means the Administrator of the Environmental
Protection Agency.
(c) Commission means the Nuclear Regulatory Commission.
(d) Department means the Department of Energy.
(e) NWPA means the Nuclear Waste Policy Act of 1982 (Pub. L. 97-
425).
(f) Agreement State means any State with which the Commission or the
Atomic Energy Commission has entered into an effective agreement under
subsection 274b of the Atomic Energy Act of 1954, as amended (68 Stat.
919).
(g) Spent nuclear fuel means fuel that has been withdrawn from a
nuclear reactor following irradiation, the constituent elements of which
have not been separated by reprocessing.
(h) High-level radioactive waste, as used in this part, means high-
level radioactive waste as defined in the Nuclear Waste Policy Act of
1982 (Pub. L. 97-425).
(i) Transuranic radioactive waste, as used in this part, means waste
containing more than 100 nanocuries of alpha-emitting transuranic
isotopes, with half-lives greater than twenty years, per gram of waste,
except for: (1) High-level radioactive wastes; (2) wastes that the
Department has determined, with the concurrence of the Administrator, do
not need the degree of isolation required by this part; or (3) wastes
that the Commission has approved for disposal on a case-by-case basis in
accordance with 10 CFR Part 61.
(j) Radioactive waste, as used in this part, means the high-level
and transuranic radioactive waste covered by this part.
(k) Storage means retention of spent nuclear fuel or radioactive
wastes with the intent and capability to readily retrieve such fuel or
waste for subsequent use, processing, or disposal.
(l) Disposal means permanent isolation of spent nuclear fuel or
radioactive waste from the accessible environment with no intent of
recovery, whether or not such isolation permits the recovery of such
fuel or waste. For example, disposal of waste in a mined geologic
repository occurs when all of the shafts to the repository are
backfilled and sealed.
(m) Management means any activity, operation, or process (except for
transportation) conducted to prepare spent nuclear fuel or radioactive
waste for storage or disposal, or the activities associated with placing
such fuel or waste in a disposal system.
(n) Site means an area contained within the boundary of a location
under the effective control of persons possessing or using spent nuclear
fuel or radioactive waste that are involved in any activity, operation,
or process covered by this subpart.
(o) General environment means the total terrestrial, atmospheric,
and
[[Page 8]]
aquatic environments outside sites within which any activity, operation,
or process associated with the management and storage of spent nuclear
fuel or radioactive waste is conducted.
(p) Member of the public means any individual except during the time
when that individual is a worker engaged in any activity, operation, or
process that is covered by the Atomic Energy Act of 1954, as amended.
(q) Critical organ means the most exposed human organ or tissue
exclusive of the integumentary system (skin) and the cornea.
Sec. 191.03 Standards.
(a) Management and storage of spent nuclear fuel or high-level or
transuranic radioactive wastes at all facilities regulated by the
Commission or by Agreement States shall be conducted in such a manner as
to provide reasonable assurance that the combined annual dose equivalent
to any member of the public in the general environment resulting from:
(1) Discharges of radioactive material and direct radiation from such
management and storage and (2) all operations covered by Part 190; shall
not exceed 25 millirems to the whole body, 75 millirems to the thyroid,
and 25 millirems to any other critical organ.
(b) Management and storage of spent nuclear fuel or high-level or
transuranic radioactive wastes at all facilities for the disposal of
such fuel or waste that are operated by the Department and that are not
regulated by the Commission or Agreement States shall be conducted in
such a manner as to provide reasonable assurance that the combined
annual dose equivalent to any member of the public in the general
environment resulting from discharges of radioactive material and direct
radiation from such management and storage shall not exceed 25 millirems
to the whole body and 75 millirems to any critical organ.
Sec. 191.04 Alternative standards.
(a) The Administrator may issue alternative standards from those
standards established in Sec. 191.03(b) for waste management and storage
activities at facilities that are not regulated by the Commission or
Agreement States if, upon review of an application for such alternative
standards:
(1) The Administrator determines that such alternative standards
will prevent any member of the public from receiving a continuous
exposure of more than 100 millirems per year dose equivalent and an
infrequent exposure of more than 500 millirems dose equivalent in a year
from all sources, excluding natural background and medical procedures;
and
(2) The Administrator promptly makes a matter of public record the
degree to which continued operation of the facility is expected to
result in levels in excess of the standards specified in Sec. 191.03(b).
(b) An application for alternative standards shall be submitted as
soon as possible after the Department determines that continued
operation of a facility will exceed the levels specified in
Sec. 191.03(b) and shall include all information necessary for the
Administrator to make the determinations called for in Sec. 191.04(a).
(c) Requests for alternative standards shall be submitted to the
Administrator, U.S. Environmental Protection Agency, 401 M Street, SW.,
Washington, DC 20460.
Sec. 191.05 Effective date.
The standards in this subpart shall be effective on November 18,
1985.
Subpart B--Environmental Standards for Disposal
Sec. 191.11 Applicability.
(a) This subpart applies to:
(1) Radioactive materials released into the accessible environment
as a result of the disposal of spent nuclear fuel or high-level or
transuranic radioactive wastes;
(2) Radiation doses received by members of the public as a result of
such disposal; and
(3) Radioactive contamination of certain sources of ground water in
the vicinity of disposal systems for such fuel or wastes.
(b) This subpart does not apply to:
(1) Disposal directly into the oceans or ocean sediments;
[[Page 9]]
(2) Wastes disposed of before November 18, 1985; and
(3) The characterization, licensing, construction, operation, or
closure of any site required to be characterized under section 113(a) of
Public Law 97-425, 96 Stat. 2201.
[50 FR 38084, Sept. 19, 1985, as amended at 58 FR 66414, Dec. 20, 1993]
Sec. 191.12 Definitions.
Unless otherwise indicated in this subpart, all terms shall have the
same meaning as in subpart A of this part.
Accessible environment means: (1) The atmosphere; (2) land surfaces;
(3) surface waters; (4) oceans; and (5) all of the lithosphere that is
beyond the controlled area.
Active institutional control means: (1) Controlling access to a
disposal site by any means other than passive institutional controls;
(2) performing maintenance operations or remedial actions at a site, (3)
controlling or cleaning up releases from a site, or (4) monitoring
parameters related to disposal system performance.
Annual committed effective dose means the committed effective dose
resulting from one-year intake of radionuclides released plus the annual
effective dose caused by direct radiation from facilities or activities
subject to subparts B and C of this part.
Aquifer means an underground geological formation, group of
formations, or part of a formation that is capable of yielding a
significant amount of water to a well or spring.
Barrier means any material or structure that prevents or
substantially delays movement of water or radionuclides toward the
accessible environment. For example, a barrier may be a geologic
structure, a canister, a waste form with physical and chemical
characteristics that significantly decrease the mobility of
radionuclides, or a material placed over and around waste, provided that
the material or structure substantially delays movement of water or
radionuclides.
Controlled area means: (1) A surface location, to be identified by
passive institutional controls, that encompasses no more than 100 square
kilometers and extends horizontally no more than five kilometers in any
direction from the outer boundary of the original location of the
radioactive wastes in a disposal system; and (2) the subsurface
underlying such a surface location.
Disposal system means any combination of engineered and natural
barriers that isolate spent nuclear fuel or radioactive waste after
disposal.
Dose equivalent means the product of absorbed dose and appropriate
factors to account for differences in biological effectiveness due to
the quality of radiation and its spatial distribution in the body; the
unit of dose equivalent is the ``rem'' (``sievert'' in SI units).
Effective dose means the sum over specified tissues of the products
of the dose equivalent received following an exposure of, or an intake
of radionuclides into, specified tissues of the body, multiplied by
appropriate weighting factors. This allows the various tissue-specific
health risks to be summed into an overall health risk. The method used
to calculate effective dose is described in appendix B of this part.
Ground water means water below the land surface in a zone of
saturation.
Heavy metal means all uranium, plutonium, or thorium placed into a
nuclear reactor.
Implementing agency means:
(1) The Commission for facilities licensed by the Commission;
(2) The Agency for those implementation responsibilities for the
Waste Isolation Pilot Plant, under this part, given to the Agency by the
Waste Isolation Pilot Plant Land Withdrawal Act (Pub. L. 102-579, 106
Stat. 4777) which, for the purposes of this part, are:
(i) Determinations by the Agency that the Waste Isolation Pilot
Plant is in compliance with subpart A of this part;
(ii) Issuance of criteria for the certifications of compliance with
subparts B and C of this part of the Waste Isolation Pilot Plant's
compliance with subparts B and C of this part;
(iii) Certifications of compliance with subparts B and C of this
part of the Waste Isolation Pilot Plant's compliance with subparts B and
C of this part;
(iv) If the initial certification is made, periodic recertification
of the
[[Page 10]]
Waste Isolation Pilot Plant's continued compliance with subparts B and C
of this part;
(v) Review and comment on performance assessment reports of the
Waste Isolation Pilot Plant; and
(vi) Concurrence by the Agency with the Department's determination
under Sec. 191.02(i) that certain wastes do not need the degree of
isolation required by subparts B and C of this part; and
(3) The Department of Energy for any other disposal facility and all
other implementation responsibilities for the Waste Isolation Pilot
Plant, under this part, not given to the Agency.
International System of Units is the version of the metric system
which has been established by the International Bureau of Weights and
Measures and is administered in the United States by the National
Institute of Standards and Technology. The abbreviation for this system
is ``SI.''
Lithosphere means the solid part of the Earth below the surface,
including any ground water contained within it.
Passive institutional control means: (1) Permanent markers placed at
a disposal site, (2) public records and archives, (3) government
ownership and regulations regarding land or resource use, and (4) other
methods of preserving knowledge about the location, design, and contents
of a disposal system.
Performance assessment means an analysis that: (1) Identifies the
processes and events that might affect the disposal system; (2) examines
the effects of these processes and events on the performance of the
disposal system; and (3) estimates the cumulative releases of
radionuclides, considering the associated uncertainties, caused by all
significant processes and events. These estimates shall be incorporated
into an overall probability distribution of cumulative release to the
extent practicable.
Radioactive material means matter composed of or containing
radionuclides, with radiological half-lives greater than 20 years,
subject to the Atomic Energy Act of 1954, as amended.
SI unit means a unit of measure in the International System of
Units.
Sievert is the SI unit of effective dose and is equal to 100 rem or
one joule per kilogram. The abbreviation is ``Sv.''
Undisturbed performance means the predicted behavior of a disposal
system, including consideration of the uncertainties in predicted
behavior, if the disposal system is not disrupted by human intrusion or
the occurrence of unlikely natural events.
Waste, as used in this subpart, means any spent nuclear fuel or
radioactive waste isolated in a disposal system.
Waste form means the materials comprising the radioactive components
of waste and any encapsulating or stabilizing matrix.
[50 FR 38084, Sept. 19, 1985, as amended at 58 FR 66414, Dec. 20, 1993]
Sec. 191.13 Containment requirements.
(a) Disposal systems for spent nuclear fuel or high-level or
transuranic radioactive wastes shall be designed to provide a reasonable
expectation, based upon performance assessments, that the cumulative
releases of radionuclides to the accessible environment for 10,000 years
after disposal from all significant processes and events that may affect
the disposal system shall:
(1) Have a likelihood of less than one chance in 10 of exceeding the
quantities calculated according to Table 1 (appendix A); and
(2) Have a likelihood of less than one chance in 1,000 of exceeding
ten times the quantities calculated according to Table 1 (appendix A).
(b) Performance assessments need not provide complete assurance that
the requirements of Sec. 191.13(a) will be met. Because of the long time
period involved and the nature of the events and processes of interest,
there will inevitably be substantial uncertainties in projecting
disposal system performance. Proof of the future performance of a
disposal system is not to be had in the ordinary sense of the word in
situations that deal with much shorter time frames. Instead, what is
required is a reasonable expectation, on the basis of the record before
the implementing agency, that compliance with Sec. 191.13 (a) will be
achieved.
[[Page 11]]
Sec. 191.14 Assurance requirements.
To provide the confidence needed for long-term compliance with the
requirements of Sec. 191.13, disposal of spent nuclear fuel or high-
level or transuranic wastes shall be conducted in accordance with the
following provisions, except that these provisions do not apply to
facilities regulated by the Commission (see 10 CFR Part 60 for
comparable provisions applicable to facilities regulated by the
Commission):
(a) Active institutional controls over disposal sites should be
maintained for as long a period of time as is practicable after
disposal; however, performance assessments that assess isolation of the
wastes from the accessible environment shall not consider any
contributions from active institutional controls for more than 100 years
after disposal.
(b) Disposal systems shall be monitored after disposal to detect
substantial and detrimental deviations from expected performance. This
monitoring shall be done with techniques that do not jeopardize the
isolation of the wastes and shall be conducted until there are no
significant concerns to be addressed by further monitoring.
(c) Disposal sites shall be designated by the most permanent
markers, records, and other passive institutional controls practicable
to indicate the dangers of the wastes and their location.
(d) Disposal systems shall use different types of barriers to
isolate the wastes from the accessible environment. Both engineered and
natural barriers shall be included.
(e) Places where there has been mining for resources, or where there
is a reasonable expectation of exploration for scarce or easily
accessible resources, or where there is a significant concentration of
any material that is not widely available from other sources, should be
avoided in selecting disposal sites. Resources to be considered shall
include minerals, petroleum or natural gas, valuable geologic
formations, and ground waters that are either irreplaceable because
there is no reasonable alternative source of drinking water available
for substantial populations or that are vital to the preservation of
unique and sensitive ecosystems. Such places shall not be used for
disposal of the wastes covered by this part unless the favorable
characteristics of such places compensate for their greater likelihood
of being disturbed in the future.
(f) Disposal systems shall be selected so that removal of most of
the wastes is not precluded for a reasonable period of time after
disposal.
Sec. 191.15 Individual protection requirements.
(a) Disposal systems for waste and any associated radioactive
material shall be designed to provide a reasonable expectation that, for
10,000 years after disposal, undisturbed performance of the disposal
system shall not cause the annual committed effective dose, received
through all potential pathways from the disposal system, to any member
of the public in the accessible environment, to exceed 15 millirems (150
microsieverts).
(b) Annual committed effective doses shall be calculated in
accordance with appendix B of this part.
(c) Compliance assessments need not provide complete assurance that
the requirements of paragraph (a) of this section will be met. Because
of the long time period involved and the nature of the processes and
events of interest, there will inevitably be substantial uncertainties
in projecting disposal system performance. Proof of the future
performance of a disposal system is not to be had in the ordinary sense
of the word in situations that deal with much shorter time frames.
Instead, what is required is a reasonable expectation, on the basis of
the record before the implementing agency, that compliance with
paragraph (a) of this section will be achieved.
(d) Compliance with the provisions in this section does not negate
the necessity to comply with any other applicable Federal regulations or
requirements.
(e) The standards in this section shall be effective on January 19,
1994.
[58 FR 66414, Dec. 20, 1993]
[[Page 12]]
Sec. 191.16 Alternative provisions for disposal.
The Administrator may, by rule, substitute for any of the provisions
of subpart B alternative provisions chosen after:
(a) The alternative provisions have been proposed for public comment
in the Federal Register together with information describing the costs,
risks, and benefits of disposal in accordance with the alternative
provisions and the reasons why compliance with the existing provisions
of Subpart B appears inappropriate;
(b) A public comment period of at least 90 days has been completed,
during which an opportunity for public hearings in affected areas of the
country has been provided; and
(c) The public comments received have been fully considered in
developing the final version of such alternative provisions.
[50 FR 38084, Sept. 19, 1985. Redesignated at 58 FR 66414, Dec. 20,
1993]
Sec. 191.17 Effective date.
The standards in this subpart shall be effective on November 18,
1985.
[50 FR 38084, Sept. 19, 1985; 50 FR 40003, Oct. 1, 1985. Redesignated at
58 FR 66414, Dec. 20, 1993]
Subpart C--Environmental Standards for Ground-Water Protection
Source: 58 FR 66415, Dec. 20, 1993, unless otherwise noted.
Sec. 191.21 Applicability.
(a) This subpart applies to:
(1) Radiation doses received by members of the public as a result of
activities subject to subpart B of this part; and
(2) Radioactive contamination of underground sources of drinking
water in the accessible environment as a result of such activities.
(b) This subpart does not apply to:
(1) Disposal directly into the oceans or ocean sediments;
(2) Wastes disposed of before the effective date of this subpart;
and
(3) The characterization, licensing, construction, operation, or
closure of any site required to be characterized under section 113(a) of
Public Law 97-425, 96 Stat. 2201.
Sec. 191.22 Definitions.
Unless otherwise indicated in this subpart, all terms have the same
meaning as in subparts A and B of this part.
Public water system means a system for the provision to the public
of piped water for human consumption, if such system has at least
fifteen service connections or regularly serves at least twenty-five
individuals. Such term includes:
(1) Any collection, treatment, storage, and distribution facilities
under control of the operator of such system and used primarily in
connection with such system; and
(2) Any collection or pretreatment storage facilities not under such
control which are used primarily in connection with such system.
Total dissolved solids means the total dissolved (filterable) solids
in water as determined by use of the method specified in 40 CFR part
136.
Underground source of drinking water means an aquifer or its portion
which:
(1) Supplies any public water system; or
(2) Contains a sufficient quantity of ground water to supply a
public water system; and
(i) Currently supplies drinking water for human consumption; or
(ii) Contains fewer than 10,000 milligrams of total dissolved solids
per liter.
Sec. 191.23 General provisions.
(a) Determination of compliance with this subpart shall be based
upon underground sources of drinking water which have been identified on
the date the implementing agency determines compliance with subpart C of
this part.
(b) [Reserved]
Sec. 191.24 Disposal standards.
(a) Disposal systems.
(1) General. Disposal systems for waste and any associated
radioactive material shall be designed to provide a reasonable
expectation that 10,000 years of undisturbed performance after
[[Page 13]]
disposal shall not cause the levels of radioactivity in any underground
source of drinking water, in the accessible environment, to exceed the
limits specified in 40 CFR part 141 as they exist on January 19, 1994.
(2) Disposal systems above or within a formation which within one-
quarter (\1/4\) mile contains an underground source of drinking water.
[Reserved]
(b) Compliance assessments need not provide complete assurance that
the requirements of paragraph (a) of this section will be met. Because
of the long time period involved and the nature of the processes and
events of interest, there will inevitably be substantial uncertainties
in projecting disposal system performance. Proof of the future
performance of a disposal system is not to be had in the ordinary sense
of the word in situations that deal with much shorter time frames.
Instead, what is required is a reasonable expectation, on the basis of
the record before the implementing agency, that compliance with
paragraph (a) of this section will be achieved.
Sec. 191.25 Compliance with other Federal regulations.
Compliance with the provisions in this subpart does not negate the
necessity to comply with any other applicable Federal regulations or
requirements.
Sec. 191.26 Alternative provisions.
The Administrator may, by rule, substitute for any of the provisions
of this subpart alternative provisions chosen after:
(a) The alternative provisions have been proposed for public comment
in the Federal Register together with information describing the costs,
risks, and benefits of disposal in accordance with the alternative
provisions and the reasons why compliance with the existing provisions
of this subpart appears inappropriate;
(b) A public comment period of at least 90 days has been completed,
during which an opportunity for public hearings in affected areas of the
country has been provided; and
(c) The public comments received have been fully considered in
developing the final version of such alternative provisions.
Sec. 191.27 Effective date.
The standards in this subpart shall be effective on January 19,
1994.
Appendix A to Part 191--Table for Subpart B
Table 1--Release Limits for Containment Requirements
[Cumulative releases to the accessible environment for 10,000 years
after disposal]
------------------------------------------------------------------------
Release
limit per
1,000
MTHM or
other
Radionuclide unit of
waste
(see
notes)
(curies)
------------------------------------------------------------------------
Americium-241 or -243........................................ 100
Carbon-14.................................................... 100
Cesium-135 or -137........................................... 1,000
Iodine-129................................................... 100
Neptunium-237................................................ 100
Plutonium-238, -239, -240, or -242........................... 100
Radium-226................................................... 100
Strontium-90................................................. 1,000
Technetium-99................................................ 10,000
Thorium-230 or -232.......................................... 10
Tin-126...................................................... 1,000
Uranium-233, -234, -235, -236, or -238....................... 100
Any other alpha-emitting radionuclide with a half-life
greater than 20 years....................................... 100
Any other radionuclide with a half-life greater than 20 years
that does not emit alpha particles.......................... 1,000
------------------------------------------------------------------------
Application of Table 1
Note 1: Units of Waste. The Release Limits in Table 1 apply to the
amount of wastes in any one of the following:
(a) An amount of spent nuclear fuel containing 1,000 metric tons of
heavy metal (MTHM) exposed to a burnup between 25,000 megawatt-days per
metric ton of heavy metal (MWd/MTHM) and 40,000 MWd/MTHM;
(b) The high-level radioactive wastes generated from reprocessing
each 1,000 MTHM exposed to a burnup between 25,000 MWd/MTHM and 40,000
MWd/MTHM;
(c) Each 100,000,000 curies of gamma or beta-emitting radionuclides
with half-lives greater than 20 years but less than 100 years (for use
as discussed in Note 5 or with materials that are identified by the
Commission as high-level radioactive waste in accordance with part B of
the definition of high-level waste in the NWPA);
(d) Each 1,000,000 curies of other radionuclides (i.e., gamma or
beta-emitters with half-lives greater than 100 years or any alpha-
emitters with half-lives greater than 20 years) (for use as discussed in
Note 5 or with materials that are identified by the
[[Page 14]]
Commission as high-level radioactive waste in accordance with part B of
the definition of high-level waste in the NWPA); or
(e) An amount of transuranic (TRU) wastes containing one million
curies of alpha-emitting transuranic radionuclides with half-lives
greater than 20 years.
Note 2: Release Limits for Specific Disposal Systems. To develop
Release Limits for a particular disposal system, the quantities in Table
1 shall be adjusted for the amount of waste included in the disposal
system compared to the various units of waste defined in Note 1. For
example:
(a) If a particular disposal system contained the high-level wastes
from 50,000 MTHM, the Release Limits for that system would be the
quantities in Table 1 multiplied by 50 (50,000 MTHM divided by 1,000
MTHM).
(b) If a particular disposal system contained three million curies
of alpha-emitting transuranic wastes, the Release Limits for that system
would be the quantities in Table 1 multiplied by three (three million
curies divided by one million curies).
(c) If a particular disposal system contained both the high-level
wastes from 50,000 MTHM and 5 million curies of alpha-emitting
transuranic wastes, the Release Limits for that system would be the
quantities in Table 1 multiplied by 55:
50,000 MTHM 5,000,000 curies TRU
------------------------------------------ + ----------------------- =55
1,000 MTHM 1,000,000 curies TRU
Note 3: Adjustments for Reactor Fuels with Different Burnup. For
disposal systems containing reactor fuels (or the high-level wastes from
reactor fuels) exposed to an average burnup of less than 25,000 MWd/MTHM
or greater than 40,000 MWd/MTHM, the units of waste defined in (a) and
(b) of Note 1 shall be adjusted. The unit shall be multiplied by the
ratio of 30,000 MWd/MTHM divided by the fuel's actual average burnup,
except that a value of 5,000 MWd/MTHM may be used when the average fuel
burnup is below 5,000 MWd/MTHM and a value of 100,000 MWd/MTHM shall be
used when the average fuel burnup is above 100,000 MWd/MTHM. This
adjusted unit of waste shall then be used in determining the Release
Limits for the disposal system.
For example, if a particular disposal system contained only high-
level wastes with an average burnup of 3,000 MWd/MTHM, the unit of waste
for that disposal system would be:
(30,000)
1,000 MTHM x --------------------- = 6,000 MTHM
(5,000)
If that disposal system contained the high-level wastes from 60,000
MTHM (with an average burnup of 3,000 MWd/MTHM), then the Release Limits
for that system would be the quantities in Table 1 multiplied by ten:
60,000 MTHM
------------------- =10
6,000 MTHM
which is the same as:
60,000 MTHM (5,000 MWd/MTHM)
---------------------- x ------------------------------- =10
1,000 MTHM (30,000 MWd/MTHM)
Note 4: Treatment of Fractionated High-Level Wastes. In some cases,
a high-level waste stream from reprocessing spent nuclear fuel may have
been (or will be) separated into two or more high-level waste components
destined for different disposal systems. In such cases, the implementing
agency may allocate the Release Limit multiplier (based upon the
original MTHM and the average fuel burnup of the high-level waste
stream) among the various disposal systems as it chooses, provided that
the total Release Limit multiplier used for that waste stream at all of
its disposal systems may not exceed the Release Limit multiplier that
would be used if the entire waste stream were disposed of in one
disposal system.
Note 5: Treatment of Wastes with Poorly Known Burnups or Original
MTHM. In some cases, the records associated with particular high-level
waste streams may not be adequate to accurately determine the original
metric tons of heavy metal in the reactor fuel that created the waste,
or to determine the average burnup that the fuel was exposed to. If the
uncertainties are such that the original amount of heavy metal or the
average fuel burnup for particular high-level waste streams cannot be
quantified, the units of waste derived from (a) and (b) of Note 1 shall
no longer be used. Instead, the units of waste defined in (c) and (d) of
Note 1 shall be used for such high-level waste streams. If the
uncertainties in such information allow a range of values to be
associated with the original amount of heavy metal or the average fuel
burnup, then the calculations described in previous Notes will be
conducted using the values that result in the smallest Release Limits,
except that the Release Limits need not be smaller than those that would
be calculated using the units of waste defined in (c) and (d) of Note 1.
Note 6: Uses of Release Limits to Determine Compliance with
Sec. 191.13 Once release limits for a particular disposal system have
been determined in accordance with Notes 1 through 5, these release
limits shall be used to determine compliance with the requirements of
Sec. 191.13 as follows. In cases where a mixture of radionuclides is
projected to be released to the accessible environment, the
[[Page 15]]
limiting values shall be determined as follows: For each radionuclide in
the mixture, determine the ratio between the cumulative release quantity
projected over 10,000 years and the limit for that radionuclide as
determined from Table 1 and Notes 1 through 5. The sum of such ratios
for all the radionuclides in the mixture may not exceed one with regard
to Sec. 191.13(a)(1) and may not exceed ten with regard to
Sec. 191.13(a)(2).
For example, if radionuclides A, B, and C are projected to be
released in amounts Qa, Qb, and Qc, and if the applicable
Release Limits are RLa, RLb, and RLc, then the cumulative
releases over 10,000 years shall be limited so that the following
relationship exists:
Qa Qb Qc
----- + ----- + ----- 1
RLa RLb RLc
[50 FR 38084, Sept. 19, 1985, as amended at 58 FR 66415, Dec. 20, 1993]
Appendix B to Part 191--Calculation of Annual Committed Effective Dose
I. Equivalent Dose
The calculation of the committed effective dose (CED) begins with
the determination of the equivalent dose, HT, to a tissue or organ,
T, listed in Table B.2 below by using the equation:
[GRAPHIC] [TIFF OMITTED] TR20DE93.009
where DT,R is the absorbed dose in rads (one gray, an SI unit,
equals 100 rads) averaged over the tissue or organ, T, due to radiation
type, R, and wR is the radiation weighting factor which is given in
Table B.1 below. The unit of equivalent dose is the rem (sievert, in SI
units).
Table B.1.--Radiation Weighting Factors, wR\1\
------------------------------------------------------------------------
wR
Radiation type and energy range \2\ value
------------------------------------------------------------------------
Photons, all energies........................................... 1
Electrons and muons, all energies............................... 1
Neutrons, energy < 10 keV....................................... 5
10 keV to 100 keV..................................... 10
>100 keV to 2 MeV..................................... 20
>2 MeV to 20 MeV...................................... 10
>20 MeV............................................... 5
Protons, other than recoil protons, >2 MeV.................... 5
Alpha particles, fission fragments, heavy nuclei................ 20
------------------------------------------------------------------------
\1\ All values relate to the radiation incident on the body or, for
internal sources, emitted from the source.
\2\ See paragraph A14 in ICRP Publication 60 for the choice of values
for other radiation types and energies not in the table.
II. Effective Dose
The next step is the calculation of the effective dose, E. The
probability of occurrence of a stochastic effect in a tissue or organ is
assumed to be proportional to the equivalent dose in the tissue or
organ. The constant of proportionality differs for the various tissues
of the body, but in assessing health detriment the total risk is
required. This is taken into account using the tissue weighting factors,
wT in Table B.2, which represent the proportion of the stochastic
risk resulting from irradiation of the tissue or organ to the total risk
when the whole body is irradiated uniformly and HT is the
equivalent dose in the tissue or organ, T, in the equation:
[GRAPHIC] [TIFF OMITTED] TR20DE93.010
Table B.2--Tissue Weighting Factors, wT \1\
------------------------------------------------------------------------
Tissue or organ wT value
------------------------------------------------------------------------
Gonads.................................................. 0.25
Breast.................................................. 0.15
Red bone marrow......................................... 0.12
Lung.................................................... 0.12
Thyroid................................................. 0.03
Bone surfaces........................................... 0.03
Remainder............................................... \2\ 0.30
------------------------------------------------------------------------
\1\ The values are considered to be appropriate for protection for
individuals of both sexes and all ages.
\2\ For purposes of calculation, the remainder is comprised of the five
tissues or organs not specifically listed in Table B.2 that receive
the highest dose equivalents; a weighting factor of 0.06 is applied to
each of them, including the various sections of the gastrointestinal
tract which are treated as separate organs. This covers all tissues
and organs except the hands and forearms, the feet and ankles, the
skin and the lens of the eye. The excepted tissues and organs should
be excluded from the computation of HE.
III. Annual Committed Tissue or Organ Equivalent Dose
For internal irradiation from incorporated radionuclides, the total
absorbed dose will be spread out in time, being gradually delivered as
the radionuclide decays. The time distribution of the absorbed dose rate
will vary with the radionuclide, its form, the mode of intake and the
tissue within which it is incorporated. To take account of this
distribution the quantity committed equivalent dose, HT()
where is the integration time in years following an intake over any
particular year, is used and is the integral over time of the equivalent
dose rate in a particular tissue or organ that will be received by an
individual following an intake of radioactive material into the body.
The time period, , is taken as 50 years as an average time of
exposure following intake:
[[Page 16]]
[GRAPHIC] [TIFF OMITTED] TR20DE93.011
for a single intake of activity at time t0 where HT(t) is the
relevant equivalent-dose rate in a tissue or organ at time t. For the
purposes of this part, the previously mentioned single intake may be
considered to be an annual intake.
IV. Annual Committed Effective Dose
If the committed equivalent doses to the individual tissues or
organs resulting from an annual intake are multiplied by the appropriate
weighting factors, wT, and then summed, the result will be the
annual committed effective dose, E():
[GRAPHIC] [TIFF OMITTED] TR20DE93.012
[58 FR 66415, Dec. 20, 1993]
Appendix C to Part 191--Guidance for Implementation of Subpart B
[Note: The supplemental information in this appendix is not an
integral part of 40 CFR part 191. Therefore, the implementing agencies
are not bound to follow this guidance. However, it is included because
it describes the Agency's assumptions regarding the implementation of
subpart B. This appendix will appear in the Code of Federal
Regulations.]
The Agency believes that the implementing agencies must determine
compliance with Secs. 191.13, 191.15, and 191.16 of subpart B by
evaluating long-term predictions of disposal system performance.
Determining compliance with Sec. 191.13 will also involve predicting the
likelihood of events and processes that may disturb the disposal system.
In making these various predictions, it will be appropriate for the
implementing agencies to make use of rather complex computational
models, analytical theories, and prevalent expert judgment relevant to
the numerical predictions. Substantial uncertainties are likely to be
encountered in making these predictions. In fact, sole reliance on these
numerical predictions to determine compliance may not be appropriate;
the implementing agencies may choose to supplement such predictions with
qualitative judgments as well. Because the procedures for determining
compliance with subpart B have not been formulated and tested yet, this
appendix to the rule indicates the Agency's assumptions regarding
certain issues that may arise when implementing Secs. 191.13, 191.15,
and 191.16. Most of this guidance applies to any type of disposal system
for the wastes covered by this rule. However, several sections apply
only to disposal in mined geologic repositories and would be
inappropriate for other types of disposal systems.
Consideration of Total Disposal System. When predicting disposal
system performance, the Agency assumes that reasonable projections of
the protection expected from all of the engineered and natural barriers
of a disposal system will be considered. Portions of the disposal system
should not be disregarded, even if projected performance is uncertain,
except for portions of the system that make negligible contributions to
the overall isolation provided by the disposal system.
Scope of Performance Assessments. Section 191.13 requires the
implementing agencies to evaluate compliance through performance
assessments as defined in Sec. 191.12(q). The Agency assumes that such
performance assessments need not consider categories of events or
processes that are estimated to have less than one chance in 10,000 of
occurring over 10,000 years. Furthermore, the performance assessments
need not evaluate in detail the releases from all events and processes
estimated to have a greater likelihood of occurrence. Some of these
events and processes may be omitted from the performance assessments if
there is a reasonable expectation that the remaining probability
distribution of cumulative releases would not be significantly changed
by such omissions.
Compliance with Sec. 191.13. The Agency assumes that, whenever
practicable, the implementing agency will assemble all of the results of
the performance assessments to determine compliance with Sec. 191.13
into a ``complementary cumulative distribution function'' that indicates
the probability of exceeding various levels of cumulative release. When
the uncertainties in parameters are considered in a performance
assessment, the effects of the uncertainties considered can be
incorporated into a single such distribution function for each disposal
system considered. The Agency assumes that a disposal system can be
considered to be in compliance with Sec. 191.13 if this single
distribution function meets the requirements of Sec. 191.13(a).
Compliance with Secs. 191.15 and 191.16. When the uncertainties in
undisturbed performance of a disposal system are considered, the
implementing agencies need not require that a very large percentage of
the range of estimated radiation exposures or radionuclide
concentrations fall below limits established
[[Page 17]]
in Secs. 191.15 and 191.16, respectively. The Agency assumes that
compliance can be determined based upon ``best estimate'' predictions
(e.g., the mean or the median of the appropriate distribution, whichever
is higher).
Institutional Controls. To comply with Sec. 191.14(a), the
implementing agency will assume that none of the active institutional
controls prevent or reduce radionuclide releases for more than 100 years
after disposal. However, the Federal Government is committed to
retaining ownership of all disposal sites for spent nuclear fuel and
high-level and transuranic radioactive wastes and will establish
appropriate markers and records, consistent with Sec. 191.14(c). The
Agency assumes that, as long as such passive institutional controls
endure and are understood, they: (1) Can be effective in deterring
systematic or persistent exploitation of these disposal sites; and (2)
can reduce the likelihood of inadvertent, intermittent human intrusion
to a degree to be determined by the implementing agency. However, the
Agency believes that passive institutional controls can never be assumed
to eliminate the chance of inadvertent and intermittent human intrusion
into these disposal sites.
Consideration of Inadvertent Human Intrusion into Geologic
Repositories. The most speculative potential disruptions of a mined
geologic repository are those associated with inadvertent human
intrusion. Some types of intrusion would have virtually no effect on a
repository's containment of waste. On the other hand, it is possible to
conceive of intrusions (involving widespread societal loss of knowledge
regarding radioactive wastes) that could result in major disruptions
that no reasonable repository selection or design precautions could
alleviate. The Agency believes that the most productive consideration of
inadvertent intrusion concerns those realistic possibilities that may be
usefully mitigated by repository design, site selection, or use of
passive controls (although passive institutional controls should not be
assumed to completely rule out the possibility of intrusion). Therefore,
inadvertent and intermittent intrusion by exploratory drilling for
resources (other than any provided by the disposal system itself) can be
the most severe intrusion scenario assumed by the implementing agencies.
Furthermore, the implementing agencies can assume that passive
institutional controls or the intruders' own exploratory procedures are
adequate for the intruders to soon detect, or be warned of, the
incompatibility of the area with their activities.
Frequency and Severity of Inadvertent Human Intrusion into Geologic
Repositories. The implementing agencies should consider the effects of
each particular disposal system's site, design, and passive
institutional controls in judging the likelihood and consequences of
such inadvertent exploratory drilling. However, the Agency assumes that
the likelihood of such inadvertent and intermittent drilling need not be
taken to be greater than 30 boreholes per square kilometer of repository
area per 10,000 years for geologic repositories in proximity to
sedimentary rock formations, or more than 3 boreholes per square
kilometer per 10,000 years for repositories in other geologic
formations. Furthermore, the Agency assumes that the consequences of
such inadvertent drilling need not be assumed to be more severe than:
(1) Direct release to the land surface of all the ground water in the
repository horizon that would promptly flow through the newly created
borehole to the surface due to natural lithostatic pressure--or (if
pumping would be required to raise water to the surface) release of 200
cubic meters of ground water pumped to the surface if that much water is
readily available to be pumped; and (2) creation of a ground water flow
path with a permeability typical of a borehole filled by the soil or
gravel that would normally settle into an open hole over time--not the
permeability of a carefully sealed borehole.
[50 FR 38084, Sept. 19, 1985. Redesignated and amended at 58 FR 66415,
Dec. 20, 1993]
PART 192--HEALTH AND ENVIRONMENTAL PROTECTION STANDARDS FOR URANIUM AND THORIUM MILL TAILINGS--Table of Contents
Subpart A--Standards for the Control of Residual Radioactive Materials
from Inactive Uranium Processing Sites
Sec.
192.00 Applicability.
192.01 Definitions.
192.02 Standards.
192.03 Monitoring.
192.04 Corrective Action.
Table 1 to Subpart A--Maximum Concentration of Constituents for
Groundwater Protection
Subpart B--Standards for Cleanup of Land and Buildings Contaminated with
Residual Radioactive Materials from Inactive Uranium Processing Sites
192.10 Applicability.
192.11 Definitions.
192.12 Standards.
Subpart C--Implementation
192.20 Guidance for implementation.
192.21 Criteria for applying supplemental standards.
192.22 Supplemental standards.
[[Page 18]]
192.23 Effective date.
Subpart D--Standards for Management of Uranium Byproduct Materials
Pursuant to Section 84 of the Atomic Energy Act of 1954, as Amended
192.30 Applicability.
192.31 Definitions and cross-references.
192.32 Standards.
192.33 Corrective action programs.
192.34 Effective date.
Table A to Subpart D
Subpart E--Standards for Management of Thorium Byproduct Materials
Pursuant to Section 84 of the Atomic Energy Act of 1954, as Amended
192.40 Applicability.
192.41 Provisions.
192.42 Substitute provisions.
192.43 Effective date.
Appendix I to Part 192--Listed Constituents
Authority: Sec. 275 of the Atomic Energy Act of 1954, 42 U.S.C.
2022, as added by the Uranium Mill Tailings Radiation Control Act of
1978, Pub. L. 95-604, as amended.
Source: 48 FR 602, Jan. 5, 1983, unless otherwise noted.
Subpart A--Standards for the Control of Residual Radioactive Materials
from Inactive Uranium Processing Sites
Sec. 192.00 Applicability.
This subpart applies to the control of residual radioactive material
at designated processing or depository sites under section 108 of the
Uranium Mill Tailings Radiation Control Act of 1978 (henceforth
designated ``the Act''), and to restoration of such sites following any
use of subsurface minerals under section 104(h) of the Act.
Sec. 192.01 Definitions.
(a) Residual radioactive material means:
(1) Waste (which the Secretary determines to be radioactive) in the
form of tailings resulting from the processing of ores for the
extraction of uranium and other valuable constituents of the ores; and
(2) Other wastes (which the Secretary determines to be radioactive)
at a processing site which relate to such processing, including any
residual stock of unprocessed ores or low-grade materials.
(b) Remedial action means any action performed under section 108 of
the Act.
(c) Control means any remedial action intended to stabilize, inhibit
future misuse of, or reduce emissions or effluents from residual
radioactive materials.
(d) Disposal site means the region within the smallest perimeter of
residual radioactive material (excluding cover materials) following
completion of control activities.
(e) Depository site means a site (other than a processing site)
selected under Section 104(b) or 105(b) of the Act.
(f) Curie (Ci) means the amount of radioactive material that
produces 37 billion nuclear transformation per second. One picocurie
(pCi) = 10 -12Ci.
(g) Act means the Uranium Mill Tailings Radiation Control Act of
1978, as amended.
(h) Administrator means the Administrator of the Environmental
Protection Agency.
(i) Secretary means the Secretary of Energy.
(j) Commission means the Nuclear Regulatory Commission.
(k) Indian tribe means any tribe, band, clan, group, pueblo, or
community of Indians recognized as eligible for services provided by the
Secretary of the Interior to Indians.
(l) Processing site means:
(1) Any site, including the mill, designated by the Secretary under
Section 102(a)(1) of the Act; and
(2) Any other real property or improvement thereon which is in the
vicinity of such site, and is determined by the Secretary, in
consultation with the Commission, to be contaminated with residual
radioactive materials derived from such site.
(m) Tailings means the remaining portion of a metal-bearing ore
after some or all of such metal, such as uranium, has been extracted.
(n) Disposal period means the period of time beginning March 7, 1983
and ending with the completion of all subpart A requirements specified
under a plan for remedial action except those specified in Sec. 192.03
and Sec. 192.04.
[[Page 19]]
(o) Plan for remedial action means a written plan (or plans) for
disposal and cleanup of residual radioactive materials associated with a
processing site that incorporates the results of site characterization
studies, environmental assessments or impact statements, and engineering
assessments so as to satisfy the requirements of subparts A and B of
this part. The plan(s) shall be developed in accordance with the
provisions of Section 108(a) of the Act with the concurrence of the
Commission and in consultation, as appropriate, with the Indian Tribe
and the Secretary of Interior.
(p) Post-disposal period means the period of time beginning
immediately after the disposal period and ending at termination of the
monitoring period established under Sec. 192.03.
(q) Groundwater means water below the ground surface in a zone of
saturation.
(r) Underground source of drinking water means an aquifer or its
portion:
(1)(i) Which supplies any public water system as defined in
Sec. 141.2 of this chapter; or
(ii) Which contains a sufficient quantity of groundwater to supply a
public water system; and
(A) Currently supplies drinking water for human consumption; or
(B) Contains fewer than 10,000 mg/l total dissolved solids; and
(2) Which is not an exempted aquifer as defined in Sec. 144.7 of
this chapter.
[48 FR 602, Jan. 5, 1983, as amended at 60 FR 2865, Jan. 11, 1995]
Sec. 192.02 Standards.
Control of residual radioactive materials and their listed
constituents shall be designed \1\ to:
---------------------------------------------------------------------------
\1\ Because the standard applies to design, monitoring after
disposal is not required to demonstrate compliance with respect to
Sec. 192.02(a) and (b).
---------------------------------------------------------------------------
(a) Be effective for up to one thousand years, to the extent
reasonably achievable, and, in any case, for at least 200 years, and,
(b) Provide reasonable assurance that releases of radon-222 from
residual radioactive material to the atmosphere will not:
(1) Exceed an average \2\ release rate of 20 picocuries per square
meter per second, or
---------------------------------------------------------------------------
\2\ This average shall apply over the entire surface of the disposal
site and over at least a one-year period. Radon will come from both
residual radioactive materials and from materials covering them. Radon
emissions from the covering materials should be estimated as part of
developing a remedial action plan for each site. The standard, however,
applies only to emissions from residual radioactive materials to the
atmosphere.
---------------------------------------------------------------------------
(2) Increase the annual average concentration of radon-222 in air at
or above any location outside the disposal site by more than one-half
picocurie per liter.
(c) Provide reasonable assurance of conformance with the following
groundwater protection provisions:
(1) The Secretary shall, on a site-specific basis, determine which
of the constituents listed in Appendix I to Part 192 are present in or
reasonably derived from residual radioactive materials and shall
establish a monitoring program adequate to determine background levels
of each such constituent in groundwater at each disposal site.
(2) The Secretary shall comply with conditions specified in a plan
for remedial action which includes engineering specifications for a
system of disposal designed to ensure that constituents identified under
paragraph (c)(1) of this section entering the groundwater from a
depository site (or a processing site, if residual radioactive materials
are retained on the site) will not exceed the concentration limits
established under paragraph (c)(3) of this section (or the supplemental
standards established under Sec. 192.22) in the uppermost aquifer
underlying the site beyond the point of compliance established under
paragraph (c)(4) of this section.
(3) Concentration limits:
(i) Concentration limits shall be determined in the groundwater for
listed constituents identified under paragraph (c)(1) of this section.
The concentration of a listed constituent in groundwater must not
exceed:
(A) The background level of that constituent in the groundwater; or
(B) For any of the constituents listed in Table 1 to subpart A, the
respective
[[Page 20]]
value given in that Table if the background level of the constituent is
below the value given in the Table; or
(C) An alternate concentration limit established pursuant to
paragraph (c)(3)(ii) of this section.
(ii)(A) The Secretary may apply an alternate concentration limit if,
after considering remedial or corrective actions to achieve the levels
specified in paragraphs (c)(3)(i)(A) and (B) of this section, he has
determined that the constituent will not pose a substantial present or
potential hazard to human health and the environment as long as the
alternate concentration limit is not exceeded, and the Commission has
concurred.
(B) In considering the present or potential hazard to human health
and the environment of alternate concentration limits, the following
factors shall be considered:
(1) Potential adverse effects on groundwater quality, considering:
(i) The physical and chemical characteristics of constituents in the
residual radioactive material at the site, including their potential for
migration;
(ii) The hydrogeological characteristics of the site and surrounding
land;
(iii) The quantity of groundwater and the direction of groundwater
flow;
(iv) The proximity and withdrawal rates of groundwater users;
(v) The current and future uses of groundwater in the region
surrounding the site;
(vi) The existing quality of groundwater, including other sources of
contamination and their cumulative impact on the groundwater quality;
(vii) The potential for health risks caused by human exposure to
constituents;
(viii) The potential damage to wildlife, crops, vegetation, and
physical structures caused by exposure to constituents;
(ix) The persistence and permanence of the potential adverse
effects;
(x) The presence of underground sources of drinking water and
exempted aquifers identified under Sec. 144.7 of this chapter; and
(2) Potential adverse effects on hydraulically-connected surface-
water quality, considering:
(i) The volume and physical and chemical characteristics of the
residual radioactive material at the site;
(ii) The hydrogeological characteristics of the site and surrounding
land;
(iii) The quantity and quality of groundwater, and the direction of
groundwater flow;
(iv) The patterns of rainfall in the region;
(v) The proximity of the site to surface waters;
(vi) The current and future uses of surface waters in the region
surrounding the site and any water quality standards established for
those surface waters;
(vii) The existing quality of surface water, including other sources
of contamination and their cumulative impact on surface water quality;
(viii) The potential for health risks caused by human exposure to
constituents;
(ix) The potential damage to wildlife, crops, vegetation, and
physical structures caused by exposure to constituents; and
(x) The persistence and permanence of the potential adverse effects.
(4) Point of compliance: The point of compliance is the location at
which the groundwater concentration limits of paragraph (c)(3) of this
section apply. The point of compliance is the intersection of a vertical
plane with the uppermost aquifer underlying the site, located at the
hydraulically downgradient limit of the disposal area plus the area
taken up by any liner, dike, or other barrier designed to contain the
residual radioactive material.
(d) Each site on which disposal occurs shall be designed and
stabilized in a manner that minimizes the need for future maintenance.
[60 FR 2865, Jan. 11, 1995]
Sec. 192.03 Monitoring.
A groundwater monitoring plan shall be implemented, to be carried
out over a period of time commencing upon completion of remedial actions
taken to comply with the standards in Sec. 192.02, and of a duration
which is adequate to demonstrate that future performance of the system
of disposal can reasonably be expected to be in accordance with the
design requirements of
[[Page 21]]
Sec. 192.02(c). This plan and the length of the monitoring period shall
be modified to incorporate any corrective actions required under
Sec. 192.04 or Sec. 192.12(c).
[60 FR 2866, Jan. 11, 1995]
Sec. 192.04 Corrective Action.
If the groundwater concentration limits established for disposal
sites under provisions of Sec. 192.02(c) are found or projected to be
exceeded, a corrective action program shall be placed into operation as
soon as is practicable, and in no event later than eighteen (18) months
after a finding of exceedance. This corrective action program will
restore the performance of the system of disposal to the original
concentration limits established under Sec. 192.02(c)(3), to the extent
reasonably achievable, and, in any case, as a minimum shall:
(a) Conform with the groundwater provisions of Sec. 192.02(c)(3),
and
(b) Clean up groundwater in conformance with subpart B, modified as
appropriate to apply to the disposal site.
[60 FR 2866, Jan. 11, 1995]
Table 1 to Subpart A.--Maximum Concentration of Constituents for
Groundwater Protection
------------------------------------------------------------------------
Constituent concentration \1\ Maximum
------------------------------------------------------------------------
Arsenic................................. 0.05
Barium.................................. 1.0
Cadmium................................. 0.01
Chromium................................ 0.05
Lead.................................... 0.05
Mercury................................. 0.002
Selenium................................ 0.01
Silver.................................. 0.05
Nitrate (as N).......................... 10.
Molybdenum.............................. 0.1
Combined radium-226 and radium-228...... 5 pCi/liter
Combined uranium-234 and uranium-238 \2\ 30 pCi/liter
Gross alpha-particle activity (excluding 15 pCi/liter
radon and uranium).
Endrin (1,2,3,4,10,10-hexachloro-6,7- 0.0002
exposy-1,4,4a,5,6,7,8,8a-octahydro-1,4-
endo,endo-5,8-dimethanonaphthalene).
Lindane (1,2,3,4,5,6- 0.004
hexachlorocyclohexane, gamma insomer).
Methoxychlor (1,1,1-trichloro-2,2'-bis(p- 0.1
methoxyphenylethane)).
Toxaphene (C10H10Cl6, technical 0.005
chlorinated camphene, 67-69 percent
chlorine).
2,4-D (2,4-dichlorophenoxyacetic acid).. 0.1
2,4,5-TP Silvex (2,4,5- 0.01
trichlorophenoxypropionic acid).
------------------------------------------------------------------------
\1\ Milligrams per liter, unless stated otherwise.
\2\ Where secular equilibrium obtains, this criterion will be satisfied
by a concentration of 0.044 milligrams per liter (0.044 mg/l). For
conditions of other than secular equilibrium, a corresponding value
may be derived and applied, based on the measured site-specific ratio
of the two isotopes of uranium.
[60 FR 2866, Jan. 11, 1995]
Subpart B--Standards for Cleanup of Land and Buildings Contaminated with
Residual Radioactive Materials from Inactive Uranium Processing Sites
Sec. 192.10 Applicability.
This subpart applies to land and buildings that are part of any
processing site designated by the Secretary of Energy under section 102
of the Act. section 101 of the Act, states, in part, that ``processing
site'' means--
(a) Any site, including the mill, containing residual radioactive
materials at which all or substantially all of the uranium was produced
for sale to any Federal agency prior to January 1, 1971, under a
contract with any Federal agency, except in the case of a site at or
near Slick Rock, Colorado, unless--
(1) Such site was owned or controlled as of Januray 1, 1978, or is
thereafter owned or controlled, by any Federal agency, or
(2) A license (issued by the (Nuclear Regulatory) Commission or its
predecessor agency under the Atomic Energy Act of 1954 or by a State as
permitted under section 274 of such Act) for the production at site of
any uranium or thorium product derived from ores is in effect on January
1, 1978, or is issued or renewed after such date; and
(b) Any other real property or improvement thereon which--
(1) Is in the vicinity of such site, and
(2) Is determined by the Secretary, in consultation with the
Commission, to be contaminated with residual radioactive materials
derived from such site.
[[Page 22]]
Sec. 192.11 Definitions.
(a) Unless otherwise indicated in this subpart, all terms shall have
the same meaning as defined in subpart A.
(b) Land means any surface or subsurface land that is not part of a
disposal site and is not covered by an occupiable building.
(c) Working Level (WL) means any combination of short-lived radon
decay products in one liter of air that will result in the ultimate
emission of alpha particles with a total energy of 130 billion electron
volts.
(d) Soil means all unconsolidated materials normally found on or
near the surface of the earth including, but not limited to, silts,
clays, sands, gravel, and small rocks.
(e) Limited use groundwater means groundwater that is not a current
or potential source of drinking water because (1) the concentration of
total dissolved solids is in excess of 10,000 mg/l, or (2) widespread,
ambient contamination not due to activities involving residual
radioactive materials from a designated processing site exists that
cannot be cleaned up using treatment methods reasonably employed in
public water systems, or (3) the quantity of water reasonably available
for sustained continuous use is less than 150 gallons per day. The
parameters for determining the quantity of water reasonably available
shall be determined by the Secretary with the concurrence of the
Commission.
[48 FR 602, Jan. 5, 1983, as amended at 60 FR 2866, Jan. 11, 1995]
Sec. 192.12 Standards.
Remedial actions shall be conducted so as to provide reasonable
assurance that, as a result of residual radioactive materials from any
designated processing site:
(a) The concentration of radium-226 in land averaged over any area
of 100 square meters shall not exceed the background level by more
than--
(1) 5 pCi/g, averaged over the first 15 cm of soil below the
surface, and
(2) 15 pCi/g, averaged over 15 cm thick layers of soil more than 15
cm below the surface.
(b) In any occupied or habitable building--
(1) The objective of remedial action shall be, and reasonable effort
shall be made to achieve, an annual average (or equivalent) radon decay
product concentration (including background) not to exceed 0.02 WL. In
any case, the radon decay product concentration (including background)
shall not exceed 0.03 WL, and
(2) The level of gamma radiation shall not exceed the background
level by more than 20 microroentgens per hour.
(c) The Secretary shall comply with conditions specified in a plan
for remedial action which provides that contamination of groundwater by
listed constituents from residual radioactive material at any designated
processing site (Sec. 192.01(1)) shall be brought into compliance as
promptly as is reasonably achievable with the provisions of
Sec. 192.02(c)(3) or any supplemental standards established under
Sec. 192.22. For the purposes of this subpart:
(1) A monitoring program shall be carried out that is adequate to
define backgroundwater quality and the areal extent and magnitude of
groundwater contamination by listed constituents from residual
radioactive materials (Sec. 192.02(c)(1)) and to monitor compliance with
this subpart. The Secretary shall determine which of the constituents
listed in Appendix I to part 192 are present in or could reasonably be
derived from residual radioactive material at the site, and
concentration limits shall be established in accordance with
Sec. 192.02(c)(3).
(2) (i) If the Secretary determines that sole reliance on active
remedial procedures is not appropriate and that cleanup of the
groundwater can be more reasonably accomplished in full or in part
through natural flushing, then the period for remedial procedures may be
extended. Such an extended period may extend to a term not to exceed 100
years if:
(A) The concentration limits established under this subpart are
projected to be satisfied at the end of this extended period,
(B) Institutional control, having a high degree of permanence and
which will effectively protect public health and the environment and
satisfy beneficial uses of groundwater during the
[[Page 23]]
extended period and which is enforceable by the administrative or
judicial branches of government entities, is instituted and maintained,
as part of the remedial action, at the processing site and wherever
contamination by listed constituents from residual radioactive materials
is found in groundwater, or is projected to be found, and
(C) The groundwater is not currently and is not now projected to
become a source for a public water system subject to provisions of the
Safe Drinking Water Act during the extended period.
(ii) Remedial actions on groundwater conducted under this subpart
may occur before or after actions under Section 104(f)(2) of the Act are
initiated.
(3) Compliance with this subpart shall be demonstrated through the
monitoring program established under paragraph (c)(1) of this section at
those locations not beneath a disposal site and its cover where
groundwater contains listed constituents from residual radioactive
material.
[48 FR 602, Jan. 5, 1983, as amended at 60 FR 2867, Jan. 11, 1995]
Subpart C--Implementation
Sec. 192.20 Guidance for implementation.
Section 108 of the Act requires the Secretary of Energy to select
and perform remedial actions with the concurrence of the Nuclear
Regulatory Commission and the full participation of any State that pays
part of the cost, and in consultation, as appropriate, with affected
Indian Tribes and the Secretary of the Interior. These parties, in their
respective roles under section 108, are referred to hereafter as ``the
implementing agencies.'' The implementing agencies shall establish
methods and procedures to provide ``reasonable assurance'' that the
provisions of Subparts A and B are satisfied. This should be done as
appropriate through use of analytic models and site-specific analyses,
in the case of Subpart A, and for Subpart B through measurements
performed within the accuracy of currently available types of field and
laboratory instruments in conjunction with reasonable survey and
sampling procedures. These methods and procedures may be varied to suit
conditions at specific sites. In particular:
(a)(1) The purpose of Subpart A is to provide for long-term
stabilization and isolation in order to inhibit misuse and spreading of
residual radioactive materials, control releases of radon to air, and
protect water. Subpart A may be implemented through analysis of the
physical properties of the site and the control system and projection of
the effects of natural processes over time. Events and processes that
could significantly affect the average radon release rate from the
entire disposal site should be considered. Phenomena that are localized
or temporary, such as local cracking or burrowing of rodents, need to be
taken into account only if their cumulative effect would be significant
in determining compliance with the standard. Computational models,
theories, and prevalent expert judgment may be used to decide that a
control system design will satisfy the standard. The numerical range
provided in the standard for the longevity of the effectiveness of the
control of residual radioactive materials allows for consideration of
the various factors affecting the longevity of control and stabilization
methods and their costs. These factors have different levels of
predictability and may vary for the different sites.
(2) Protection of water should be considered on a case-specific
basis, drawing on hydrological and geochemical surveys and all other
relevant data. The hydrologic and geologic assessment to be conducted at
each site should include a monitoring program sufficient to establish
background groundwater quality through one or more upgradient or other
appropriately located wells. The groundwater monitoring list in Appendix
IX of part 264 of this chapter (plus the additional constituents in
Table A of this paragraph) may be used for screening purposes in place
of Appendix I of part 192 in the monitoring program. New depository
sites for tailings that contain water at greater than the level of
``specific retention'' should use aliner or equivalent. In considering
design objectives for groundwater protection, the implementing agencies
should give priority to concentration levels in the
[[Page 24]]
order listed under Sec. 192.02(c)(3)(i). When considering the potential
for health risks caused by human exposure to known or suspected
carcinogens, alternate concentration limits pursuant to paragraph
192.02(c)(3)(ii) should be established at concentration levels which
represent an excess lifetime risk, at a point of exposure, to an average
individual no greater than between 10-4 and 10-6.
Table A to Sec. 192.20(a)(2)--Additional Listed Constituents
Nitrate (as N)
Molybdenum
Combined radium-226 and radium-228
Combined uranium-234 and uranium-238
Gross alpha-particle activity (excluding radon and uranium)
------------------------------------------------------------------------
(3) The plan for remedial action, concurred in by the Commission,
will specify how applicable requirements of subpart A are to be
satisfied. The plan should include the schedule and steps necessary to
complete disposal operations at the site. It should include an estimate
of the inventory of wastes to be disposed of in the pile and their
listed constituents and address any need to eliminate free liquids;
stabilization of the wastes to a bearing capacity sufficient to support
the final cover; and the design and engineering specifications for a
cover to manage the migration of liquids through the stabilized pile,
function without maintenance, promote drainage and minimize erosion or
abrasion of the cover, and accommodate settling and subsidence so that
cover integrity is maintained. Evaluation of proposed designs to conform
to subpart A should be based on realistic technical judgments and
include use of available empirical information. The consideration of
possible failure modes and related corrective actions should be limited
to reasonable failure assumptions, with a demonstration that the
disposal design is generally amenable to a range of corrective actions.
(4) The groundwater monitoring list in Appendix IX of part 264 of
this chapter (plus the additional constituents in Table A in paragraph
(a)(2) of this section) may be used for screening purposes in place of
Appendix I of part 192 in monitoring programs. The monitoring plan
required under Sec. 192.03 should be designed to include verification of
site-specific assumptions used to project the performance of the
disposal system. Prevention of contamination of groundwater may be
assessed by indirect methods, such as measuring the migration of
moisture in the various components of the cover, the tailings, and the
area between the tailings and the nearest aquifer, as well as by direct
monitoring of groundwater. In the case of vicinity properties
(Sec. 192.01(l)(2)), such assessments may not be necessary, as
determined by the Secretary, with the concurrence of the Commission,
considering such factors as local geology and the amount of
contamination present. Temporary excursions from applicable limits of
groundwater concentrations that are attributable to a disposal operation
itself shall not constitute a basis for considering corrective action
under Sec. 192.04 during the disposal period, unless the disposal
operation is suspended prior to completion for other than seasonal
reasons.
(b)(1) Compliance with Sec. 192.12(a) and (b) of subpart B, to the
extent practical, should be demonstrated through radiation surveys. Such
surveys may, if appropriate, be restricted to locations likely to
contain residual radioactive materials. These surveys should be designed
to provide for compliance averaged over limited areas rather than point-
by-point compliance with the standards. In most cases, measurement of
gamma radiation exposure rates above and below the land surface can be
used to show compliance with Sec. 192.12(a). Protocols for making such
measurements should be based on realistic radium distributions near the
surface rather than extremes rarely encountered.
(2) In Sec. 192.12(a), ``background level'' refers to the native
radium concentration in soil. Since this may not be determinable in the
presence of contamination by residual radioactive materials, a surrogate
``background level'' may be established by simple direct or indirect
(e.g., gamma radiation) measurements performed nearby but outside of the
contaminated location.
[[Page 25]]
(3) Compliance with Sec. 192.12(b) may be demonstrated by methods
that the Department of Energy has approved for use under Pub. L. 92-314
(10 CFR part 712), or by other methods that the implementing agencies
determine are adequate. Residual radioactive materials should be removed
from buildings exceeding 0.03 WL so that future replacement buildings
will not pose a hazard [unless removal is not practical--see
Sec. 192.21(c)]. However, sealants, filtration, and ventilation devices
may provide reasonable assurance of reductions from 0.03 WL to below
0.02 WL. In unusual cases, indoor radiation may exceed the levels
specified in Sec. 192.12(b) due to sources other than residual
radioactive materials. Remedial actions are not required in order to
comply with the standard when there is reasonable assurance that
residual radioactive materials are not the cause of such an excess.
(4) The plan(s) for remedial action will specify how applicable
requirements of subpart B would be satisfied. The plan should include
the schedule and steps necessary to complete the cleanup of groundwater
at the site. It should document the extent of contamination due to
releases prior to final disposal, including the identification and
location of listed constituents and the rate and direction of movement
of contaminated groundwater, based upon the monitoring carried out under
Sec. 192.12(c)(1). In addition, the assessment should consider future
plume movement, including an evaluation of such processes as attenuation
and dilution and future contamination from beneath a disposal site.
Monitoring for assessment and compliance purposes should be sufficient
to establish the extent and magnitude of contamination, with reasonable
assurance, through use of a carefully chosen minimal number of sampling
locations. The location and number of monitoring wells, the frequency
and duration of monitoring, and the selection of indicator analytes for
long-term groundwater monitoring, and, more generally, the design and
operation of the monitoring system, will depend on the potential for
risk to receptors and upon other factors, including characteristics of
the subsurface environment, such as velocity of groundwater flow,
contaminant retardation, time of groundwater or contaminant transit to
receptors, results of statistical evaluations of data trends, and
modeling of the dynamics of the groundwater system. All of these factors
should be incorporated into the design of a site-specific monitoring
program that will achieve the purpose of the regulations in this subpart
in the most cost-effective manner. In the case of vicinity properties
(Sec. 192.01(l)(2)), such assessments will usually not be necessary. The
Secretary, with the concurrence of the Commission, may consider such
factors as local geology and amount of contamination present in
determining criteria to decide when such assessments are needed. In
cases where Sec. 192.12(c)(2) is invoked, the plan should include a
monitoring program sufficient to verify projections of plume movement
and attenuation periodically during the extended cleanup period.
Finally, the plan should specify details of the method to be used for
cleanup of groundwater.
[48 FR 602, Jan. 5, 1983, as amended at 60 FR 2867, Jan. 11, 1995]
Sec. 192.21 Criteria for applying supplemental standards.
Unless otherwise indicated in this subpart, all terms shall have the
same meaning as defined in Title I of the Act or in subparts A and B.
The implementing agencies may (and in the case of paragraph (h) of this
section shall) apply standards under Sec. 192.22 in lieu of the
standards of subparts A or B if they determine that any of the following
circumstances exists:
(a) Remedial actions required to satisfy subpart A or B would pose a
clear and present risk of injury to workers or to members of the public,
notwithstanding reasonable measures to avoid or reduce risk.
(b) Remedial actions to satisfy the cleanup standards for land,
Sec. 192.12(a), and groundwater, Sec. 192.12(c), or the acquisition of
minimum materials required for control to satisfy Secs. 192.02(b) and
(c), would, notwithstanding reasonable measures to limit damage,
directly produce health and environmental harm that is clearly excessive
[[Page 26]]
compared to the health and environmental benefits, now or in the future.
A clear excess of health and environmental harm is harm that is long-
term, manifest, and grossly disproportionate to health and environmental
benefits that may reasonably be anticipated.
(c) The estimated cost of remedial action to satisfy Sec. 192.12(a)
at a ``vicinity'' site (described under section 101(6)(B) of the Act) is
unreasonably high relative to the long-term benefits, and the residual
radioactive materials do not pose a clear present or future hazard. The
likelihood that buildings will be erected or that people will spend long
periods of time at such a vicinity site should be considered in
evaluating this hazard. Remedial action will generally not be necessary
where residual radioactive materials have been placed semi-permanently
in a location where site-specific factors limit their hazard and from
which they are costly or difficult to remove, or where only minor
quantities of residual radioactive materials are involved. Examples are
residual radioactive materials under hard surface public roads and
sidewalks, around public sewer lines, or in fence post foundations.
Supplemental standards should not be applied at such sites, however, if
individuals are likely to be exposed for long periods of time to
radiation from such materials at levels above those that would prevail
under Sec. 192.12(a).
(d) The cost of a remedial action for cleanup of a building under
Sec. 192.12(b) is clearly unreasonably high relative to the benefits.
Factors that should be included in this judgment are the anticipated
period of occupancy, the incremental radiation level that would be
affected by the remedial action, the residual useful lifetime of the
building, the potential for future construction at the site, and the
applicability of less costly remedial methods than removal of residual
radioactive materials.
(e) There is no known remedial action.
(f) The restoration of groundwater quality at any designated
processing site under Sec. 192.12(c) is technically impracticable from
an engineering perspective.
(g) The groundwater meets the criteria of Sec. 192.11(e).
(h) Radionuclides other than radium-226 and its decay products are
present in sufficient quantity and concentration to constitute a
significant radiation hazard from residual radioactive materials.
[48 FR 602, Jan. 5, 1983, as amended at 60 FR 2868, Jan. 11, 1995]
Sec. 192.22 Supplemental standards.
Federal agencies implementing subparts A and B may in lieu thereof
proceed pursuant to this section with respect to generic or individual
situations meeting the eligibility requirements of Sec. 192.21.
(a) When one or more of the criteria of Sec. 192.21(a) through (g)
applies, the Secretary shall select and perform that alternative
remedial action that comes as close to meeting the otherwise applicable
standard under Sec. 192.02(c)(3) as is reasonably achievable.
(b) When Sec. 192.21(h) applies, remedial actions shall reduce other
residual radioactivity to levels that are as low as is reasonably
achievable and conform to the standards of subparts A and B to the
maximum extent practicable.
(c) The implementing agencies may make general determinations
concerning remedial actions under this section that will apply to all
locations with specified characteristics, or they may make a
determination for a specific location. When remedial actions are
proposed under this section for a specific location, the Department of
Energy shall inform any private owners and occupants of the affected
location and solicit their comments. The Department of Energy shall
provide any such comments to the other implementing agencies. The
Department of Energy shall also periodically inform the Environmental
Protection Agency of both general and individual determinations under
the provisions of this section.
(d) When Sec. 192.21(b), (f), or (g) apply, implementing agencies
shall apply any remedial actions for the restoration of contamination of
groundwater by residual radioactive materials that is required to
assure, at a minimum, protection of human health and the environment. In
addition, when Sec. 192.21(g) applies, supplemental standards shall
ensure that current and reasonably
[[Page 27]]
projected uses of the affected groundwater are preserved.
[48 FR 602, Jan. 5, 1983, as amended at 60 FR 2868, Jan. 11, 1995]
Sec. 192.23 Effective date.
Subparts A, B, and C shall be effective March 7, 1983.
Subpart D--Standards for Management of Uranium Byproduct Materials
Pursuant to Section 84 of the Atomic Energy Act of 1954, as Amended
Source: 48 FR 45946, Oct. 7, 1983, unless otherwise noted.
Sec. 192.30 Applicability.
This subpart applies to the management of uranium byproduct
materials under section 84 of the Atomic Energy Act of 1954 (henceforth
designated ``the Act''), as amended, during and following processing of
uranium ores, and to restoration of disposal sites following any use of
such sites under section 83(b)(1)(B) of the Act.
Sec. 192.31 Definitions and cross-references.
References in this subpart to other parts of the Code of Federal
Regulations are to those parts as codified on January 1, 1983.
(a) Unless otherwise indicated in this subpart, all terms shall have
the same meaning as in Title II of the Uranium Mill Tailings Rediation
Control Act of 1978, subparts A and B of this part, or parts 190, 260,
261, and 264 of this chapter. For the purposes of this subpart, the
terms ``waste,'' ``hazardous waste,'' and related terms, as used in
parts 260, 261, and 264 of this chapter shall apply to byproduct
material.
(b) Uranium byproduct material means the tailings or wastes produced
by the extraction or concentration of uranium from any ore processed
primarily for its source material content. Ore bodies depleted by
uranium solution extraction operations and which remain underground do
not constitute ``byproduct material'' for the purpose of this subpart.
(c) Control means any action to stabilize, inhibit future misuse of,
or reduce emissions or effluents from uranium byproduct materials.
(d) Licensed site means the area contained within the boundary of a
location under the control of persons generating or storing uranium
byproduct materials under a license issued pursuant to section 84 of the
Act. For purposes of this subpart, ``licensed site'' is equivalent to
``regulated unit'' in subpart F of part 264 of this chapter.
(e) Disposal site means a site selected pursuant to section 83 of
the Act.
(f) Disposal area means the region within the perimeter of an
impoundment or pile containing uranium by product materials to which the
post-closure requirements of Sec. 192.32(b)(1) of this subpart apply.
(g) Regulatory agency means the U.S. Nuclear Regulatory Commission.
(h) Closure period means the period of time beginning with the
cessation, with respect to a waste impoundment, of uranium ore
processing operations and ending with completion of requirements
specified under a closure plan.
(i) Closure plan means the plan required under Sec. 264.112 of this
chapter.
(j) Existing portion means that land surface area of an existing
surface impoundment on which significant quantities of uranium byproduct
materials have been placed prior to promulgation of this standard.
(k) As expeditiously as practicable considering technological
feasibility means as quickly as possible considering: the physical
characteristics of the tailings and the site; the limits of available
technology; the need for consistency with mandatory requirements of
other regulatory programs; and factors beyond the control of the
licensee. The phrase permits consideration of the cost of compliance
only to the extent specifically provided for by use of the term
``available technology.''
(l) Permanent Radon Barrier means the final radon barrier
constructed to achieve compliance with, including attainment of, the
limit on releases of radon-222 in Sec. 192.32(b)(1)(ii).
(m) Available technology means technologies and methods for
emplacing a permanent radon barrier on uranium mill tailings piles or
impoundments.
[[Page 28]]
This term shall not be construed to include extraordinary measures or
techniques that would impose costs that are grossly excessive as
measured by practice within the industry or one that is reasonably
analogous, (such as, by way of illustration only, unreasonable overtime,
staffing or transportation requirements, etc., considering normal
practice in the industry; laser fusion, of soils, etc.), provided there
is reasonable progress toward emplacement of a permanent radon barrier.
To determine grossly excessive costs, the relevant baseline against
which cost increases shall be compared is the cost estimate for tailings
impoundment closure contained in the licensee's tailings closure plan,
but costs beyond such estimates shall not automatically be considered
grossly excessive.
(n) Tailings Closure Plan (Radon) means the Nuclear Regulatory
Commission or Agreement State approved plan detailing activities to
accomplish timely emplacement of a permanent radon barrier. A tailings
closure plan shall include a schedule for key radon closure milestone
activities such as wind blown tailings retrieval and placement on the
pile, interim stabilization (including dewatering or the removal of
freestanding liquids and recontouring), and emplacement of a permanent
radon barrier constructed to achieve compliance with the 20 pCi/
m2-s flux standard as expeditiously as practicable considering
technological feasibility (including factors beyond the control of the
licensee).
(o) Factors beyond the control of the licensee means factors
proximately causing delay in meeting the schedule in the applicable
license for timely emplacement of the permanent radon barrier
notwithstanding the good faith efforts of the licensee to achieve
compliance. These factors may include, but are not limited to, physical
conditions at the site; inclement weather or climatic conditions; an act
of God; an act of war; a judicial or administrative order or decision,
or change to the statutory, regulatory, or other legal requirements
applicable to the licensee's facility that would preclude or delay the
performance of activities required for compliance; labor disturbances;
any modifications, cessation or delay ordered by state, Federal or local
agencies; delays beyond the time reasonably required in obtaining
necessary governmental permits, licenses, approvals or consent for
activities described in the tailings closure plan (radon) proposed by
the licensee that result from agency failure to take final action after
the licensee has made a good faith, timely effort to submit legally
sufficient applications, responses to requests (including relevant data
requested by the agencies), or other information, including approval of
the tailings closure plan by NRC or the affected Agreement State; and an
act or omission of any third party over whom the licensee has no
control.
(p) Operational means that a uranium mill tailings pile or
impoundment is being used for the continued placement of uranium
byproduct material or is in standby status for such placement. A
tailings pile or impoundment is operational from the day that uranium
byproduct material is first placed in the pile or impoundment until the
day final closure begins.
(q) Milestone means an enforceable date by which action, or the
occurrence of an event, is required for purposes of achieving compliance
with the 20 pCi/m\2\-s flux standard.
[48 FR 45946, Oct. 7, 1983, as amended at 58 FR 60355, Nov. 15, 1993]
Sec. 192.32 Standards.
(a) Standards for application during processing operations and prior
to the end of the closure period. (1) Surface impoundments (except for
an existing portion) subject to this subpart must be designed,
constructed, and installed in such manner as to conform to the
requirements of Sec. 264.221 of this chapter, except that at sites where
the annual precipitation falling on the impoundment and any drainage
area contributing surface runoff to the impoundment is less than the
annual evaporation from the impoundment, the requirements of
Sec. 264.228(a)(2) (iii)(E) referenced in Sec. 264.221 do not apply.
(2) Uranium byproduct materials shall be managed so as to conform to
the ground water protection standard in Sec. 264.92 of this chapter,
except that for the purposes of this subpart:
[[Page 29]]
(i) To the list of hazardous constituents referenced in Sec. 264.93
of this chapter are added the chemical elements molybdenum and uranium,
(ii) To the concentration limits provided in Table 1 of Sec. 264.94
of this chapter are added the radioactivity limits in Table A of this
subpart,
(iii) Detection monitoring programs required under Sec. 264.98 to
establish the standards required under Sec. 264.92 shall be completed
within one (1) year of promulgation,
(iv) The regulatory agency may establish alternate concentration
limits (to be satisfied at the point of compliance specified under
Sec. 264.95) under the criteria of Sec. 264.94(b), provided that, after
considering practicable corrective actions, these limits are as low as
reasonably achievable, and that, in any case, the standards of
Sec. 264.94(a) are satisfied at all points at a greater distance than
500 meters from the edge of the disposal area and/or outside the site
boundary, and
(v) The functions and responsibilities designated in Part 264 of
this chapter as those of the ``Regional Administrator'' with respect to
``facility permits'' shall be carried out by the regulatory agency,
except that exemptions of hazardous constituents under Sec. 264.93 (b)
and (c) of this chapter and alternate concentration limits established
under Sec. 264.94 (b) and (c) of this chapter (except as otherwise
provided in Sec. 192.32(a)(2)(iv)) shall not be effective until EPA has
concurred therein.
(3)(i) Uranium mill tailings piles or impoundments that are
nonoperational and subject to a license by the Nuclear Regulatory
Commission or an Agreement State shall limit releases of radon-222 by
emplacing a permanent radon barrier. This permanent radon barrier shall
be constructed as expeditiously as practicable considering technological
feasibility (including factors beyond the control of the licensee) after
the pile or impoundment ceases to be operational. Such control shall be
carried out in accordance with a written tailings closure plan (radon)
to be incorporated by the Nuclear Regulatory Commission or Agreement
State into individual site licenses.
(ii) The Nuclear Regulatory Commission or Agreement State may
approve a licensee's request to extend the time for performance of
milestones if, after providing an opportunity for public participation,
the Nuclear Regulatory Commission or Agreement State finds that
compliance with the 20 pCi/m\2\-s flux standard has been demonstrated
using a method approved by the NRC, in the manner required in
192.32(a)(4)(i). Only under these circumstances and during the period of
the extension must compliance with the 20 pCi/m\2\-s flux standard be
demonstrated each year.
(iii) The Nuclear Regulatory Commission or Agreement State may
extend the final compliance date for emplacement of the permanent radon
barrier, or relevant milestone, based upon cost if the new date is
established after a finding by the Nuclear Regulatory Commission or
Agreement State, after providing an opportunity for public
participation, that the licensee is making good faith efforts to emplace
a permanent radon barrier; the delay is consistent with the definition
of ``available technology'' in Sec. 192.31(m); and the delay will not
result in radon releases that are determined to result in significant
incremental risk to the public health.
(iv) The Nuclear Regulatory Commission or Agreement State may, in
response to a request from a licensee, authorize by license or license
amendment a portion of the site to remain accessible during the closure
process to accept uranium byproduct material as defined in section
11(e)(2) of the Atomic Energy Act, 42 U.S.C. 2014(e)(2), or to accept
materials similar to the physical, chemical and radiological
characteristics of the in situ uranium mill tailings and associated
wastes, from other sources. No such authorization may be used as a means
for delaying or otherwise impeding emplacement of the permanent radon
barrier over the remainder of the pile or impoundment in a manner that
will achieve compliance with the 20 pCi/m\2\-s flux standard, averaged
over the entire pile or impoundment.
[[Page 30]]
(v) The Nuclear Regulatory Commission or Agreement State may, in
response to a request from a licensee, authorize by license or license
amendment a portion of a pile or impoundment to remain accessible after
emplacement of a permanent radon barrier to accept uranium byproduct
material as defined in section 11(e)(2) of the Atomic Energy Act, 42
U.S.C. 2014(e)(2), if compliance with the 20 pCi/m\2\-s flux standard of
Sec. 192.32(b)(1)(ii) is demonstrated by the licensee's monitoring
conducted in a manner consistent with Sec. 192.32(a)(4)(i). Such
authorization may be provided only if the Nuclear Regulatory Commission
or Agreement State makes a finding, constituting final agency action and
after providing an opportunity for public participation, that the site
will continue to achieve the 20 pCi/m2-s flux standard when averaged
over the entire impoundment.
(4)(i) Upon emplacement of the permanent radon barrier pursuant to
40 CFR 192.32(a)(3), the licensee shall conduct appropriate monitoring
and analysis of the radon-222 releases to demonstrate that the design of
the permanent radon barrier is effective in limiting releases of radon-
222 to a level not exceeding 20 pCi/m\2\-s as required by 40 CFR
192.32(b)(1)(ii). This monitoring shall be conducted using the
procedures described in 40 CFR part 61, Appendix B, Method 115, or any
other measurement method proposed by a licensee that the Nuclear
Regulatory Commission or Agreement State approves as being at least as
effective as EPA Method 115 in demonstrating the effectiveness of the
permanent radon barrier in achieving compliance with the 20 pCi/m\2\-s
flux standard.
(ii) When phased emplacement of the permanent radon barrier is
included in the applicable tailings closure plan (radon), then radon
flux monitoring required under Sec. 192.32(a)(4)(i) shall be conducted,
however the licensee shall be allowed to conduct such monitoring for
each portion of the pile or impoundment on which the radon barrier has
been emplaced by conducting flux monitoring on the closed portion.
(5) Uranium byproduct materials shall be managed so as to conform to
the provisions of:
(i) Part 190 of this chapter, ``Environmental Radiation Protection
Standards for Nuclear Power Operations'' and
(ii) Part 440 of this chapter, ``Ore Mining and Dressing Point
Source Category: Effluent Limitations Guidelines and New Source
Performance Standards, Subpart C, Uranium, Radium, and Vanadium Ores
Subcategory.''
(6) The regulatory agency, in conformity with Federal Radiation
Protection Guidance (FR, May 18, 1960, pgs. 4402-4403), shall make every
effort to maintain radiation doses from radon emissions from surface
impoundments of uranium byproduct materials as far below the Federal
Radiation Protection Guides as is practicable at each licensed site.
(b) Standards for application after the closure period. At the end
of the closure period:
(1) Disposal areas shall each comply with the closure performance
standard in Sec. 264.111 of this chapter with respect to nonradiological
hazards and shall be designed1 to provide reasonable assurance of
control of radiological hazards to
---------------------------------------------------------------------------
\1\ The standard applies to design with a monitoring requirement as
specified in Sec. 192.32(a)(4).
---------------------------------------------------------------------------
(i) Be effective for one thousand years, to the extent reasonably
achievable, and, in any case, for at least 200 years, and,
(ii) Limit releases of radon-222 from uranium byproduct materials to
the atmosphere so as to not exceed an average2 release rate of 20
picocuries per square meter per second (pCi/m2s).
---------------------------------------------------------------------------
\2\ This average shall apply to the entire surface of each disposal
area over periods of at least one year, but short compared to 100 years.
Radon will come from both uranium byproduct materials and from covering
materials. Radon emissions from covering materials should be estimated
as part of developing a closure plan for each site. The standard,
however, applies only to emissions from uranium byproduct materials to
the atmosphere.
---------------------------------------------------------------------------
(2) The requirements of Sec. 192.32(b)(1) shall not apply to any
portion of a licensed and/or disposal site which contains a
concentration of radium-226 in land, averaged over areas of 100 square
meters, which, as a result of uranium
[[Page 31]]
byproduct material, does not exceed the background level by more than:
(i) 5 picocuries per gram (pCi/g), averaged over the first 15
centimeters (cm) below the surface, and
(ii) 15 pCi/g, averaged over 15 cm thick layers more than 15 cm
below the surface.
[48 FR 45946, Oct. 7, 1983, as amended at 58 FR 60355-60356, Nov. 15,
1993]
Sec. 192.33 Corrective action programs.
If the ground water standards established under provisions of
Sec. 192.32(a)(2) are exceeded at any licensed site, a corrective action
program as specified in Sec. 264.100 of this chapter shall be put into
operation as soon as is practicable, and in no event later than eighteen
(18) months after a finding of exceedance.
Sec. 192.34 Effective date.
Subpart D shall be effective December 6, 1983.
Table A to Subpart D
------------------------------------------------------------------------
pCi/liter
------------------------------------------------------------------------
Combined radium-226 and radium-228........................... 5
Gross alpha-particle activity (excluding radon and uranium).. 15
------------------------------------------------------------------------
Subpart E--Standards for Management of Thorium Byproduct Materials
Pursuant to Section 84 of the Atomic Energy Act of 1954, as Amended
Source: 48 FR 45947, Oct. 7, 1983, unless otherwise noted.
Sec. 192.40 Applicability.
This subpart applies to the management of thorium byproduct
materials under section 84 of the Atomic Energy Act of 1954, as amended,
during and following processing of thorium ores, and to restoration of
disposal sites following any use of such sites under section 83(b)(1)(B)
of the Act.
Sec. 192.41 Provisions.
Except as otherwise noted in Sec. 192.41(e), the provisions of
subpart D of this part, including Secs. 192.31, 192.32, and 192.33,
shall apply to thorium byproduct material and:
(a) Provisions applicable to the element uranium shall also apply to
the element thorium;
(b) Provisions applicable to radon-222 shall also apply to radon-
220; and
(c) Provisions applicable to radium-226 shall also apply to radium-
228.
(d) Operations covered under Sec. 192.32(a) shall be conducted in
such a manner as to provide reasonable assurance that the annual dose
equivalent does not exceed 25 millirems to the whole body, 75 millirems
to the thyroid, and 25 millirems to any other organ of any member of the
public as a result of exposures to the planned discharge of radioactive
materials, radon-220 and its daughters excepted, to the general
environment.
(e) The provisions of Sec. 192.32(a) (3) and (4) do not apply to the
management of thorium byproduct material.
[48 FR 45946, Oct. 7, 1983, as amended at 58 FR 60356, Nov. 15, 1993]
Sec. 192.42 Substitute provisions.
The regulatory agency may, with the concurrence of EPA, substitute
for any provisions of Sec. 192.41 of this subpart alternative provisions
it deems more practical that will provide at least an equivalent level
of protection for human health and the environment.
Sec. 192.43 Effective date.
Subpart E shall be effective December 6, 1983.
Appendix I to Part 192--Listed Constituents
Acetonitrile
Acetophenone (Ethanone, 1-phenyl)
2-Acetylaminofluorene (Acetamide, N-9H-fluoren-2-yl-)
Acetyl chloride
1-Acetyl-2-thiourea (Acetamide, N-(aminothioxymethyl)-)
Acrolein (2-Propenal)
Acrylamide (2-Propenamide)
Acrylonitrile (2-Propenenitrile)
Aflatoxins
Aldicarb (Propenal, 2-methyl-2-(methylthio)-,O-
[(methylamino)carbonyl]oxime
Aldrin (1,4:5,8-Dimethanonaphthalene, 1,2,3,4,10,10-hexachloro-
1,4,4a,5,8,8a-
hexahydro(1,4,4a,5,8,8
)-)
Allyl alcohol (2-Propen-1-ol)
Allyl chloride (1-Propane,3-chloro)
Aluminum phosphide
4-Aminobiphenyl ([1,1'-Biphenyl]-4-amine)
[[Page 32]]
5-(Aminomethyl)-3-isoxazolol (3(2H)-Isoxazolone,5-(aminomethyl)-)
4-Aminopyridine (4-Pyridineamine)
Amitrole (lH-1,2,4-Triazol-3-amine)
Ammonium vanadate (Vanadic acid, ammonium salt)
Aniline (Benzenamine)
Antimony and compounds, N.O.S.\1\
---------------------------------------------------------------------------
\1\ The abbreviation N.O.S. (not otherwise specified) signifies
those members of the general class not specifically listed by name in
this appendix.
---------------------------------------------------------------------------
Aramite (Sulfurous acid, 2-chloroethyl 2-[4-(1,1-dimethylethyl)phenoxy]-
1-methylethyl ester)
Arsenic and compounds, N.O.S.
Arsenic acid (Arsenic acid H3AsO4)
Arsenic pentoxide (Arsenic oxide As2O5)
Auramine (Benzamine, 4,4'-carbonimidoylbis[N,N-dimethyl-])
Azaserine (L-Serine, diazoacetate (ester))
Barium and compounds, N.O.S.
Barium cyanide
Benz[c]acridine (3,4-Benzacridine)
Benz[a]anthracene (1,2-Benzanthracene)
Benzal chloride (Benzene, dichloromethyl-)
Benzene (Cyclohexatriene)
Benzenearsonic acid (Arsenic acid, phenyl-)
Benzidine ([1,1'-Biphenyl]-4,4'-diamine)
Benzo[b]fluoranthene (Benz[e]acephananthrylene)
Benzo[j]fluoranthene
Benzo[k]fluoranthene
Benzo[a]pyrene
p-Benzoquinone (2,5-Cyclohexadiene-1,4-dione)
Benzotrichloride (Benzene, (trichloro-
methyl)-)
Benzyl chloride (Benzene, (chloromethyl)-)
Beryllium and compounds, N.O.S.
Bromoacetone (2-Propanone, 1-bromo-)
Bromoform (Methane, tribromo-)
4-Bromophenyl phenyl ether (Benzene, l-bromo-4-phenoxy-)
Brucine (Strychnidin-10-one, 2,3-dimeth-
oxy-)
Butyl benzyl phthalate (1,2-Benzenedicarbozylic acid, butyl phenylmethyl
ester)
Cacodylic acid (Arsinic acid, dimethyl)
Cadmium and compounds, N.O.S.
Calcium chromate (Chromic acid H2CrO4, calcium salt)
Calcium cyanide (Ca(CN)2)
Carbon disulfide
Carbon oxyfluoride (Carbonic difluoride)
Carbon tetrachloride (Methane, tetrachloro-)
Chloral (Acetaldehyde, trichloro-)
Chlorambucil (Benzenebutanoic acid, 4-[bis(2-chloroethyl)amino]-)
Chlordane (4,7-Methano-1H-indene,1,2,4,5,6,7,8,8-octachloro-
2,3,3a,4,7,7a-hexahydro-)
Chlorinated benzenes, N.O.S.
Chlorinated ethane, N.O.S.
Chlorinated fluorocarbons, N.O.S.
Chlorinated naphthalene, N.O.S.
Chlorinated phenol, N.O.S.
Chlornaphazin (Naphthalenamine, N,N'-bis(2-chlorethyl)-)
Chloroacetaldehyde (Acetaldehyde, chloro-)
Chloroalkyl ethers, N.O.S.
p-Chloroaniline (Benzenamine, 4-chloro-)
Chlorobenzene (Benzene, chloro-)
Chlorobenzilate (Benzeneacetic acid, 4-chloro--(4-
chlorophenyl)--hydroxy-, ethyl ester)
p-Chloro-m-cresol (Phenol, 4-chloro-3-methyl)
2-Chloroethyl vinyl ether (Ethene, (2-chloroethoxy)-)
Chloroform (Methane, trichloro-)
Chloromethyl methyl ether (Methane, chloromethoxy-)
-Chloronapthalene (Naphthalene, 2-chloro-)
o-Chlorophenol (Phenol, 2-chloro-)
1-(o-Chlorophenyl)thiourea (Thiourea, (2-chlorophenyl-))
3-Chloropropionitrile (Propanenitrile, 3-chloro-)
Chromium and compounds, N.O.S.
Chrysene
Citrus red No. 2 (2-Naphthalenol, 1-[(2,5-dimethoxyphenyl)azo]-)
Coal tar creosote
Copper cyanide (CuCN)
Creosote
Cresol (Chresylic acid) (Phenol, methyl-)
Crotonaldehyde (2-Butenal)
Cyanides (soluble salts and complexes), N.O.S.
Cyanogen (Ethanedinitrile)
Cyanogen bromide ((CN)Br)
Cyanogen chloride ((CN)Cl)
Cycasin (beta-D-Glucopyranoside, (methyl-ONN-azoxy)methyl)
2-Cyclohexyl-4,6-dinitrophenol (Phenol, 2-cyclohexyl-4,6-dinitro-)
Cyclophosphamide (2H-1,3,2-Oxazaphosphorin-2-amine,N,N-bis(2-
chloroethyl)
tetrahydro-,2-oxide)
2,4-D and salts and esters (Acetic acid, (2,4-dichlorophenoxy)-)
Daunomycin (5,12-Naphthacenedione,8-acetyl-10-[(3-amino-2,3,6-trideoxy-
-Llyxo-hexopyranosyl)oxy]-7,8,9,10-tetrahydro-6,8,11-
trihydroxy-1-methoxy-,(8S-cis))
DDD (Benzene, 1,1'-(2,2-dichloroethylidene)bis[4-chloro-)
DDE (Benzene, 1,1-(dichloroethylidene)bis[4-chloro-)
DDT (Benzene, 1,1'-(2,2,2-trichloroethlyidene)bis[4-chloro-)
Diallate (Carbomothioic acid, bis(1-methylethyl)-,S-(2,3-dichloro-2-
propenyl) ester)
Dibenz[a,h]acridine
Dibenz[a,j]acridine
Dibenz[a,h]anthracene
7H-Dibenzo[c,g]carbazole
[[Page 33]]
Dibenzo[a,e]pyrene (Naphtho[1,2,4,5-def)crysene)
Dibenzo[a,h]pyrene (Dibenzo[b,def]crysene)
Dibenzo[a,i]pyrene (Benzo[rst]pentaphene)
1,2-Dibromo-3-chloropropane (Propane, 1,2-dibromo-3-chloro-)
Dibutylphthalate (1,2-Benzenedicarboxylic acid, dibutyl ester)
o-Dichlorobenzene (Benzene, 1,2-dichloro-)
m-Dichlorobenzene (Benzene, 1,3-dichloro-)
p-Dichlorobenzene (Benzene, 1,4-dichloro-)
Dichlorobenzene, N.O.S. (Benzene; dichloro-, N.O.S.)
3,3'-Dichlorobenzidine ([1,1'-Biphenyl]-4,4'-diamine, 3,3'-dichloro-)
1,4-Dichloro-2-butene (2-Butene, 1,4-dichloro-)
Dichlorodifluoromethane (Methane, dichlorodifluoro-)
Dichloroethylene, N.O.S.
1,1-Dichloroethylene (Ethene, 1,1-dichloro-)
1,2-Dichloroethylene (Ethene, 1,2-dichloro-,(E)-)
Dichloroethyl ether (Ethane, 1,1'-oxybis[2-chloro-)
Dichloroisopropyl ether (Propane, 2,2'-oxybis[2-chloro-)
Dichloromethoxy ethane (Ethane, 1,1'-[methylenebis(oxy)bis[2-chloro-)
Dichloromethyl ether (Methane, oxybis[chloro-)
2,4-Dichlorophenol (Phenol, 2,4-dichloro-)
2,6-Dichlorophenol (Phenol, 2,6-dichloro-)
Dichlorophenylarsine (Arsinous dichloride, phenyl-)
Dichloropropane, N.O.S. (Propane,
dichloro-,)
Dichloropropanol, N.O.S. (Propanol, dichloro-,)
Dichloropropene; N.O.S. (1-Propane, dichloro-,)
1,3-Dichloropropene (1-Propene, 1,3-dichloro-)
Dieldrin (2,7:3,6-Dimethanonaphth[2,3-b]oxirene,3,4,5,6,9,9-hexachloro-
1a,2,2a,3,6,6a,7,7a,octahydro-
,(1a,2,2a,3,6,6a,7
,7a)-)
1,2:3,4-Diepoxybutane (2,2'-Bioxirane)
Diethylarsine (Arsine, diethyl-)
1,4 Diethylene oxide (1,4-Dioxane)
Diethylhexyl phthalate (1,2-Benzenedicarboxlyic acid, bis(2-ethylhexl)
ester)
N,N-Diethylhydrazine (Hydrazine, 1,2-diethyl)
O,O-Diethyl S-methyl dithiophosphate (Phosphorodithioic acid, O,O-
diethyl S-methyl ester)
Diethyl-p-nitrophenyl phosphate (Phosphoric acid, diethyl 4-nitrophenyl
ester)
Diethyl phthalate (1,2-Benzenedicarboxylic acid, diethyl ester)
O,O-Diethyl O-pyrazinyl phosphorothioate (Phosphorothioic acid, O,O-
diethyl O-pyrazinyl ester)
Diethylstilbesterol (Phenol, 4,4'-(1,2-diethyl-1,2-ethenediyl)bis-,(E)-)
Dihydrosafrole (1,3-Benxodioxole, 5-propyl-)
Diisopropylfluorophosphate (DFP) (Phosphorofluoridic acid, bis(1-methyl
ethyl) ester)
Dimethoate (Phosphorodithioic acid, O,O-dimethyl S-[2-(methylamino) 2-
oxoethyl] ester)
3,3'-Dimethoxybenzidine ([1,1'-Biphenyl]-4,4'-diamine, 3,3'-dimethoxy-)
p-Dimethylaminoazobenzene (Benzenamine, N,N-dimethyl-4-(phenylazo)-)
7,12-Dimethylbenz[a]anthracene (Benz[a]anthracene, 7,12-dimethyl-)
3,3'-Dimethylbenzidine ([1,1'-Biphenyl]-4,4'-diamine, 3,3'-dimethyl-)
Dimethylcarbamoyl chloride (carbamic chloride, dimethyl-)
1,1-Dimethylhydrazine (Hydrazine, 1,1-dimethyl-)
1,2-Dimethylhydrazine (Hydrazine, 1,2-dimethyl-)
,-Dimethylphenethylamine (Benzeneethanamine,
,-dimethyl-)
2,4-Dimethylphenol (Phenol, 2,4-dimethyl-)
Dimethylphthalate (1,2-Benzenedicarboxylic acid, dimethyl ester)
Dimethyl sulfate (Sulfuric acid, dimethyl ester)
Dinitrobenzene, N.O.S. (Benzene, dinitro-)
4,6-Dinitro-o-cresol and salts (Phenol, 2-methyl-4,6-dinitro-)
2,4-Dinitrophenol (Phenol, 2,4-dinitro-)
2,4-Dinitrotoluene (Benzene, 1-methyl-2,4-dinitro-)
2,6-Dinitrotoluene (Benzene, 2-methyl-1,3-dinitro-)
Dinoseb (Phenol, 2-(1-methylpropyl)-4,6-dinitro-)
Di-n-octyl phthalate (1,2-Benzenedicarboxylic acid, dioctyl ester)
1,4-Dioxane (1,4-Diethyleneoxide)
Diphenylamine (Benzenamine, N-phenyl-)
1,2-Diphenylhydrazine (Hydrazine, 1,2-diphenyl-)
Di-n-propylnitrosamine (1-Propanamine,N-nitroso-N-propyl-)
Disulfoton (Phosphorodithioic acid, O,O-diethyl S-[2-(ethylthio)ethyl]
ester)
Dithiobiuret (Thioimidodicarbonic diamide [(H2N)C(S)]2NH)
Endosulfan (6,9,Methano-2,4,3-benzodioxathiepin,6,7,8,9,10,10-
hexachloro-1,5,5a,6,9,9ahexahydro,3-oxide)
Endothall (7-Oxabicyclo[2.2.1]heptane-2,3-dicarboxylic acid)
Endrin and metabolites (2,7:3,6-Dimethanonaphth[2,3-
b]oxirene,3,4,5,6,9,9-hexachloro1a,2,2a,3,6,6a,7,7a-octa-
hydro,(1a,2,2a,3,6,6a
,7,7a)-)
Epichlorohydrin (Oxirane, (chloromethyl)-)
Epinephrine (1,2-Benzenediol,4-[1-hydroxy-2-(methylamino)ethyl]-,(R)-,)
Ethyl carbamate (urethane) (Carbamic acid, ethyl ester)
Ethyl cyanide (propanenitrile)
Ethylenebisdithiocarbamic acid, salts and esters (Carbamodithioic acid,
1,2-Ethanediylbis-)
[[Page 34]]
Ethylene dibromide (1,2-Dibromoethane)
Ethylene dichloride (1,2-Dichloroethane)
Ethylene glycol monoethyl ether (Ethanol, 2-ethoxy-)
Ethyleneimine (Aziridine)
Ethylene oxide (Oxirane)
Ethylenethiourea (2-Imidazolidinethione)
Ethylidene dichloride (Ethane, 1,1-
Dichloro-)
Ethyl methacrylate (2-Propenoic acid, 2-methyl-, ethyl ester)
Ethylmethane sulfonate (Methanesulfonic acid, ethyl ester)
Famphur (Phosphorothioic acid, O-[4-[(dimethylamino)sulphonyl]phenyl]
O,O-dimethyl ester)
Fluoranthene
Fluorine
Fluoroacetamide (Acetamide, 2-fluoro-)
Fluoroacetic acid, sodium salt (Acetic acid, fluoro-, sodium salt)
Formaldehyde (Methylene oxide)
Formic acid (Methanoic acid)
Glycidylaldehyde (Oxiranecarboxyaldehyde)
Halomethane, N.O.S.
Heptachlor (4,7-Methano-1H-indene, 1,4,5,6,7,8,8-heptachloro-3a,4,7,7a-
tetrahydro-)
Heptachlor epoxide (, , and isomers) (2,5-
Methano-2H-indeno[1,2-b]-oxirene, 2,3,4,5,6,7,7-heptachloro-
1a,1b,5,5a,6,6a-hexa-hydro-
,(1a,1b,2,5,5a,6,6a
)-)
Hexachlorobenzene (Benzene, hexachloro-)
Hexachlorobutadiene (1,3-Butadiene, 1,1,2,3,4,4-hexachloro-)
Hexachlorocyclopentadiene (1,3-Cyclopentadiene, 1,2,3,4,5,5-hexachloro-)
Hexachlorodibenzofurans
Heptachlorodibenzo-p-dioxins
Hexachloroethane (Ethane, hexachloro-)
Hexachlorophene (phenol, 2,2'-Methylenebis[3,4,6-trichloro-)
Hexachloropropene (1-Propene, 1,1,2,3,3,3-hexachloro-)
Hexaethyl tetraphosphate (Tetraphosphoric acid, hexaethyl ester)
Hydrazine
Hydrocyanic acid
Hydrofluoric acid
Hydrogen sulfide (H2S)
Indeno(1,2,3-cd)pyrene
Isobutyl alcohol (1-Propanol, 2-methyl-)
Isodrin (1,4,5,8-Dimethanonaphthalene, 1,2,3,4,10,10-hexachloro-
1,4,4a,5,8,8a-hexahydro,
(1,4,4a,5,8,8a)-)
Isosafrole (1,3-Benzodioxole, 5-(1-propenyl)-)
Kepone (1,3,4-Metheno-2H-cyclobuta[cd]pentalen-2-one,
1,1a,3,3a,4,5,5,5a,5b,6-decachlorooctahydro-)
Lasiocarpine (2-Butenoic acid, 2-methyl-,7-[[2,3-dihydroxy-2-(1-
methoxyethyl)-3-methyl-1-oxobutoxy]methyl]-2,3,5,7a-tetrahydro-1H-
pyrrolizin-l-yl ester)
Lead and compounds, N.O.S.
Lead acetate (Acetic acid, lead(2+) salt)
Lead phosphate (Phosphoric acid, lead(2+) salt(2:3))
Lead subacetate (Lead, bis(acetato-O)tetrahydroxytri-)
Lindane (Clohexane, 1,2,3,4,5,6-hexachloro-,
(1,2,3,4,5,6)-)
Maleic anhydride (2,5-Furandione)
Maleic hydrazide (3,6-Pyridazinedione, 1,2-dihydro-)
Malononitrile (Propanedinitrile)
Melphalan (L-Phenylalanine, 4-[bis(2-chloroethyl)aminol]-)
Mercury and compounds, N.O.S.
Mercury fulminate (Fulminic acid, mercury(2+) salt)
Methacrylonitrile (2-Propenenitrile, 2-methyl-)
Methapyrilene (1,2-Ethanediamine, N,N-dimethyl-N'-2-pyridinyl-N'-(2-
thienylmethyl)-)
Metholmyl (Ethamidothioic acid, N-[[(methylamino)carbonyl]oxy]thio-,
methyl ester)
Methoxychlor (Benzene, 1,1'-(2,2,2-trichloroethylidene)bis[4-methoxy-)
Methyl bromide (Methane, bromo-)
Methyl chloride (Methane, chloro-)
Methyl chlorocarbonate (Carbonchloridic acid, methyl ester)
Methyl chloroform (Ethane, 1,1,1-trichloro-)
3-Methylcholanthrene (Benz[j]aceanthrylene, 1,2-dihydro-3-methyl-)
4,4'-Methylenebis(2-chloroaniline) (Benzenamine, 4,4'-methylenebis(2-
chloro-)
Methylene bromide (Methane, dibromo-)
Methylene chloride (Methane, dichloro-)
Methyl ethyl ketone (MEK) (2-Butanone)
Methyl ethyl ketone peroxide (2-Butanone, peroxide)
Methyl hydrazine (Hydrazine, methyl-)
Methyl iodide (Methane, iodo-)
Methyl isocyanate (Methane, isocyanato-)
2-Methyllactonitrile (Propanenitrile, 2-hydroxy-2-methyl-)
Methyl methacrylate (2-Propenoic acid, 2-methyl-, methyl ester)
Methyl methanesulfonate (Methanesulfonic acid, methyl ester)
Methyl parathion (Phosphorothioic acid, O,O-dimethyl O-(4-nitrophenyl)
ester)
Methylthiouracil (4(1H)Pyrimidinone, 2,3-dihydro-6-methyl-2-thioxo-)
Mitomycin C (Azirino[2',3':3,4]pyrrolo[1,2-a]indole-4,7-dione,6-amino-8-
[[(aminocarbonyl) oxy]methyl]-1,1a,2,8,8a,8b-hexahydro-8a-methoxy-5-
methy-, [1aS-(1a,8,8a,8b)]-)
MNNG (Guanidine, N-methyl-N'-nitro-N-nitroso-)
Mustard gas (Ethane, 1,1'-thiobis[2-chloro-)
Naphthalene
1,4-Naphthoquinone (1,4-Naphthalenedione)
-Naphthalenamine (1-Naphthylamine)
-Naphthalenamine (2-Naphthylamine)
-Naphthylthiourea (Thiourea, 1-naphthalenyl-)
Nickel and compounds, N.O.S.
Nickel carbonyl (Ni(CO)4 (T-4)-)
[[Page 35]]
Nickel cyanide (Ni(CN)2)
Nicotine and salts (Pyridine, 3-(1-methyl-2-pyrrolidinyl)-, (S)-)
Nitric oxide (Nitrogen oxide NO)
p-Nitroaniline (Benzenamine, 4-nitro-)
Nitrobenzene (Benzene, nitro-)
Nitrogen dioxide (Nitrogen oxide NO2)
Nitrogen mustard, and hydrochloride salt (Ethanamine, 2-chloro-N-(2-
chloroethyl)-N-methyl-)
Nitrogen mustard N-oxide and hydrochloride salt (Ethanamine, 2chloro-N-
(2-chloroethyl)N-methyl-, N-oxide)
Nitroglycerin (1,2,3-Propanetriol, trinitrate)
p-Nitrophenol (Phenol, 4-nitro-)
2-Nitropropane (Propane, 2-nitro-)
Nitrosamines, N.O.S.
N-Nitrosodi-n-butylamine (l-Butanamine, N-butyl-N-nitroso-)
N-Nitrosodiethanolamine (Ethanol, 2,2'-(nitrosoimino)bis-)
N-Nitrosodiethylamine (Ethanamine, N-ethyl-N-nitroso-1)
N-Nitrosodimethylamine (Methanamine, N-methyl-N-nitroso-)
N-Nitroso-N-ethylurea (Urea, N-ethyl-N-nitroso-)
N-Nitrosomethylethylamine (Ethanamine, N-methyl-N-nitroso-)
N-Nitroso-N-methylurea (Urea, N-methyl-N-nitroso-)
N-Nitroso-N-methylurethane (Carbamic acid, methylnitroso-, ethyl ester)
N-Nitrosomethylvinylamine (Vinylamine, N-methyl-N-nitroso-)
N-Nitrosomorpholine (Morpholine,
4-nitroso-)
N-Nitrosonornicotine (Pyridine, 3-(1-nitroso-2-pyrrolidinyl)-, (S)-)
N-Nitrosopiperidine (Piperidine, 1-nitroso-)
Nitrosopyrrolidine (Pyrrolidine, 1-nitroso-)
N-Nitrososarcosine (Glycine, N-methyl-N-nitroso-)
5-Nitro-o-toluidine (Benzenamine, 2-methyl-5-nitro-)
Octamethylpyrophosphoramide (Diphosphoramide, octamethyl-)
Osmium tetroxide (Osmium oxide OsO4, (T-4)-)
Paraldehyde (1,3,5-Trioxane, 2,4,6-tri
methyl-)
Parathion (Phosphorothioic acid, O,O-diethyl O-(4-nitrophenyl) ester)
Pentachlorobenzene (Benzene, pentachloro-)
Pentachlorodibenzo-p-dioxins
Pentachlorodibenzofurans
Pentachloroethane (Ethane, pentachloro-)
Pentachloronitrobenzene (PCNB) (Benzene, pentachloronitro-)
Pentachlorophenol (Phenol, pentachloro-)
Phenacetin (Acetamide, N-(4-ethoxyphenyl)-)
Phenol
Phenylenediamine (Benzenediamine)
Phenylmercury acetate (Mercury, (acetato-O)phenyl-)
Phenylthiourea (Thiourea, phenyl-)
Phosgene (Carbonic dichloride)
Phosphine
Phorate (Phosphorodithioic acid, O,O-diethyl S-[(ethylthiomethyl] ester)
Phthalic acid esters, N.O.S.
Phthalic anhydride (1,3-isobenzofurandione)
2-Picoline (Pyridine, 2-methyl-)
Polychlorinated biphenyls, N.O.S.
Potassium cyanide (K(CN))
Potassium silver cyanide (Argentate(l-), bis(cyano-C)-, potassium)
Pronamide (Benzamide, 3,5-dichloro-N-(1,1-dimethyl-2-propynyl)-)
1,3-Propane sultone (1,2-Oxathiolane, 2,2-dioxide)
n-Propylamine (1-Propanamine)
Propargyl alcohol (2-Propyn-1-ol)
Propylene dichloride (Propane, 1,2-
dichloro-)
1,2-Propylenimine (Aziridine, 2-methyl-)
Propylthiouracil (4(1H)-Pyrimidinone, 2,3-dihydro-6-propyl-2-thioxo-)
Pyridine
Reserpinen (Yohimban-16-carboxylic acid, 11,17-dimethoxy-18-[(3,4,5-
trimethoxybenzoyl)oxy]-smethyl ester, (3,16
,17,18,20)-)
Resorcinol (1,3-Benzenediol)
Saccharin and salts (1,2-Benzisothiazol-3(2H)-one, 1,1-dioxide)
Safrole (1,3-Benzodioxole, 5-(2-propenyl)-)
Selenium and compounds, N.O.S.
Selenium dioxide (Selenious acid)
Selenium sulfide (SeS2)
Selenourea
Silver and compounds, N.O.S.
Silver cyanide (Silver cyanide Ag(CN))
Silvex (Propanoic acid, 2-(2,4,5-trichlorophen
oxy)-)
Sodium cyanide (Sodium cyanide Na(CN))
Streptozotocin (D-Glucose, 2-deoxy-2-
[[methylnitrosoamino)carbonyl]amino]-)
Strychnine and salts (Strychnidin-10-one)
TCDD (Dibenzo[b,e][1,4]dioxin, 2,3,7,8-tetrachloro-)
1,2,4,5-Tetrachlorobenzene (Benzene, 1,2,4,5-tetrachloro-)
Tetrachlorodibenzo-p-dioxins
Tetrachlorodibenxofurans
Tetrachloroethane, N.O.S. (Ethane, tetrachloro-, N.O.S.)
1,1,1,2-Tetrachloroethane (Ethane, 1,1,1,2-tetrachloro-)
1,1,2,2-Tetrachloroethane (Ethane, 1,1,2,2-tetrachloro-)
Tetrachloroethylene (Ethene, tetrachloro-)
2,3,4,6-Tetrachlorophenol (Phenol, 2,3,4,6-tetrachloro-)
Tetraethyldithiopyrophosphate (Thiodiphosphoric acid, tetraethyl ester)
Tetraethyl lead (Plumbane, tetraethyl-)
Tetraethyl pyrophosphate (Diphosphoric acid, tetraethyl ester)
Tetranitromethane (Methane, tetranitro-)
Thallium and compounds, N.O.S.
Thallic oxide (Thallium oxide Tl2O3)
Thallium (I) acetate (Acetic acid, thallium (1+) salt)
[[Page 36]]
Thallium (I) carbonate (Carbonic acid, dithallium (1+) salt)
Thallium (I) chloride (Thallium chloride TlCl)
Thallium (I) nitrate (Nitric acid, thallium (1+) salt)
Thallium selenite (Selenius acid, dithallium (1+) salt)
Thallium (I) sulfate (Sulfuric acid, thallium (1+) salt)
Thioacetamide (Ethanethioamide)
3,Thiofanox (2-Butanone, 3,3-dimethyl-1-(methylthio)-, O-
[(methylamino)carbonyl] oxime)
Thiomethanol (Methanethiol)
Thiophenol (Benzenethiol)
Thiosemicarbazide (Hydrazinecarbothioamide)
Thiourea
Thiram (Thioperoxydicarbonic diamide [(H2N)C(S)]2S2,
tetramethyl-)
Toluene (Benzene, methyl-)
Toluenediamine (Benzenediamine, ar-methyl-)
Toluene-2,4-diamine (1,3-Benzenediamine, 4-methyl-)
Toluene-2,6-diamine (1,3-Benzenediamine, 2-methyl-)
Toluene-3,4-diamine (1,2-Benzenediamine, 4-methyl-)
Toluene diisocyanate (Benzene, 1,3-diisocyanatomethyl-)
o-Toluidine (Benzenamine, 2-methyl-)
o-Toluidine hydrochloride (Benzenamine, 2-methyl-, hydrochloride)
p-Toluidine (Benzenamine, 4-methyl-)
Toxaphene
1,2,4-Trichlorobenzene (Benzene, 1,2,4-trichloro-)
1,1,2-Trichloroethane (Ethane, 1,1,2-trichloro-)
Trichloroethylene (Ethene,trichloro-)
Trichloromethanethiol (Methanethiol, trichloro-)
Trichloromonofluoromethane (Methane, trichlorofluoro-)
2,4,5-Trichlorophenol (Phenol, 2,4,5-trichloro-)
2,4,6-Trichlorophenol (Phenol, 2,4,6-trichloro-)
2,4,5-T (Acetic acid, 2,4,5- trichloro-
phenoxy-)
Trichloropropane, N.O.S.
1,2,3-Trichloropropane (Propane, 1,2,3-trichloro-)
O,O,O-Triethyl phosphorothioate (Phosphorothioic acid, O,O,O-triethyl
ester)
Trinitrobenzene (Benzene, 1,3,5-trinitro-)
Tris(1-aziridinyl)phosphine sulfide (Aziridine,
1,1',1''phosphinothioylidynetris-))
Tris(2,3-dibromopropyl) phosphate (1-Propanol, 2,3-dibromo-, phosphate
(3:1))
Trypan blue (2,7-Naphthalendisulfonic acid, 3,3'-[(3,3'-dimethyl[1,1'-
biphenyl]-4,4'-diyl)bis(azo)]bis(5-amino-4-hydroxy-, tetrasodium salt)
Uracil mustard (2,4-(1H,3H)-Pyrimidinedione, 5-[bis(2-
chloroethyl)amino]-)
Vanadium pentoxide (Vanadium oxide V2O5)
Vinyl chloride (Ethene, chloro-)
Wayfarin (2H-1-Benzopyran-2-one, 4-hydroxy-3-(3-oxo-1-phenlybutyl)-)
Zinc cyanide (Zn(CN)2)
Zinc phosphide (Zn3P2)
[60 FR 2868, Jan. 11, 1995]
PART 194--CRITERIA FOR THE CERTIFICATION AND RE-CERTIFICATION OF THE WASTE ISOLATION PILOT PLANT'S COMPLIANCE WITH THE 40 CFR PART 191 DISPOSAL REGULATIONS--Table of Contents
Subpart A--General Provisions
Sec.
194.1 Purpose, scope, and applicability.
194.2 Definitions.
194.3 Communications.
194.4 Conditions of compliance certification.
194.5 Publications incorporated by reference.
194.6 Alternative provisions.
194.7 Effective date.
Subpart B--Compliance Certification and Re-certification Applications
194.11 Completeness and accuracy of compliance applications.
194.12 Submission of compliance applications.
194.13 Submission of reference materials.
194.14 Content of compliance certification application.
194.15 Content of compliance re-certification application(s).
Subpart C--Compliance Certification and Re-certification
General Requirements
194.21 Inspections.
194.22 Quality assurance.
194.23 Models and computer codes.
194.24 Waste characterization.
194.25 Future state assumptions.
194.26 Expert judgment.
194.27 Peer review.
Containment Requirements
194.31 Application of release limits.
194.32 Scope of performance assessments.
194.33 Consideration of drilling events in performance assessments.
194.34 Results of performance assessments.
[[Page 37]]
Assurance Requirements
194.41 Active institutional controls.
194.42 Monitoring.
194.43 Passive institutional controls.
194.44 Engineered barriers.
194.45 Consideration of the presence of resources.
194.46 Removal of waste.
Individual and Ground-water Protection Requirements
194.51 Consideration of protected individual.
194.52 Consideration of exposure pathways.
194.53 Consideration of underground sources of drinking water.
194.54 Scope of compliance assessments.
194.55 Results of compliance assessments.
Subpart D--Public Participation
194.61 Advance notice of proposed rulemaking for certification.
194.62 Notice of proposed rulemaking for certification.
194.63 Final rule for certification.
194.64 Documentation of continued compliance.
194.65 Notice of proposed rulemaking for modification or revocation.
194.66 Final rule for modification or revocation.
194.67 Dockets.
Authority: The Waste Isolation Pilot Plant Land Withdrawal Act of
1992, Pub.L. 102-579, 106 Stat. 4777; Atomic Energy Act of 1954, as
amended, 42 U.S.C. 2011-2296; Reorganization Plan No. 3 of 1970, 5
U.S.C. app.1; Nuclear Waste Policy Act of 1982, as amended, 42 U.S.C.
10101-10270.
Source: 61 FR 5235, Feb. 9, 1996, unless otherwise noted.
Subpart A--General Provisions
Sec. 194.1 Purpose, scope, and applicability.
This part specifies criteria for the certification or any re-
certification, or subsequent actions relating to the terms or conditions
of certification of the Department of Energy's Waste Isolation Pilot
Plant's compliance with the disposal regulations found at part 191 of
this chapter and pursuant to section 8(d)(1) and section 8(f),
respectively, of the WIPP LWA. The compliance certification application
submitted pursuant to section 8(d)(1) of the WIPP LWA and any compliance
re-certification application submitted pursuant to section 8(f) of the
WIPP LWA shall comply with the requirements of this part.
Sec. 194.2 Definitions.
Unless otherwise indicated in this part, all terms have the same
meaning as in part 191 of this chapter.
Certification means any action taken by the Administrator pursuant
to section 8(d)(1) of the WIPP LWA.
Compliance application(s) means the compliance certification
application submitted to the Administrator pursuant to section 8(d)(1)
of the WIPP LWA or any compliance re-certification applications
submitted to the Administrator pursuant to section 8(f) of the WIPP LWA.
Compliance assessment(s) means the analysis conducted to determine
compliance with Sec. 191.15, and part 191, subpart C of this chapter.
Delaware Basin means those surface and subsurface features which lie
inside the boundary formed to the north, east and west of the disposal
system by the innermost edge of the Capitan Reef, and formed, to the
south, by a straight line drawn from the southeastern point of the Davis
Mountains to the most southwestern point of the Glass Mountains.
Deep drilling means those drilling events in the Delaware Basin that
reach or exceed a depth of 2,150 feet below the surface relative to
where such drilling occurred.
Department means the United States Department of Energy.
Disposal regulations means part 191, subparts B and C of this
chapter.
Management systems review means the qualitative assessment of a data
collection operation or organization(s) to establish whether the
prevailing quality management structure, policies, practices, and
procedures are adequate to ensure that the type and quality of data
needed are obtained.
Modification means action(s) taken by the Administrator that alters
the terms or conditions of certification pursuant to section 8(d)(1) of
the WIPP LWA. Modification of any certification shall comply with this
part and part 191 of this chapter.
Population of CCDFs means all possible complementary, cumulative
distribution functions (CCDFs) that can
[[Page 38]]
be generated from all disposal system parameter values used in
performance assessments.
Population of estimates means all possible estimates of radiation
doses and radionuclide concentrations that can be generated from all
disposal system parameter values used in compliance assessments.
Quality assurance means those planned and systematic actions
necessary to provide adequate confidence that the disposal system will
comply with the disposal regulations set forth in part 191 of this
chapter. Quality assurance includes quality control, which comprises
those actions related to the physical characteristics of a material,
structure, component, or system that provide a means to control the
quality of the material, structure, component, or system to
predetermined requirements.
Re-certification means any action taken by the Administrator
pursuant to section 8(f) of the WIPP LWA.
Regulatory time frame means the time period beginning at disposal
and ending 10,000 years after disposal.
Revocation means any action taken by the Administrator to terminate
the certification pursuant to section 8(d)(1) of the WIPP LWA.
Secretary means the Secretary of Energy.
Shallow drilling means those drilling events in the Delaware Basin
that do not reach a depth of 2,150 feet below the surface relative to
where such drilling occurred.
Suspension means any action taken by the Administrator to withdraw,
for a limited period of time, the certification pursuant to section
8(d)(1) of the WIPP LWA.
Waste means the radioactive waste, radioactive material and
coincidental material subject to the requirements of part 191 of this
chapter.
Waste characteristic means a property of the waste that has an
impact on the containment of waste in the disposal system.
Waste component means an ingredient of the total inventory of the
waste that influences a waste characteristic.
WIPP means the Waste Isolation Pilot Plant, as authorized pursuant
to section 213 of the Department of Energy National Security and
Military
[[Page 39]]
Applications of Nuclear Energy Authorization Act of 1980 (Pub.L. 96-164;
93 Stat. 1259, 1265).
WIPP LWA means the Waste Isolation Pilot Plant Land Withdrawal Act
of 1992 (Pub.L. 102-579, 106 Stat. 4777).
Sec. 194.3 Communications.
(a) Compliance application(s) shall be:
(1) Addressed to the Administrator; and
(2) Signed by the Secretary.
(b) Communications and reports concerning the criteria in this part
shall be:
(1) Addressed to the Administrator or the Administrator's authorized
representative; and
(2) Signed by the Secretary or the Secretary's authorized
representative.
Sec. 194.4 Conditions of compliance certification.
(a) Any certification of compliance issued pursuant to section
8(d)(1) of the WIPP LWA may include such conditions as the Administrator
finds necessary to support such certification.
(b) Whether stated therein or not, the following conditions shall
apply in any such certification:
(1) The certification shall be subject to modification, suspension
or revocation by the Administrator. Any suspension of the certification
shall be done at the discretion of the Administrator. Any modification
or revocation of the certification shall be done by rule pursuant to 5
U.S.C. 553. If the Administrator revokes the certification, the
Department shall retrieve, as soon as practicable and to the extent
practicable, any waste emplaced in the disposal system.
(2) Any time after the Administrator issues a certification, the
Administrator or the Administrator's authorized representative may
submit a written request to the Department for information to enable the
Administrator to determine whether the certification should be modified,
suspended or revoked. Unless otherwise specified by the Administrator or
the Administrator's authorized representative, the Department shall
submit such information to the Administrator or the Administrator's
authorized representative within 30 calendar days of receipt of the
request.
(3) Any time after the Administrator issues a certification, the
Department shall report any planned or unplanned changes in activities
or conditions pertaining to the disposal system that differ
significantly from the most recent compliance application.
(i) The Department shall inform the Administrator, in writing, prior
to making such a planned change in activity or disposal system
condition.
(ii) In the event of an unplanned change in activity or condition,
the Department shall immediately cease emplacement of waste in the
disposal system if the Department determines that one or more of the
following conditions is true:
(A) The containment requirements established pursuant to Sec. 191.13
of this chapter have been or are expected to be exceeded;
(B) Releases from already-emplaced waste lead to committed effective
doses that are or are expected to be in excess of those established
pursuant to Sec. 191.15 of this chapter. For purposes of this paragraph
(b)(3)(ii)(B), emissions from operations covered pursuant to part 191,
subpart A of this chapter are not included; or
(C) Releases have caused or are expected to cause concentrations of
radionuclides or estimated doses due to radionuclides in underground
sources of drinking water in the accessible environment to exceed the
limits established pursuant to part 191, subpart C of this chapter.
(iii) If the Department determines that a condition described in
paragraph (b)(3)(ii) of this section has occurred or is expected to
occur, the Department shall notify the Administrator, in writing, within
24 hours of the determination. Such notification shall, to the extent
practicable, include the following information:
(A) Identification of the location and environmental media of the
release or the expected release;
(B) Identification of the type and quantity of waste (in activity in
curies of each radionuclide) released or expected to be released;
[[Page 40]]
(C) Time and date of the release or the estimated time of the
expected release;
(D) Assessment of the hazard posed by the release or the expected
release; and
(E) Additional information requested by the Administrator or the
Administrator's authorized representative.
(iv) The Department may resume emplacement of waste in the disposal
system upon written notification that the suspension has been lifted by
the Administrator.
(v) If the Department discovers a condition or activity that differs
significantly from what is indicated in the most recent compliance
application, but does not involve conditions or activities listed in
paragraph (b)(3)(ii) of this section, then the difference shall be
reported, in writing, to the Administrator within 10 calendar days of
its discovery.
(vi) Following receipt of notification, the Administrator will
notify the Secretary in writing whether any condition or activity
reported pursuant to paragraph (b)(3) this section:
(A) Does not comply with the terms of the certification; and, if it
does not comply,
(B) Whether the compliance certification must be modified, suspended
or revoked. The Administrator or the Administrator's authorized
representative may request additional information before determining
whether modification, suspension or revocation of the compliance
certification is required.
(4) Not later than six months after the Administrator issues a
certification, and at least annually thereafter, the Department shall
report to the Administrator, in writing, any changes in conditions or
activities pertaining to the disposal system that were not required to
be reported by paragraph (b)(3) of this section and that differ from
information contained in the most recent compliance application.
Sec. 194.5 Publications incorporated by reference.
(a) The following publications are incorporated into this part by
reference:
(1) U.S. Nuclear Regulatory Commission, NUREG-1297 ``Peer Review for
High-Level Nuclear Waste Repositories,'' published February 1988;
incorporation by reference (IBR) approved for Secs. 194.22, 194.23 and
194.27.
(2) American Society of Mechanical Engineers (ASME) Nuclear Quality
Assurance (NQA) Standard, NQA-1-1989 edition, ``Quality Assurance
Program Requirements for Nuclear Facilities;'' IBR approved for
Sec. 194.22.
(3) ASME NQA-2a-1990 addenda, part 2.7, to ASME NQA-2-1989 edition
``Quality Assurance Requirements for Nuclear Facility Applications;''
IBR approved for Sec. 194.22 and Sec. 194.23.
(4) ASME NQA-3-1989 edition, ``Quality Assurance Program
Requirements for the Collection of Scientific and Technical Information
for Site Characterization of High-Level Nuclear Waste Repositories''
(excluding section 2.1 (b) and (c)); IBR approved for Sec. 194.22.
(b) The publications listed in paragraph (a) of this section were
approved for incorporation by reference by the Director of the Federal
Register in accordance with 5 U.S.C. 552(a) and 1 CFR part 51. Copies
may be inspected or obtained from the Air Docket, Docket No. A-92-56,
room M1500 (LE131), U.S. Environmental Protection Agency, 401 M Street,
SW, Washington, DC 20460, or copies may be inspected at the Office of
the Federal Register, 800 N. Capitol Street NW, 7th floor, Suite 700,
Washington, DC, or copies may be obtained from the following addresses:
(1) For ASME standards, contact American Society of Mechanical
Engineers, 22 Law Drive, P.O. Box 2900, Fairfield, NJ 07007-2900, phone
1-800-843-2763.
(2) For Nuclear Regulatory Commission documents, contact Division of
Information Support Services, Distribution Service, U.S. Nuclear
Regulatory Commission, Washington, DC 20555, or contact National
Technical Information Service, 5285 Port Royal Road, Springfield, VA
22161, phone 703-487-4650.
Sec. 194.6 Alternative provisions.
The Administrator may, by rule pursuant to 5 U.S.C. 553, substitute
for any of the provisions of this part alternative provisions chosen
after:
(a) The alternative provisions have been proposed for public comment
in
[[Page 41]]
the Federal Register together with information describing how the
alternative provisions comport with the disposal regulations, the
reasons why the existing provisions of this part appear inappropriate,
and the costs, risks and benefits of compliance in accordance with the
alternative provisions;
(b) A public comment period of at least 120 days has been completed
and public hearings have been held in New Mexico;
(c) The public comments received have been fully considered; and
(d) A notice of final rulemaking is published in the Federal
Register.
Sec. 194.7 Effective date.
The criteria in this part shall be effective on April 9, 1996. The
incorporation by reference of certain publications listed in the
criteria is approved by the Director of the Federal Register as of April
9, 1996.
Subpart B--Compliance Certification and Re-certification Applications
Sec. 194.11 Completeness and accuracy of compliance applications.
Information provided to the Administrator in support of any
compliance application shall be complete and accurate. The
Administrator's evaluation for certification pursuant to section
8(d)(1)(B) of the WIPP LWA and evaluation for recertification pursuant
to section 8(f)(2) of the WIPP LWA shall not begin until the
Administrator has notified the Secretary, in writing, that a complete
application in accordance with this part has been received.
Sec. 194.12 Submission of compliance applications.
Unless otherwise specified by the Administrator or the
Administrator's authorized representative, 30 copies of any compliance
application, any accompanying materials, and any amendments thereto
shall be submitted in a printed form to the Administrator.
Sec. 194.13 Submission of reference materials.
Information may be included by reference into compliance
application(s), provided that the references are clear and specific and
that, unless otherwise specified by the Administrator or the
Administrator's authorized representative, 10 copies of the referenced
information are submitted to the Administrator. Referenced materials
which are widely available in standard textbooks or reference books need
not be submitted.
Sec. 194.14 Content of compliance certification application.
Any compliance application shall include:
(a) A current description of the natural and engineered features
that may affect the performance of the disposal system. The description
of the disposal system shall include, at a minimum, the following
information:
(1) The location of the disposal system and the controlled area;
(2) A description of the geology, geophysics, hydrogeology,
hydrology, and geochemistry of the disposal system and its vicinity and
how these conditions are expected to change and interact over the
regulatory time frame. Such description shall include, at a minimum:
(i) Existing fluids and fluid hydraulic potential, including brine
pockets, in and near the disposal system; and
(ii) Existing higher permeability anhydrite interbeds located at or
near the horizon of the waste.
(3) The presence and characteristics of potential pathways for
transport of waste from the disposal system to the accessible
environment including, but not limited to: Existing boreholes, solution
features, breccia pipes, and other potentially permeable features, such
as interbeds.
(4) The projected geophysical, hydrogeologic and geochemical
conditions of the disposal system due to the presence of waste
including, but not limited to, the effects of production of heat or
gases from the waste.
(b) A description of the design of the disposal system including:
(1) Information on materials of construction including, but not
limited to: Geologic media, structural materials, engineered barriers,
general arrangement, and approximate dimensions; and
[[Page 42]]
(2) Computer codes and standards that have been applied to the
design and construction of the disposal system.
(c) Results of assessments conducted pursuant to this part.
(d) A description of input parameters associated with assessments
conducted pursuant to this part and the basis for selecting those input
parameters.
(e) Documentation of measures taken to meet the assurance
requirements of this part.
(f) A description of waste acceptance criteria and actions taken to
assure adherence to such criteria.
(g) A description of background radiation in air, soil and water in
the vicinity of the disposal system and the procedures employed to
determine such radiation.
(h) One or more topographic map(s) of the vicinity of the disposal
system. The contour interval shall be sufficient to show clearly the
pattern of surface water flow in the vicinity of the disposal system.
The map(s) shall include standard map notations and symbols, and, in
addition, shall show boundaries of the controlled area and the location
of any active, inactive, and abandoned injection and withdrawal wells in
the controlled area and in the vicinity of the disposal system.
(i) A description of past and current climatologic and meteorologic
conditions in the vicinity of the disposal system and how these
conditions are expected to change over the regulatory time frame.
(j) The information required elsewhere in this part or any
additional information, analyses, tests, or records determined by the
Administrator or the Administrator's authorized representative to be
necessary for determining compliance with this part.
Sec. 194.15 Content of compliance re-certification application(s).
(a) In submitting documentation of continued compliance pursuant to
section 8(f) of the WIPP LWA, the previous compliance application shall
be updated to provide sufficient information for the Administrator to
determine whether or not the WIPP continues to be in compliance with the
disposal regulations. Updated documentation shall include:
(1) All additional geologic, geophysical, geochemical, hydrologic,
and meteorologic information;
(2) All additional monitoring data, analyses and results;
(3) All additional analyses and results of laboratory experiments
conducted by the Department or its contractors as part of the WIPP
program;
(4) An identification of any activities or assumptions that deviate
from the most recent compliance application;
(5) A description of all waste emplaced in the disposal system since
the most recent compliance certification or re-certification
application. Such description shall consist of a description of the
waste characteristics and waste components identified in
Secs. 194.24(b)(1) and 194.24(b)(2);
(6) Any significant information not previously included in a
compliance certification or re-certification application related to
whether the disposal system continues to be in compliance with the
disposal regulations; and
(7) Any additional information requested by the Administrator or the
Administrator's authorized representative.
(b) To the extent that information required for a re-certification
of compliance remains valid and has been submitted in previous
certification or re-certification application(s), such information need
not be duplicated in subsequent applications; such information may be
summarized and referenced.
Subpart C--Compliance Certification and Re-certification
General Requirements
Sec. 194.21 Inspections.
(a) The Administrator or the Administrator's authorized
representative(s) shall, at any time:
(1) Be afforded unfettered and unannounced access to inspect any
area of the WIPP, and any locations performing activities that provide
information relevant to compliance application(s), to which the
Department has rights of access. Such access shall be equivalent
[[Page 43]]
to access afforded Department employees upon presentation of credentials
and other required documents.
(2) Be allowed to obtain samples, including split samples, and to
monitor and measure aspects of the disposal system and the waste
proposed for disposal in the disposal system.
(b) Records (including data and other information in any form) kept
by the Department pertaining to the WIPP shall be made available to the
Administrator or the Administrator's authorized representative upon
request. If requested records are not immediately available, they shall
be delivered within 30 calendar days of the request.
(c) The Department shall, upon request by the Administrator or the
Administrator's authorized representative, provide permanent, private
office space that is accessible to the disposal system. The office space
shall be for the exclusive use of the Administrator or the
Administrator's authorized representative(s).
(d) The Administrator or the Administrator's authorized
representative(s) shall comply with applicable access control measures
for security, radiological protection, and personal safety when
conducting activities pursuant to this section.
Sec. 194.22 Quality assurance.
(a)(1) As soon as practicable after April 9, 1996, the Department
shall adhere to a quality assurance program that implements the
requirements of ASME NQA-1-1989 edition, ASME NQA-2a-1990 addenda, part
2.7, to ASME NQA-2-1989 edition, and ASME NQA-3-1989 edition (excluding
Section 2.1 (b) and (c), and Section 17.1). (Incorporation by reference
as specified in Sec. 194.5.)
(2) Any compliance application shall include information which
demonstrates that the quality assurance program required pursuant to
paragraph (a)(1) of this section has been established and executed for:
(i) Waste characterization activities and assumptions;
(ii) Environmental monitoring, monitoring of the performance of the
disposal system, and sampling and analysis activities;
(iii) Field measurements of geologic factors, ground water,
meteorologic, and topographic characteristics;
(iv) Computations, computer codes, models and methods used to
demonstrate compliance with the disposal regulations in accordance with
the provisions of this part;
(v) Procedures for implementation of expert judgment elicitation
used to support applications for certification or re-certification of
compliance;
(vi) Design of the disposal system and actions taken to ensure
compliance with design specifications;
(vii) The collection of data and information used to support
compliance application(s); and
(viii) Other systems, structures, components, and activities
important to the containment of waste in the disposal system.
(b) Any compliance application shall include information which
demonstrates that data and information collected prior to the
implementation of the quality assurance program required pursuant to
paragraph (a)(1) of this section have been qualified in accordance with
an alternate methodology, approved by the Administrator or the
Administrator's authorized representative, that employs one or more of
the following methods: Peer review, conducted in a manner that is
compatible with NUREG-1297, ``Peer Review for High-Level Nuclear Waste
Repositories,'' published February 1988 (incorporation by reference as
specified in Sec. 194.5); corroborating data; confirmatory testing; or a
quality assurance program that is equivalent in effect to ASME NQA-1-
1989 edition, ASME NQA-2a-1990 addenda, part 2.7, to ASME NQA-2-1989
edition, and ASME NQA-3-1989 edition (excluding Section 2.1 (b) and (c)
and Section 17.1). (Incorporation by reference as specified in
Sec. 194.5.)
(c) Any compliance application shall provide, to the extent
practicable, information which describes how all data used to support
the compliance application have been assessed for their quality
characteristics, including:
(1) Data accuracy, i.e., the degree to which data agree with an
accepted reference or true value;
[[Page 44]]
(2) Data precision, i.e., a measure of the mutual agreement between
comparable data gathered or developed under similar conditions expressed
in terms of a standard deviation;
(3) Data representativeness, i.e., the degree to which data
accurately and precisely represent a characteristic of a population, a
parameter, variations at a sampling point, or environmental conditions;
(4) Data completeness, i.e., a measure of the amount of valid data
obtained compared to the amount that was expected; and
(5) Data comparability, i.e., a measure of the confidence with which
one data set can be compared to another.
(d) Any compliance application shall provide information which
demonstrates how all data are qualified for use in the demonstration of
compliance.
(e) The Administrator will verify appropriate execution of quality
assurance programs through inspections, record reviews and record
keeping requirements, which may include, but may not be limited to,
surveillance, audits and management systems reviews.
Sec. 194.23 Models and computer codes.
(a) Any compliance application shall include:
(1) A description of the conceptual models and scenario construction
used to support any compliance application.
(2) A description of plausible, alternative conceptual model(s)
seriously considered but not used to support such application, and an
explanation of the reason(s) why such model(s) was not deemed to
accurately portray performance of the disposal system.
(3) Documentation that:
(i) Conceptual models and scenarios reasonably represent possible
future states of the disposal system;
(ii) Mathematical models incorporate equations and boundary
conditions which reasonably represent the mathematical formulation of
the conceptual models;
(iii) Numerical models provide numerical schemes which enable the
mathematical models to obtain stable solutions;
(iv) Computer models accurately implement the numerical models;
i.e., computer codes are free of coding errors and produce stable
solutions;
(v) Conceptual models have undergone peer review according to
Sec. 194.27.
(b) Computer codes used to support any compliance application shall
be documented in a manner that complies with the requirements of ASME
NQA-2a-1990 addenda, part 2.7, to ASME NQA-2-1989 edition.
(Incorporation by reference as specified in Sec. 194.5.)
(c) Documentation of all models and computer codes included as part
of any compliance application performance assessment calculation shall
be provided. Such documentation shall include, but shall not be limited
to:
(1) Descriptions of the theoretical backgrounds of each model and
the method of analysis or assessment;
(2) General descriptions of the models; discussions of the limits of
applicability of each model; detailed instructions for executing the
computer codes, including hardware and software requirements, input and
output formats with explanations of each input and output variable and
parameter (e.g., parameter name and units); listings of input and output
files from a sample computer run; and reports on code verification,
benchmarking, validation, and quality assurance procedures;
(3) Detailed descriptions of the structure of computer codes and
complete listings of the source codes;
(4) Detailed descriptions of data collection procedures, sources of
data, data reduction and analysis, and code input parameter development;
(5) Any necessary licenses; and
(6) An explanation of the manner in which models and computer codes
incorporate the effects of parameter correlation.
(d) The Administrator or the Administrator's authorized
representative may verify the results of computer simulations used to
support any compliance application by performing independent
simulations. Data files, source codes, executable versions of computer
software for each model, other material or information needed to permit
the Administrator or the Administrator's authorized representative to
perform independent simulations, and access to necessary hardware to
perform such simulations, shall be provided
[[Page 45]]
within 30 calendar days of a request by the Administrator or the
Administrator's authorized representative.
Sec. 194.24 Waste characterization.
(a) Any compliance application shall describe the chemical,
radiological and physical composition of all existing waste proposed for
disposal in the disposal system. To the extent practicable, any
compliance application shall also describe the chemical, radiological
and physical composition of to-be-generated waste proposed for disposal
in the disposal system. These descriptions shall include a list of waste
components and their approximate quantities in the waste. This list may
be derived from process knowledge, current non-destructive examination/
assay, or other information and methods.
(b) The Department shall submit in the compliance certification
application the results of an analysis which substantiates:
(1) That all waste characteristics influencing containment of waste
in the disposal system have been identified and assessed for their
impact on disposal system performance. The characteristics to be
analyzed shall include, but shall not be limited to: Solubility;
formation of colloidal suspensions containing radionuclides; production
of gas from the waste; shear strength; compactability; and other waste-
related inputs into the computer models that are used in the performance
assessment.
(2) That all waste components influencing the waste characteristics
identified in paragraph (b)(1) of this section have been identified and
assessed for their impact on disposal system performance. The components
to be analyzed shall include, but shall not be limited to: metals;
cellulosics; chelating agents; water and other liquids; and activity in
curies of each isotope of the radionuclides present.
(3) Any decision to exclude consideration of any waste
characteristic or waste component because such characteristic or
component is not expected to significantly influence the containment of
the waste in the disposal system.
(c) For each waste component identified and assessed pursuant to
paragraph (b) of this section, the Department shall specify the limiting
value (expressed as an upper or lower limit of mass, volume, curies,
concentration, etc.), and the associated uncertainty (i.e., margin of
error) for each limiting value, of the total inventory of such waste
proposed for disposal in the disposal system. Any compliance application
shall:
(1) Demonstrate that, for the total inventory of waste proposed for
disposal in the disposal system, WIPP complies with the numeric
requirements of Sec. 194.34 and Sec. 194.55 for the upper or lower
limits (including the associated uncertainties), as appropriate, for
each waste component identified in paragraph (b)(2) of this section, and
for the plausible combinations of upper and lower limits of such waste
components that would result in the greatest estimated release.
(2) Identify and describe the method(s) used to quantify the limits
of waste components identified in paragraph (b)(2) of this section.
(3) Provide information which demonstrates that the use of process
knowledge to quantify components in waste for disposal conforms with the
quality assurance requirements found in Sec. 194.22.
(4) Provide information which demonstrates that a system of controls
has been and will continue to be implemented to confirm that the total
amount of each waste component that will be emplaced in the disposal
system will not exceed the upper limiting value or fall below the lower
limiting value described in the introductory text of paragraph (c) of
this section. The system of controls shall include, but shall not be
limited to: Measurement; sampling; chain of custody records; record
keeping systems; waste loading schemes used; and other documentation.
(5) Identify and describe such controls delineated in paragraph
(c)(4) of this section and confirm that they are applied in accordance
with the quality assurance requirements found in Sec. 194.22.
[[Page 46]]
(d) The Department shall include a waste loading scheme in any
compliance application, or else performance assessments conducted
pursuant to Sec. 194.32 and compliance assessments conducted pursuant to
Sec. 194.54 shall assume random placement of waste in the disposal
system.
(e) Waste may be emplaced in the disposal system only if the
emplaced components of such waste will not cause:
(1) The total quantity of waste in the disposal system to exceed the
upper limiting value, including the associated uncertainty, described in
the introductory text to paragraph (c) of this section; or
(2) The total quantity of waste that will have been emplaced in the
disposal system, prior to closure, to fall below the lower limiting
value, including the associated uncertainty, described in the
introductory text to paragraph (c) of this section.
(f) Waste emplacement shall conform to the assumed waste loading
conditions, if any, used in performance assessments conducted pursuant
to Sec. 194.32 and compliance assessments conducted pursuant to
Sec. 194.54.
(g) The Department shall demonstrate in any compliance application
that the total inventory of waste emplaced in the disposal system
complies with the limitations on transuranic waste disposal described in
the WIPP LWA.
(h) The Administrator will use inspections and records reviews, such
as audits, to verify compliance with this section.
Sec. 194.25 Future state assumptions.
(a) Unless otherwise specified in this part or in the disposal
regulations, performance assessments and compliance assessments
conducted pursuant the provisions of this part to demonstrate compliance
with Sec. 191.13, Sec. 191.15 and part 191, subpart C shall assume that
characteristics of the future remain what they are at the time the
compliance application is prepared, provided that such characteristics
are not related to hydrogeologic, geologic or climatic conditions.
(b) In considering future states pursuant to this section, the
Department shall document in any compliance application, to the extent
practicable, effects of potential future hydrogeologic, geologic and
climatic conditions on the disposal system over the regulatory time
frame. Such documentation shall be part of the activities undertaken
pursuant to Sec. 194.14, Content of compliance certification
application; Sec. 194.32, Scope of performance assessments; and
Sec. 194.54, Scope of compliance assessments.
(1) In considering the effects of hydrogeologic conditions on the
disposal system, the Department shall document in any compliance
application, to the extent practicable, the effects of potential changes
to hydrogeologic conditions.
(2) In considering the effects of geologic conditions on the
disposal system, the Department shall document in any compliance
application, to the extent practicable, the effects of potential changes
to geologic conditions, including, but not limited to: Dissolution; near
surface geomorphic features and processes; and related subsidence in the
geologic units of the disposal system.
(3) In considering the effects of climatic conditions on the
disposal system, the Department shall document in any compliance
application, to the extent practicable, the effects of potential changes
to future climate cycles of increased precipitation (as compared to
present conditions).
Sec. 194.26 Expert judgment.
(a) Expert judgment, by an individual expert or panel of experts,
may be used to support any compliance application, provided that expert
judgment does not substitute for information that could reasonably be
obtained through data collection or experimentation.
(b) Any compliance application shall:
(1) Identify any expert judgments used to support the application
and shall identify experts (by name and employer) involved in any expert
judgment elicitation processes used to support the application.
(2) Describe the process of eliciting expert judgment, and document
the results of expert judgment elicitation processes and the reasoning
behind
[[Page 47]]
those results. Documentation of interviews used to elicit judgments from
experts, the questions or issues presented for elicitation of expert
judgment, background information provided to experts, and deliberations
and formal interactions among experts shall be provided. The opinions of
all experts involved in each elicitation process shall be provided
whether the opinions are used to support compliance applications or not.
(3) Provide documentation that the following restrictions and
guidelines have been applied to any selection of individuals used to
elicit expert judgments:
(i) Individuals who are members of the team of investigators
requesting the judgment or the team of investigators who will use the
judgment were not selected; and
(ii) Individuals who maintain, at any organizational level, a
supervisory role or who are supervised by those who will utilize the
judgment were not selected.
(4) Provide information which demonstrates that:
(i) The expertise of any individual involved in expert judgment
elicitation comports with the level of knowledge required by the
questions or issues presented to that individual; and
(ii) The expertise of any expert panel, as a whole, involved in
expert judgment elicitation comports with the level and variety of
knowledge required by the questions or issues presented to that panel.
(5) Explain the relationship among the information and issues
presented to experts prior to the elicitation process, the elicited
judgment of any expert panel or individual, and the purpose for which
the expert judgment is being used in compliance applications(s).
(6) Provide documentation that the initial purpose for which expert
judgment was intended, as presented to the expert panel, is consistent
with the purpose for which this judgment was used in compliance
application(s).
(7) Provide documentation that the following restrictions and
guidelines have been applied in eliciting expert judgment:
(i) At least five individuals shall be used in any expert
elicitation process, unless there is a lack or unavailability of experts
and a documented rationale is provided that explains why fewer than five
individuals were selected.
(ii) At least two-thirds of the experts involved in an elicitation
shall consist of individuals who are not employed directly by the
Department or by the Department's contractors, unless the Department can
demonstrate and document that there is a lack or unavailability of
qualified independent experts. If so demonstrated, at least one-third of
the experts involved in an elicitation shall consist of individuals who
are not employed directly by the Department or by the Department's
contractors.
(c) The public shall be afforded a reasonable opportunity to present
its scientific and technical views to expert panels as input to any
expert elicitation process.
Sec. 194.27 Peer review.
(a) Any compliance application shall include documentation of peer
review that has been conducted, in a manner required by this section,
for:
(1) Conceptual models selected and developed by the Department;
(2) Waste characterization analyses as required in Sec. 194.24(b);
and
(3) Engineered barrier evaluation as required in Sec. 194.44.
(b) Peer review processes required in paragraph (a) of this section,
and conducted subsequent to the promulgation of this part, shall be
conducted in a manner that is compatible with NUREG-1297, ``Peer Review
for High-Level Nuclear Waste Repositories,'' published February 1988.
(Incorporation by reference as specified in Sec. 194.5.)
(c) Any compliance application shall:
(1) Include information that demonstrates that peer review processes
required in paragraph (a) of this section, and conducted prior to the
implementation of the promulgation of this part, were conducted in
accordance with an alternate process substantially equivalent in effect
to NUREG-1297 and approved by the Administrator or the Administrator's
authorized representative; and
(2) Document any peer review processes conducted in addition to
those required pursuant to paragraph (a) of
[[Page 48]]
this section. Such documentation shall include formal requests, from the
Department to outside review groups or individuals, to review or comment
on any information used to support compliance applications, and the
responses from such groups or individuals.
Containment Requirements
Sec. 194.31 Application of release limits.
The release limits shall be calculated according to part 191,
appendix A of this chapter, using the total activity, in curies, that
will exist in the disposal system at the time of disposal.
Sec. 194.32 Scope of performance assessments.
(a) Performance assessments shall consider natural processes and
events, mining, deep drilling, and shallow drilling that may affect the
disposal system during the regulatory time frame.
(b) Assessments of mining effects may be limited to changes in the
hydraulic conductivity of the hydrogeologic units of the disposal system
from excavation mining for natural resources. Mining shall be assumed to
occur with a one in 100 probability in each century of the regulatory
time frame. Performance assessments shall assume that mineral deposits
of those resources, similar in quality and type to those resources
currently extracted from the Delaware Basin, will be completely removed
from the controlled area during the century in which such mining is
randomly calculated to occur. Complete removal of such mineral resources
shall be assumed to occur only once during the regulatory time frame.
(c) Performance assessments shall include an analysis of the effects
on the disposal system of any activities that occur in the vicinity of
the disposal system prior to disposal and are expected to occur in the
vicinity of the disposal system soon after disposal. Such activities
shall include, but shall not be limited to, existing boreholes and the
development of any existing leases that can be reasonably expected to be
developed in the near future, including boreholes and leases that may be
used for fluid injection activities.
(d) Performance assessments need not consider processes and events
that have less than one chance in 10,000 of occurring over 10,000 years.
(e) Any compliance application(s) shall include information which:
(1) Identifies all potential processes, events or sequences and
combinations of processes and events that may occur during the
regulatory time frame and may affect the disposal system;
(2) Identifies the processes, events or sequences and combinations
of processes and events included in performance assessments; and
(3) Documents why any processes, events or sequences and
combinations of processes and events identified pursuant to paragraph
(e)(1) of this section were not included in performance assessment
results provided in any compliance application.
Sec. 194.33 Consideration of drilling events in performance assessments.
(a) Performance assessments shall examine deep drilling and shallow
drilling that may potentially affect the disposal system during the
regulatory time frame.
(b) The following assumptions and process shall be used in assessing
the likelihood and consequences of drilling events, and the results of
such process shall be documented in any compliance application:
(1) Inadvertent and intermittent intrusion by drilling for resources
(other than those resources provided by the waste in the disposal system
or engineered barriers designed to isolate such waste) is the most
severe human intrusion scenario.
(2) In performance assessments, drilling events shall be assumed to
occur in the Delaware Basin at random intervals in time and space during
the regulatory time frame.
(3) The frequency of deep drilling shall be calculated in the
following manner:
(i) Identify deep drilling that has occurred for each resource in
the Delaware Basin over the past 100 years prior to the time at which a
compliance application is prepared.
(ii) The total rate of deep drilling shall be the sum of the rates
of deep drilling for each resource.
[[Page 49]]
(4) The frequency of shallow drilling shall be calculated in the
following manner:
(i) Identify shallow drilling that has occurred for each resource in
the Delaware Basin over the past 100 years prior to the time at which a
compliance application is prepared.
(ii) The total rate of shallow drilling shall be the sum of the
rates of shallow drilling for each resource.
(iii) In considering the historical rate of all shallow drilling,
the Department may, if justified, consider only the historical rate of
shallow drilling for resources of similar type and quality to those in
the controlled area.
(c) Performance assessments shall document that in analyzing the
consequences of drilling events, the Department assumed that:
(1) Future drilling practices and technology will remain consistent
with practices in the Delaware Basin at the time a compliance
application is prepared. Such future drilling practices shall include,
but shall not be limited to: The types and amounts of drilling fluids;
borehole depths, diameters, and seals; and the fraction of such
boreholes that are sealed by humans; and
(2) Natural processes will degrade or otherwise affect the
capability of boreholes to transmit fluids over the regulatory time
frame.
(d) With respect to future drilling events, performance assessments
need not analyze the effects of techniques used for resource recovery
subsequent to the drilling of the borehole.
Sec. 194.34 Results of performance assessments.
(a) The results of performance assessments shall be assembled into
``complementary, cumulative distribution functions'' (CCDFs) that
represent the probability of exceeding various levels of cumulative
release caused by all significant processes and events.
(b) Probability distributions for uncertain disposal system
parameter values used in performance assessments shall be developed and
documented in any compliance application.
(c) Computational techniques, which draw random samples from across
the entire range of the probability distributions developed pursuant to
paragraph (b) of this section, shall be used in generating CCDFs and
shall be documented in any compliance application.
(d) The number of CCDFs generated shall be large enough such that,
at cumulative releases of 1 and 10, the maximum CCDF generated exceeds
the 99th percentile of the population of CCDFs with at least a 0.95
probability. Values of cumulative release shall be calculated according
to Note 6 of Table 1, appendix A of part 191 of this chapter.
(e) Any compliance application shall display the full range of CCDFs
generated.
(f) Any compliance application shall provide information which
demonstrates that there is at least a 95 percent level of statistical
confidence that the mean of the population of CCDFs meets the
containment requirements of Sec. 191.13 of this chapter.
Assurance Requirements
Sec. 194.41 Active institutional controls.
(a) Any compliance application shall include detailed descriptions
of proposed active institutional controls, the controls' location, and
the period of time the controls are proposed to remain active.
Assumptions pertaining to active institutional controls and their
effectiveness in terms of preventing or reducing radionuclide releases
shall be supported by such descriptions.
(b) Performance assessments shall not consider any contributions
from active institutional controls for more than 100 years after
disposal.
Sec. 194.42 Monitoring.
(a) The Department shall conduct an analysis of the effects of
disposal system parameters on the containment of waste in the disposal
system and shall include the results of such analysis in any compliance
application. The results of the analysis shall be used in developing
plans for pre-closure and post-closure monitoring required pursuant to
paragraphs (c) and (d) of this section. The disposal system parameters
analyzed shall include, at a minimum:
(1) Properties of backfilled material, including porosity,
permeability, and
[[Page 50]]
degree of compaction and reconsolidation;
(2) Stresses and extent of deformation of the surrounding roof,
walls, and floor of the waste disposal room;
(3) Initiation or displacement of major brittle deformation features
in the roof or surrounding rock;
(4) Ground water flow and other effects of human intrusion in the
vicinity of the disposal system;
(5) Brine quantity, flux, composition, and spatial distribution;
(6) Gas quantity and composition; and
(7) Temperature distribution.
(b) For all disposal system parameters analyzed pursuant to
paragraph (a) of this section, any compliance application shall document
and substantiate the decision not to monitor a particular disposal
system parameter because that parameter is considered to be
insignificant to the containment of waste in the disposal system or to
the verification of predictions about the future performance of the
disposal system.
(c) Pre-closure monitoring. To the extent practicable, pre-closure
monitoring shall be conducted of significant disposal system
parameter(s) as identified by the analysis conducted pursuant to
paragraph (a) of this section. A disposal system parameter shall be
considered significant if it affects the system's ability to contain
waste or the ability to verify predictions about the future performance
of the disposal system. Such monitoring shall begin as soon as
practicable; however, in no case shall waste be emplaced in the disposal
system prior to the implementation of pre-closure monitoring. Pre-
closure monitoring shall end at the time at which the shafts of the
disposal system are backfilled and sealed.
(d) Post-closure monitoring. The disposal system shall, to the
extent practicable, be monitored as soon as practicable after the shafts
of the disposal system are backfilled and sealed to detect substantial
and detrimental deviations from expected performance and shall end when
the Department can demonstrate to the satisfaction of the Administrator
that there are no significant concerns to be addressed by further
monitoring. Post-closure monitoring shall be complementary to monitoring
required pursuant to applicable federal hazardous waste regulations at
parts 264, 265, 268, and 270 of this chapter and shall be conducted with
techniques that do not jeopardize the containment of waste in the
disposal system.
(e) Any compliance application shall include detailed pre-closure
and post-closure monitoring plans for monitoring the performance of the
disposal system. At a minimum, such plans shall:
(1) Identify the parameters that will be monitored and how baseline
values will be determined;
(2) Indicate how each parameter will be used to evaluate any
deviations from the expected performance of the disposal system; and
(3) Discuss the length of time over which each parameter will be
monitored to detect deviations from expected performance.
Sec. 194.43 Passive institutional controls.
(a) Any compliance application shall include detailed descriptions
of the measures that will be employed to preserve knowledge about the
location, design, and contents of the disposal system. Such measures
shall include:
(1) Identification of the controlled area by markers that have been
designed and will be fabricated and emplaced to be as permanent as
practicable;
(2) Placement of records in the archives and land record systems of
local, State, and Federal governments, and international archives, that
would likely be consulted by individuals in search of unexploited
resources. Such records shall identify:
(i) The location of the controlled area and the disposal system;
(ii) The design of the disposal system;
(iii) The nature and hazard of the waste;
(iv) Geologic, geochemical, hydrologic, and other site data
pertinent to the containment of waste in the disposal system, or the
location of such information; and
(v) The results of tests, experiments, and other analyses relating
to backfill of excavated areas, shaft sealing, waste
[[Page 51]]
interaction with the disposal system, and other tests, experiments, or
analyses pertinent to the containment of waste in the disposal system,
or the location of such information.
(3) Other passive institutional controls practicable to indicate the
dangers of the waste and its location.
(b) Any compliance application shall include the period of time
passive institutional controls are expected to endure and be understood.
(c) The Administrator may allow the Department to assume passive
institutional control credit, in the form of reduced likelihood of human
intrusion, if the Department demonstrates in the compliance application
that such credit is justified because the passive institutional controls
are expected to endure and be understood by potential intruders for the
time period approved by the Administrator. Such credit, or a smaller
credit as determined by the Administrator, cannot be used for more than
several hundred years and may decrease over time. In no case, however,
shall passive institutional controls be assumed to eliminate the
likelihood of human intrusion entirely.
Sec. 194.44 Engineered barriers.
(a) Disposal systems shall incorporate engineered barrier(s)
designed to prevent or substantially delay the movement of water or
radionuclides toward the accessible environment.
(b) In selecting any engineered barrier(s) for the disposal system,
the Department shall evaluate the benefit and detriment of engineered
barrier alternatives, including but not limited to: Cementation,
shredding, supercompaction, incineration, vitrification, improved waste
canisters, grout and bentonite backfill, melting of metals, alternative
configurations of waste placements in the disposal system, and
alternative disposal system dimensions. The results of this evaluation
shall be included in any compliance application and shall be used to
justify the selection and rejection of each engineered barrier
evaluated.
(c)(1) In conducting the evaluation of engineered barrier
alternatives, the following shall be considered, to the extent
practicable:
(i) The ability of the engineered barrier to prevent or
substantially delay the movement of water or waste toward the accessible
environment;
(ii) The impact on worker exposure to radiation both during and
after incorporation of engineered barriers;
(iii) The increased ease or difficulty of removing the waste from
the disposal system;
(iv) The increased or reduced risk of transporting the waste to the
disposal system;
(v) The increased or reduced uncertainty in compliance assessment;
(vi) Public comments requesting specific engineered barriers;
(vii) The increased or reduced total system costs;
(viii) The impact, if any, on other waste disposal programs from the
incorporation of engineered barriers (e.g., the extent to which the
incorporation of engineered barriers affects the volume of waste);
(ix) The effects on mitigating the consequences of human intrusion.
(2) If, after consideration of one or more of the factors in
paragraph (c)(1) of this section, the Department concludes that an
engineered barrier considered within the scope of the evaluation should
be rejected without evaluating the remaining factors in paragraph (c)(1)
of this section, then any compliance application shall provide a
justification for this rejection explaining why the evaluation of the
remaining factors would not alter the conclusion.
(d) In considering the ability of engineered barriers to prevent or
substantially delay the movement of water or radionuclides toward the
accessible environment, the benefit and detriment of engineered barriers
for existing waste already packaged, existing waste not yet packaged,
existing waste in need of re-packaging, and to-be-generated waste shall
be considered separately and described.
(e) The evaluation described in paragraphs (b), (c) and (d) of this
section shall consider engineered barriers alone and in combination.
[[Page 52]]
Sec. 194.45 Consideration of the presence of resources.
Any compliance application shall include information that
demonstrates that the favorable characteristics of the disposal system
compensate for the presence of resources in the vicinity of the disposal
system and the likelihood of the disposal system being disturbed as a
result of the presence of those resources. If performance assessments
predict that the disposal system meets the containment requirements of
Sec. 191.13 of this chapter, then the Agency will assume that the
requirements of this section and Sec. 191.14(e) of this chapter have
been fulfilled.
Sec. 194.46 Removal of waste.
Any compliance application shall include documentation which
demonstrates that removal of waste from the disposal system is feasible
for a reasonable period of time after disposal. Such documentation shall
include an analysis of the technological feasibility of mining the
sealed disposal system, given technology levels at the time a compliance
application is prepared.
Individual and Ground-water Protection Requirements
Sec. 194.51 Consideration of protected individual.
Compliance assessments that analyze compliance with Sec. 191.15 of
this chapter shall assume that an individual resides at the single
geographic point on the surface of the accessible environment where that
individual would be expected to receive the highest dose from
radionuclide releases from the disposal system.
Sec. 194.52 Consideration of exposure pathways.
In compliance assessments that analyze compliance with Sec. 191.15
of this chapter, all potential exposure pathways from the disposal
system to individuals shall be considered. Compliance assessments with
part 191, subpart C and Sec. 191.15 of this chapter shall assume that
individuals consume 2 liters per day of drinking water from any
underground source of drinking water in the accessible environment.
Sec. 194.53 Consideration of underground sources of drinking water.
In compliance assessments that analyze compliance with part 191,
subpart C of this chapter, all underground sources of drinking water in
the accessible environment that are expected to be affected by the
disposal system over the regulatory time frame shall be considered. In
determining whether underground sources of drinking water are expected
to be affected by the disposal system, underground interconnections
among bodies of surface water, ground water, and underground sources of
drinking water shall be considered.
Sec. 194.54 Scope of compliance assessments.
(a) Any compliance application shall contain compliance assessments
required pursuant to this part. Compliance assessments shall include
information which:
(1) Identifies potential processes, events, or sequences of
processes and events that may occur over the regulatory time frame;
(2) Identifies the processes, events, or sequences of processes and
events included in compliance assessment results provided in any
compliance application; and
(3) Documents why any processes, events, or sequences of processes
and events identified pursuant to paragraph (a)(1) of this section were
not included in compliance assessment results provided in any compliance
application.
(b) Compliance assessments of undisturbed performance shall include
the effects on the disposal system of:
(1) Existing boreholes in the vicinity of the disposal system, with
attention to the pathways they provide for migration of radionuclides
from the site; and
(2) Any activities that occur in the vicinity of the disposal system
prior to or soon after disposal. Such activities shall include, but
shall not be limited to: Existing boreholes and the development of any
existing leases that can be reasonably expected to be developed in the
near future, including boreholes and leases that may be used for fluid
injection activities.
[[Page 53]]
Sec. 194.55 Results of compliance assessments.
(a) Compliance assessments shall consider and document uncertainty
in the performance of the disposal system.
(b) Probability distributions for uncertain disposal system
parameter values used in compliance assessments shall be developed and
documented in any compliance application.
(c) Computational techniques which draw random samples from across
the entire range of values of each probability distribution developed
pursuant to paragraph (b) of this section shall be used to generate a
range of:
(1) Estimated committed effective doses received from all pathways
pursuant to Sec. 194.51 and Sec. 194.52;
(2) Estimated radionuclide concentrations in USDWs pursuant to
Sec. 194.53; and
(3) Estimated dose equivalent received from USDWs pursuant to
Sec. 194.52 and Sec. 194.53.
(d) The number of estimates generated pursuant to paragraph (c) of
this section shall be large enough such that the maximum estimates of
doses and concentrations generated exceed the 99th percentile of the
population of estimates with at least a 0.95 probability.
(e) Any compliance application shall display:
(1) The full range of estimated radiation doses; and
(2) The full range of estimated radionuclide concentrations.
(f) Any compliance application shall document that there is at least
a 95 percent level of statistical confidence that the mean and the
median of the range of estimated radiation doses and the range of
estimated radionuclide concentrations meet the requirements of
Sec. 191.15 and part 191, subpart C of this chapter, respectively.
Subpart D--Public Participation
Sec. 194.61 Advance notice of proposed rulemaking for certification.
(a) Upon receipt of a compliance application submitted pursuant to
section 8(d)(1) of the WIPP LWA and Sec. 194.11, the Agency will publish
in the Federal Register an Advance Notice of Proposed Rulemaking
announcing that a compliance application has been received, soliciting
comment on such application, and announcing the Agency's intent to
conduct a rulemaking to certify whether the WIPP facility will comply
with the disposal regulations.
(b) A copy of the compliance application will be made available for
inspection in Agency dockets established pursuant to Sec. 194.67.
(c) The notice will provide a public comment period of 120 days.
(d) A public hearing concerning the notice will be held if a written
request is received by the Administrator or the Administrator's
authorized representative within 30 calendar days of the date of
publication pursuant to paragraph (a) of this section.
(e) Any comments received on the notice will be made available for
inspection in the dockets established pursuant to Sec. 194.67.
(f) Any comments received on the notice will be provided to the
Department and the Department may submit to the Agency written responses
to the comments.
Sec. 194.62 Notice of proposed rulemaking for certification.
(a) The Administrator will publish a Notice of Proposed Rulemaking
in the Federal Register announcing the Administrator's proposed
decision, pursuant to section 8(d)(1) of the WIPP LWA, whether to issue
a certification that the WIPP facility will comply with the disposal
regulations and soliciting comment on the proposal.
(b) The notice will provide a public comment period of at least 120
days.
(c) The notice will announce public hearings in New Mexico.
(d) Any comments received on the notice will be made available for
inspection in the dockets established pursuant to Sec. 194.67.
Sec. 194.63 Final rule for certification.
(a) The Administrator will publish a Final Rule in the Federal
Register announcing the Administrator's decision, pursuant to section
8(d)(1) of the WIPP LWA, whether to issue a certification that the WIPP
facility will comply with the disposal regulations.
(b) A document summarizing significant comments and issues arising
from
[[Page 54]]
comments received on the Notice of Proposed Rulemaking, as well as the
Administrator's response to such significant comments and issues, will
be prepared and will be made available for inspection in the dockets
established pursuant to Sec. 194.67.
Sec. 194.64 Documentation of continued compliance.
(a) Upon receipt of documentation of continued compliance with the
disposal regulations pursuant to section 8(f) of the WIPP LWA and
Sec. 194.11, the Administrator will publish a notice in the Federal
Register announcing that such documentation has been received,
soliciting comment on such documentation, and announcing the
Administrator's intent to determine whether or not the WIPP facility
continues to be in compliance with the disposal regulations.
(b) Copies of documentation of continued compliance received by the
Administrator will be made available for inspection in the dockets
established pursuant to Sec. 194.67.
(c) The notice will provide a public comment period of at least 30
days after publication pursuant to paragraph (a) of this section.
(d) Any comments received on such notice will be made available for
public inspection in the dockets established pursuant to Sec. 194.67.
(e) Upon completion of review of the documentation of continued
compliance with the disposal regulations, the Administrator will publish
a notice in the Federal Register announcing the Administrator's decision
whether or not to re-certify the WIPP facility.
Sec. 194.65 Notice of proposed rulemaking for modification or revocation.
(a) If the Administrator determines that any changes in activities
or conditions pertaining to the disposal system depart significantly
from the most recent compliance application, the Agency will publish a
Notice of Proposed Rulemaking in the Federal Register announcing the
Administrator's proposed decision on modification or revocation, and
soliciting comment on the proposal.
(b) Any comments received on the notice will be made available for
inspection in the dockets established pursuant to Sec. 194.67.
Sec. 194.66 Final rule for modification or revocation.
(a) The Administrator will publish a Final Rule in the Federal
Register announcing the Administrator's decision on modification or
revocation.
(b) A document summarizing significant comments and issues arising
from comments received on the Notice of Proposed Rulemaking as well as
the Administrator's response to such significant comments and issues
will be prepared and will be made available for inspection in the
dockets established pursuant to Sec. 194.67.
Sec. 194.67 Dockets.
The Agency will establish and maintain dockets in the State of New
Mexico and Washington, DC. The dockets will consist of all relevant,
significant information received from outside parties and all
significant information considered by the Administrator in certifying
whether the WIPP facility will comply with the disposal regulations, in
certifying whether or not the WIPP facility continues to be in
compliance with the disposal regulations, and in determining whether
compliance certification should be modified, suspended or revoked.
PART 195--RADON PROFICIENCY PROGRAMS--Table of Contents
Subpart A--General Provisions
Sec.
Sec. 195.1 Purpose and applicability.
Sec. 195.2 Definitions.
Subpart B--Fees
Sec. 195.20 Fee payments.
Sec. 195.30 Failure to remit fee.
Authority: 15 U.S.C. 2665.
Source: 59 FR 13175, Mar. 18, 1994, unless otherwise noted.
Subpart A--General Provisions
Sec. 195.1 Purpose and applicability.
(a) Purpose. The purpose of this part is to establish and collect
the fees from
[[Page 55]]
applicants and participants required by section 305 of the Toxic
Substances Control Act, U.S.C. 2665 to defray the cost to EPA for
operating the following programs: The National Radon Measurement
Proficiency (RMP) Program, the individual proficiency component of the
RMP Program, and the National Radon Contractor Proficiency (RCP)
Program.
(b) Applicability. This part applies to all applicants and
participants in the following EPA programs: The National Radon
Measurement Proficiency Program, the individual proficiency component of
the RMP Program, and the National Radon Contractor Proficiency Program.
Sec. 195.2 Definitions.
Definitions in 15 U.S.C. 2602 and 2662 apply to this part unless
otherwise specified in this section. In addition, the following
definitions apply:
Acceptance date means the date on which EPA enters the application
into the data system.
Accepted application refers to an application that has been entered
into the data system.
Applicant means an individual or organization that submits an
application to the RMP program, including the individual proficiency
component of the RMP program, or the RCP program. An applicant to the
RMP program must submit a separate application for each location from
which it provides radon measurement services. After the application is
accepted by EPA, the applicant becomes a ``participant'' in the
proficiency programs.
Application means the documents submitted to EPA by applicants to
the RMP and RCP programs which request participation in a program.
Device/measurement device means a unit, component, or system
designed to measure radon gas or radon decay products.
EPA means the U.S. Environmental Protection Agency.
Individual proficiency/RMP exam means the exam which evaluates
individuals who provide radon measurement services in a residential
environment.
Listed participant in an individual or organization who has met all
the requirements for listing in the RMP and RCP programs.
Measurement method is a means of measuring radon gas or radon decay
products encompassing similar measurement devices, sampling techniques,
or analysis procedures.
Organization is any individual, sole proprietorship, partnership,
business, company, corporation, college or university, government agency
(includes Federal, State and local government entities), laboratory, or
institution.
Participant is an individual or organization engaged in radon
measurement and/or mitigation activities or in offering radon
measurement and/or mitigation services to consumers and others, whose
proficiency program application EPA has accepted.
Primary measurement services (primary) refers to radon measurement
services using a specific device which services include the capability
to read and/or analyze the results generated from the device.
Radon Contractor Proficiency (RCP) program refers to EPA's program
to evaluate radon mitigation contractors and the contractor's ability to
communicate information to the public.
Radon Measurement Proficiency (RMP) program refers to EPA's program
to evaluate organizations and individuals offering measurement services
to consumers. It provides a means for organizations to demonstrate their
proficiency in measuring radon and its decay products in indoor air.
Radon mitigation contractor means a contractor who provides radon
mitigation services to the public.
Secondary radon measurement services (secondary) refers to radon
measurement services that do not include the reading or the ability to
analyze the results of the measurement devices used. These services may
include placement and retrieval of devices, reporting results, and/or
consultation with consumers.
Subpart B--Fees
Sec. 195.20 Fee payments.
(a) Fee Amounts. Applicants to and participants in the RMP and RCP
programs shall pay fees according to the following fee schedule:
[[Page 56]]
(1) Organizations Listed for or Seeking Listing for Primary
Measurement Services in the RMP Program. (i) In order to remain a listed
participant, each organization that is listed for primary measurement
services in the RMP program on the effective date of this section shall
pay an annual fee of $390 for each device.
(ii) Each organization seeking listing for primary measurement
services that submits an initial application after the effective date of
this section shall pay an annual fee of $390 per device. This fee will
be prorated quarterly, based on the acceptance date of an organization's
application.
(iii) Organizations that have or are seeking a listing for secondary
measurement services for their primary devices will not be required to
pay the additional $50 fee applicable to secondary organizations.
(2) Organizations Listed for or Seeking Listing for Secondary
Measurement Services in the RMP Program. (i) In order to remain a listed
participant, each organization that is listed for secondary measurement
services in the RMP program on the effective date of this section shall
pay an annual fee of $50 for each business location listed.
(ii) Each organization seeking listing for secondary measurement
services that submits an initial application after the effective date of
this section shall pay an annual fee of $50 for each business location
listed. This fee will be prorated quarterly, based on the acceptance
date of an organization's application.
(iii) Primary organizations that have or are seeking secondary
listings for methods other than those for which they are listed as a
primary, are subject to the fees.
(3) Individual Proficiency Component of the RMP Program. (i) In
order to remain a listed participant, each individual listed in the RMP
individual proficiency program on the effective date of this section
shall pay an annual fee of $105.
(ii) Each individual who submits an initial application after the
effective date of this section shall pay an annual fee of $105. This fee
will be prorated quarterly, based on the acceptance date of an
individual's application.
(iii) Individuals who have or are seeking listing status as an RMP
primary or secondary organization are subject to the applicable fees
under paragraphs (a)(1) and (2) of this section.
(4) RCP Program. (i)(A) In order to remain a listed participant,
each individual listed in the RCP program on the effective date of this
section shall pay an annual fee of $210.
(B) Each individual who is not a listed participant in the RCP
program on the effective date of this section and submits an initial
application after the effective date of this section shall pay an annual
fee of $210. This fee will be prorated quarterly, based on the
acceptance date of an individual's application.
(ii) An organization or individual who is not a listed participant
in EPA's radon proficiency programs on the effective date of this
section and/or whose proficiency program application has not yet been
accepted by EPA becomes subject to the fees described above once its
application has been accepted by EPA. Fees for such organizations or
individuals will be prorated quarterly, based on the acceptance date of
the application. To remain listed, each participant in the RMP or RCP
programs, whether individual or organization, shall submit the
appropriate annual fee to EPA each year.
(b) Exemptions. State and local governments are exempted from these
fees under section 305(e)(2) of TSCA, 15 U.S.C. 2665.
(c) Determination of Fees. (1) Participants listed in the RMP and
RCP programs on the effective date of this section will be sent, by EPA,
a payment invoice with its fee calculation at least 30 days before the
payment is due. Fees will be assessed based on the current information
in EPA's proficiency data bases. Participants who intend to pay the
invoiced fee amount must send their payment to EPA following the
procedures in the invoice. Organizations or individuals who wish to
notify EPA of any errors or corrections they wish to make to their
listing status must do so by following the instructions on the payment
invoice. Corrected payment invoices for both the RMP Program and the RCP
Program shall be sent to: Radon Proficiency
[[Page 57]]
Programs User Fees, c/o Sanford Cohen and Associates, Inc. (SC&A), 1418
I-85 Parkway, Montgomery, Alabama, 36106. EPA will review the
corrections noted on the payment invoice, adjust the payment invoice
amount (as appropriate) and issue a new invoice. Participants must pay
the amount in the corrected payment invoice within 30 days of the date
listed on the corrected invoice.
(2) If the appropriate fee or a revised payment invoice for an
individual or organization participating in the RMP or RCP program has
not been received by EPA on or before the payment due date, EPA will
send, by certified mail, notice that the individual or organization will
be delisted from the proficiency program unless he/she pays the fee
within 30 days of this second certified notification. If payment still
has not been received by EPA after 30 days of the second certified
notification, the organization's or individual's listing shall be
removed from the proficiency program.
(3) New or initial applicants to the RMP or RCP programs will be
assessed a fee at the time of their initial application. EPA will send a
payment invoice to the new applicant upon acceptance of the initial
application. The applicant will be given at least 30 days from the date
on the payment invoice to remit payment. The fee assessed will be
prorated quarterly, based on the acceptance date of the application. If
the appropriate fee has not been received by EPA by the payment due
date, the application will be placed in an inactive file with no further
action taken by EPA.
(d) Payment Procedures. Each remittance to EPA under this section
shall be in United States currency and shall be paid by certified check,
personal or business check, or money order made payable to the order of
the ``U.S. ENVIRONMENTAL PROTECTION AGENCY'' and sent to: U.S. EPA,
Washington Financial Management Center, Radon Proficiency Program User
Fees (IRAA), P.O. Box 952491, St. Louis, Missouri, 63195-2491. The fee
payment shall include the original copy of the EPA payment invoice.
Collection of fees will begin in the calendar year beginning January 1,
1995. Specific guidance on how and when fees must be paid can be found
in How to Pay Your Radon Proficiency Programs User Fees, U.S. EPA/Office
of Radiation and Indoor Air. Copies of this document can be obtained by
contacting the RIS at (334) 272-2797 or by FAX at (334) 260-9051.
(e) Adjustment of Fees. (1) EPA shall collect 100 percent of its
operating costs associated with its radon proficiency programs by
calendar year 1998. As necessary, EPA shall adjust the fees established
by this subpart each year over the next four years to collect the
following percentages of program costs:
------------------------------------------------------------------------
Year 1 Year 2 Year 3 Year 4 Year 5
------------------------------------------------------------------------
30%.......... 47.5% 65% 82.5% 100%
------------------------------------------------------------------------
Actual fees for each fiscal year will be calculated based on program
costs and participation rates. New fee schedules will be published in
the Federal Register as a technical amendment final rule to this part to
become effective 30 days or more after publication.
(2) EPA will use a three-step process to adjust the fees annually.
First, EPA will estimate the costs of providing each of the proficiency
programs for the upcoming year. EPA will account for future additional
fixed costs (e.g., updating examinations) and increases/decreases in
variable costs due to inflation and other factors. In order to calculate
increases/decreases in costs due to inflation, EPA may use one of the
three following indices: the Federal General Schedule (GS) pay scale,
the Consumer Price Index (CPI), and/or a component of the CPI, such as
services. Second, EPA will estimate the number of participants for each
program. At a minimum, these participation rates will be based on past
and current program participation rates. Third, EPA shall calculate the
per capita costs that individuals and organizations should pay to enable
it to recover its fixed and variable costs each year for each program.
EPA shall also consider potential industry impacts as it adjusts to
levels to ultimately achieve full cost recovery over the period of five
years.
[60 FR 41816, Aug. 14, 1995]
[[Page 58]]
Sec. 195.30 Failure to remit fee.
EPA will not process an application or continue a participant's
listing in the National Radon Measurement Proficiency program,
individual proficiency component of the RMP program, or the National
Radon Contractor Proficiency program until the appropriate remittance
provided in Sec. 195.20(a) has been received by EPA. Failure by a
currently EPA-listed organization or individual to remit the required
fees in a timely manner will result in the loss of that organization's
or individual's listing status as specified in Sec. 195.20(c).