Notice2022-10692
Notice of Availability of Final Versatile Test Reactor Environmental Impact Statement
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Published
May 20, 2022
Issuing agencies
Energy Department
Abstract
The U.S. Department of Energy (DOE or the Department) announces the availability of the Final Versatile Test Reactor Environmental Impact Statement (VTR EIS) (DOE/EIS-0542). DOE prepared the VTR EIS in accordance with the National Environmental Policy Act (NEPA) to evaluate the potential environmental impacts of alternatives for constructing and operating VTR and associated facilities for post- irradiation examination of irradiated test specimens and the management of VTR spent nuclear fuel. The Final VTR EIS also evaluates the potential environmental impacts of options for production of VTR driver fuel (the fuel that powers the reactor).
Full Text
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<title>Federal Register, Volume 87 Issue 98 (Friday, May 20, 2022)</title>
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[Federal Register Volume 87, Number 98 (Friday, May 20, 2022)]
[Notices]
[Pages 30931-30933]
From the Federal Register Online via the Government Publishing Office [<a href="http://www.gpo.gov">www.gpo.gov</a>]
[FR Doc No: 2022-10692]
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DEPARTMENT OF ENERGY
Notice of Availability of Final Versatile Test Reactor
Environmental Impact Statement
AGENCY: Office of Nuclear Energy, Department of Energy.
ACTION: Notice of availability.
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SUMMARY: The U.S. Department of Energy (DOE or the Department)
announces the availability of the Final Versatile Test Reactor
Environmental Impact Statement (VTR EIS) (DOE/EIS-0542). DOE prepared
the VTR EIS in accordance with the National Environmental Policy Act
(NEPA) to evaluate the potential environmental impacts of alternatives
for constructing and operating VTR and associated facilities for post-
irradiation examination of irradiated test specimens and the management
of VTR spent nuclear fuel. The Final VTR EIS also evaluates the
potential environmental impacts of options for production of VTR driver
fuel (the fuel that powers the reactor).
DATES: DOE will issue a Record of Decision based on the VTR EIS no
sooner than 30 days after the May 20, 2022, publication of the U.S.
Environmental Protection Agency notice of availability of the Final VTR
EIS in the Federal Register. For alternatives (or options) for which
DOE did not identify a preferred alternative (or option) in the Final
VTR EIS, DOE will not issue a Record of Decision until 30 days after it
announces its preferred alternative (or option) in the Federal
Register.
ADDRESSES: Communications regarding the Final VTR EIS should be sent to
Mr. James Lovejoy, Document Manager, by mail to: U.S. Department of
Energy, Idaho Operations Office, 1955 Fremont Avenue, MS 1235, Idaho
Falls, Idaho 83415; or by email to <a href="/cdn-cgi/l/email-protection#144240463a515d47547a6177787175663a717a7166736d3a737b62"><span class="__cf_email__" data-cfemail="4e181a1c600b071d0e203b2d222b2f3c602b202b3c293760292138">[email protected]</span></a>. The
Final VTR EIS is available for viewing or download at <a href="https://www.energy.gov/nepa">https://www.energy.gov/nepa</a> or <a href="https://www.energy.gov/ne/versatile-test-reactor">https://www.energy.gov/ne/versatile-test-reactor</a>.
FOR FURTHER INFORMATION CONTACT: For information regarding the VTR
Project or the Final VTR EIS, visit <a href="https://www.energy.gov/ne/versatile-test-reactor">https://www.energy.gov/ne/versatile-test-reactor</a>. For questions about the Final VTR EIS or the
analyses therein, contact Mr. James Lovejoy at the mailing address
listed in ADDRESSES; via email at <a href="/cdn-cgi/l/email-protection#e2b4b6b0cca7abb1a28c97818e878390cc878c8790859bcc858d94"><span class="__cf_email__" data-cfemail="94c2c0c6bad1ddc7d4fae1f7f8f1f5e6baf1faf1e6f3edbaf3fbe2">[email protected]</span></a>; or call
(208) 526-6805. For general information on DOE's NEPA process, contact
Mr. Jason Anderson at the mailing address listed in ADDRESSES; via
email at <a href="/cdn-cgi/l/email-protection#f2a4a6a0dcb7bba1b29c87919e979380dc979c9780958bdc959d84"><span class="__cf_email__" data-cfemail="8cdad8dea2c9c5dfcce2f9efe0e9edfea2e9e2e9feebf5a2ebe3fa">[email protected]</span></a>; or call (208) 526-6805.
SUPPLEMENTARY INFORMATION:
Background
Part of the DOE mission is to ensure America's security and
prosperity by addressing its energy, environmental, and nuclear
challenges through transformative science and technology solutions.
Many commercial organizations and universities are pursuing advanced
nuclear energy fuels, materials, and reactor designs that complement
the efforts of DOE and its laboratories in advancing nuclear energy.
These designs include thermal and fast-spectrum \1\ reactors targeting
improved fuel resource utilization and waste management and utilizing
materials other than water for cooling. Development of these designs
requires adequate infrastructure for experimentation, testing, design
evolution, and component qualification. Existing irradiation test
capabilities are aging and some are over 50 years old. The existing
capabilities are focused on testing of materials, fuels, and components
in the thermal neutron spectrum and do not have the ability to support
the needs of fast reactor researchers. Only limited fast-neutron-
spectrum-testing capabilities, with restricted availability, exist
outside the United States. To meet its obligation to support advanced
reactor technology development, DOE needs to develop the capability for
large-scale testing, accelerated testing, and qualification of advanced
nuclear fuels, materials, instrumentation, and sensors. This testing
capability is essential for the United States to modernize its nuclear
[[Page 30932]]
energy infrastructure and for developing transformational nuclear
energy technologies that will play a crucial role in helping the United
States reach net-zero emissions by 2050 while re-establishing the
United States as a world leader in nuclear technology
commercialization.
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\1\ Fast neutrons are highly energetic neutrons (ranging from
0.1 to 10 million electron volts [MeV] and travelling at speeds of
thousands to tens of thousands kilometers per second) emitted during
fission. The fast-neutron spectrum refers to the range of energies
associated with fast neutrons. By contrast, thermal neutrons, such
as those typically associated in a commercial light-water reactor,
are neutrons that are less energetic than fast neutrons (more than a
million times less energetic [about 0.25eV] and travelling at speeds
of less than 5 kilometers per second), having been slowed by
collisions with other materials such as water. The thermal neutron
spectrum refers to the range of energies associated with thermal
neutrons.
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Recognizing that the United States does not have a dedicated fast-
neutron-spectrum testing capability, DOE performed a mission needs
assessment to evaluate current testing capabilities (domestic and
foreign) against the required testing capabilities to support the
development of advanced nuclear technologies. This needs assessment was
consistent with the Nuclear Energy Innovation Capabilities Act (NEICA)
(Pub. L. 115-248) passed in 2018, which directed DOE to assess the
mission need for, and cost of, a versatile reactor-based fast- neutron
source with a high neutron flux, irradiation flexibility, multiple
experimental environment (e.g., coolant) capabilities, and volume for
many concurrent users. The needs assessment identified a gap between
required testing needs and existing capabilities. That is, there
currently is an inability to effectively test advanced nuclear fuels
and materials in a fast-neutron spectrum irradiation environment at
high neutron fluxes. Specifically, the DOE Office of Nuclear Energy
(NE), Nuclear Energy Advisory Committee (NEAC) report, Assessment of
Missions and Requirements for a New U.S. Test Reactor, confirmed that
there was a need in the United States for fast-neutron testing
capabilities, but that there is no facility that is readily available
domestically or internationally. The NEAC study confirmed the
conclusions of an earlier study, the Advanced Demonstration and Test
Reactor Options Study. That study established the strategic objective
that DOE ``provide an irradiation test reactor to support development
and qualification of fuels, materials, and other important components/
items (e.g., control rods, instrumentation) of both thermal and fast
neutron-based advanced reactor systems.''
Following establishment of the mission need described previously,
the VTR Project was formally launched in February 2019 as a part of the
effort to modernize the nuclear research and development user facility
infrastructure in the United States. In later 2020, Congress enacted
the Energy Act of 2020. This legislation, contained within the
Consolidated Appropriations Act, directs the Secretary to provide a
fast-neutron testing capability and revised the completion date from
2025 to 2026.
The Department is committed to reviving and expanding the nuclear
energy infrastructure in the United States. An important step to
achieving this goal is building the VTR in a manner that is protective
of the public and the environment. DOE is announcing the Final VTR EIS
to meet the intent of NEICA and to comply with the Council on
Environmental Quality's Regulations for Implementing the Procedural
Provisions of the National Environmental Policy Act, which require
agencies to ``integrate the NEPA process with other planning at the
earliest possible time to insure that planning and decisions reflect
environmental values, to avoid delays later in the process, and to head
off potential conflicts'' (40 CFR 1501.2).
Alternatives
In addition to a No Action Alternative, the Final VTR EIS evaluates
potential environmental impacts of alternatives for constructing and
operating a VTR. Under the action alternatives, the VTR would be a
small (approximately 300 megawatt thermal) sodium-cooled, pool-type,
metal-fueled reactor. DOE has completed a conceptual design of a fast-
neutron- spectrum reactor based on the Power Reactor Innovative Small
Module (PRISM) design from GE-Hitachi. In addition to constructing and
operating the VTR, the action alternatives include the activities
necessary to perform post-irradiation examination of test specimens and
for the management of spent nuclear fuel from the VTR. After
irradiation in the VTR, test specimens/experimental cartridges would be
transferred to post-irradiation examination facilities where they would
be disassembled so that the specimens can undergo detailed evaluation.
To the extent practical, DOE would make use of existing facilities to
perform post-irradiation examination. Spent driver fuel would be
removed from the VTR each year over its 60-year operating life. The
fuel would be treated (to remove sodium that is used as a bonding
material in fabrication of the fuel) and packaged in containers that
are ready for transport to an offsite storage facility or repository;
no fissile material would be recovered during this treatment process.
Pending shipment offsite, the packaged spent nuclear fuel would be
stored at a facility provided by the VTR project. These activities
would be part of each action alternative. The alternatives evaluated
include establishing the VTR and support activities at the Idaho
National Laboratory (INL) or the Oak Ridge National Laboratory (ORNL).
Idaho National Laboratory Versatile Test Reactor Alternative
Under the INL VTR Alternative, DOE would site the VTR adjacent to
the Materials and Fuels Complex (MFC) at INL and use existing hot cell
and other facilities at the MFC for post-irradiation examination. The
MFC is the location of the Hot Fuel Examination Facility (HFEF), the
Irradiated Materials Characterization Laboratory (IMCL), the
Experimental Fuels Facility (EFF), and other laboratory facilities.
Spent driver fuel would be treated at the Fuel Conditioning Facility
(FCF) and stored at a facility constructed as part of the VTR project.
The INL VTR Alternative is DOE's preferred alternative.
Oak Ridge National Laboratory Versatile Test Reactor Alternative
Under the ORNL VTR Alternative, the VTR would be sited at ORNL at a
location about three quarters of a mile northeast of the High Flux
Isotope Reactor. In addition to constructing the VTR and a facility to
store spent driver fuel, DOE would also construct a new hot cell
facility at this location. The hot cell facility would include
capability and capacity for the initial post- irradiation disassembly
and examination of test specimens and for the treatment of spent VTR
driver fuel. Several existing facilities at ORNL would be used to
provide additional post-irradiation examination capabilities. Hot cells
in the Irradiated Fuels Examination Laboratory and the Irradiated
Materials Examination and Testing Facility would augment the
capabilities in the new hot cell facility. In addition, the Low
Activation Materials Design and Analysis Laboratory would be used for
testing low-dose samples that do not require the use of hot cells.
Reactor Fuel Production
The driver fuel for the VTR would be a metal alloy composed of
uranium, plutonium, and zirconium. Activities to produce reactor fuel
may include feedstock preparation, as well as fuel fabrication. The
Final VTR EIS evaluates the potential environmental impacts of a number
of feedstock preparation activities that would be used to remove
contaminants from the plutonium (called polishing) and to convert
plutonium oxides to metal that can be used in fuel fabrication. The
fabrication steps include creating the alloy; casting the alloy to
create fuel slugs; fabricating fuel pins, including establishing a
sodium bond between the fuel slugs and the encasing tube; and
assembling the tube bundles that would be placed in
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the reactor. DOE evaluates two options for each phase of reactor fuel
production. The feedstock preparation could be performed at either INL
or the Savanah River Site (SRS). Similarly, fuel fabrication activities
could be performed at INL or SRS.
Under the options to perform feedstock preparation and fuel
fabrication at INL, new and existing gloveboxes and equipment would be
used in the Fuel Manufacturing Facility and the building that
previously housed the Zero Power Physics Reactor. Under the options to
perform feedstock preparation and fuel fabrication at SRS, new
gloveboxes and equipment would be installed in a building that
previously housed one of the SRS production reactors. DOE has not
identified a preferred option for reactor fuel production.
Public Involvement
The Final VTR EIS follows the December 2020 release of the Draft
VTR EIS (85 FR 83068). The U.S. Environmental Protection Agency
published its notice of availability on December 31, 2020 (83 FR
86919). DOE accepted comments through March 2, 2021. During the review
and comment period, DOE held two web-based public hearings. DOE
received comments from Federal and state agencies, American Indian
tribes, and the public. In preparing the Final EIS, DOE considered and
responded to the comments received on the Draft EIS. Responses to all
comments are included in Volume 3 of the Final VTR EIS.
Signing Authority
This document of the Department of Energy was signed on May 12,
2022, by Robert Boston, DOE Idaho Operations Office Manager, Office of
Nuclear Energy, pursuant to delegated authority from the Secretary of
Energy. That document with the original signature and date is
maintained by DOE. For administrative purposes only, and in compliance
with requirements of the Office of the Federal Register, the
undersigned DOE Federal Register Liaison Officer has been authorized to
sign and submit the document in electronic format for publication, as
an official document of the Department of Energy. This administrative
process in no way alters the legal effect of this document upon
publication in the Federal Register.
Signed in Washington, DC, on May 13, 2022.
Treena V. Garrett,
Federal Register Liaison Officer, U.S. Department of Energy.
[FR Doc. 2022-10692 Filed 5-19-22; 8:45 am]
BILLING CODE 6450-01-P
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