[Federal Register Volume 84, Number 150 (Monday, August 5, 2019)]
[Notices]
[Pages 38021-38026]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-16578]
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DEPARTMENT OF ENERGY
Notice of Intent To Prepare an Environmental Impact Statement for
a Versatile Test Reactor
AGENCY: Office of Nuclear Energy, Department of Energy.
ACTION: Notice of intent.
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SUMMARY: As required by the ``Nuclear Energy Innovation Capabilities
Act of 2017'' the Department of Energy (DOE) assessed the mission need
for a versatile reactor-based fast-neutron source. Having identified
the need for such a fast-neutron source, the Act directs DOE to
complete construction and approve the start of facility operations, to
the maximum extent practicable, by December 31, 2025. To this end, the
Department intends to prepare an environmental impact statement (EIS)
in accordance with the National Environmental Policy Act (NEPA) and its
implementing regulations. This EIS will evaluate alternatives for a
versatile reactor-based fast-neutron source facility and associated
facilities for the
[[Page 38022]]
preparation, irradiation and post-irradiation examination of test/
experimental fuels and materials.
DATES: DOE invites public comment on the scope of this EIS during a 30-
day public scoping period commencing August 5, 2019, and ending on
September 4, 2019. DOE will hold webcast scoping meetings on August 27,
2019 at 6:00 p.m. ET/4:00 p.m. MT and on August 28, 2019 at 8:00 p.m.
ET/6:00 p.m. MT.
In defining the scope of the EIS, DOE will consider all comments
received or postmarked by the end of the scoping period. Comments
received or postmarked after the scoping period end date will be
considered to the extent practicable.
ADDRESSES: Written comments regarding the scope of this EIS should be
sent to Mr. Gordon McClellan, Document Manager, by mail at: U.S.
Department of Energy, Idaho Operations Office, 1955 Fremont Avenue, MS
1235, Idaho Falls, Idaho 83415; or by email to
[email protected]. To request further information about the
EIS or to be placed on the EIS distribution list, you may use any of
the methods listed in this section. In requesting to be added to the
distribution list, please specify whether you would like to receive a
copy of the Summary and Draft EIS on a compact disk (CD); a printed
copy of the Summary and a CD with the Draft EIS; a full printed copy of
the Summary and Draft EIS; or if you prefer to access the document via
the internet. The Draft EIS and Summary will be available at: https://www.energy.gov/nepa.
FOR FURTHER INFORMATION CONTACT: For information regarding the
Versatile Test Reactor (VTR) Project or the EIS, contact Mr. Gordon
McClellan at the address given above; or email
[email protected]; or call (208) 526-6805. For general
information on DOE's NEPA process, contact Mr. Jason Sturm at the
address given above; or email [email protected]; or call (208)
526-6805.
SUPPLEMENTARY INFORMATION:
Background
Part of the mission of DOE is to advance the energy, environmental,
and nuclear security of the United States and promote scientific and
technological innovation in support of that mission. DOE's 2014-2018
Strategic Plan states that DOE will ``support a more economically
competitive, environmentally responsible, secure and resilient U.S.
energy infrastructure.'' Specifically, ``DOE will continue to explore
advanced concepts in nuclear energy that may lead to new types of
reactors with further safety improvements and reduced environmental and
nonproliferation concerns.''
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 achieving DOE's
goal of 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. Their development requires an 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 for fast
reactors. Only limited fast-neutron-spectrum-testing capabilities, with
restricted availability, exist outside the United States.
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\1\ Fast neutrons are highly energetic neutrons (ranging from
0.1 to 5 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. Thermal neutrons are neutrons that
are less energetic than fast neutrons (more than a million times
less energetic [about 0.025eV] 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 assess 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 of 2017,
or NEICA, (Pub. L. 115-248) 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. This
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 U.S. 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, 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.'' 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 energy infrastructure and for developing
transformational nuclear energy technologies that re-establish the U.S.
as a world leader in nuclear technology commercialization.
The key recommendation of the NEAC report was that ``DOE-NE proceed
immediately with pre-conceptual design planning activities to support a
new test reactor'' to fill the domestic need for a fast-neutron test
capability. The considerations for such a capability include:
An intense, neutron-irradiation environment with
prototypic spectrum to determine irradiation tolerance and chemical
compatibility with other reactor materials, particularly the coolant.
Testing that provides a fundamental understanding of
materials performance, validation of models for more rapid future
development, and engineering-scale validation of materials performance
in support of licensing efforts.
A versatile testing capability to address diverse
technology options and, sustained and adaptable testing environments.
Focused irradiations, either long- or short-term, with
heavily instrumented experimental devices, and the possibility to do
in-situ measurements and quick extraction of samples.
An accelerated schedule to regain and sustain U.S.
technology leadership and to enable the competiveness of U.S-based
industry entities in the advanced reactor markets. This can be achieved
through use of mature technologies for the reactor design (e.g., sodium
coolant
[[Page 38023]]
in a pool-type, metallic-alloy-fueled fast reactor) while enabling
innovative experimentation.
A summary of preliminary requirements that meet these
considerations include:
Provide a high peak neutron flux (neutron energy greater
than 0.1 MeV) with a prototypic fast-reactor-neutron-energy spectrum;
the target flux is 4 x 10\15\ neutrons per square centimeter per second
(neutrons/cm\2\-sec) or greater.
Provide high neutron dose rate for materials testing
[quantified as displacements per atom]; the target is 30 displacements
per atom per year or greater.
Provide an irradiation length that is appropriate for fast
reactor fuel testing; the target is 0.6 to 1 meter.
Provide a large irradiation volume within the core region;
the target is 7 liters.
Provide innovative testing capabilities through
flexibility in testing configuration and testing environment (coolants)
in closed loops.
Provide the ability to test advanced sensors and
instrumentation for the core and test positions.
Expedite experiment life cycle by enabling easy access to
support facilities for experiments fabrication and post-irradiation
examination.
Provide life-cycle management (spent nuclear fuel storage
pending ultimate disposal) for the reactor driver fuel (fuel needed to
run the reactor) while minimizing cost and schedule impacts.
Make the facility available for testing as soon as
possible by using proven technologies with a high technology readiness
level.
Having identified the need for the VTR, NEICA directs DOE ``to the
maximum extent practicable, complete construction of, and approve the
start of operations for, the user facility by not later than December
31, 2025.''
Secretary of Energy Rick Perry announced the launch of the
Versatile Test Reactor Project on February 28, 2019 as a part of
modernizing the nuclear research and development (R&D) user facility
infrastructure in the United States.
An initial evaluation of alternatives during the pre-conceptual
design planning activity recommends the development of a well-
instrumented sodium-cooled, fast-neutron-spectrum test reactor in the
300 megawatt-thermal power level range. This design would provide a
flexible, reconfigurable testing environment for known and anticipated
testing. It is the most practical and cost-effective strategy to meet
the mission need and address constraints and considerations identified
above. The evaluation of alternatives is consistent with the
conclusions of the test reactor options study and the NEAC
recommendation.
DOE expects that the VTR, coupled with the existing supporting R&D
infrastructure, would provide the basic and applied physics, materials
science, nuclear fuels, and advanced sensor communities with a unique
research capability. This capability would enable a comprehensive
understanding of the multi-scale and multi-physics performance of
nuclear fuels and structural materials to support the development and
deployment of advanced nuclear energy systems. To this end, DOE is
collaborating with universities, commercial industry, and national
laboratories to identify needed experimental capabilities.
Purpose and Need for Agency Action
The purpose of this DOE action is to provide a domestic versatile
reactor-based fast-neutron source and associated facilities that meet
identified user needs (e.g., providing a high neutron flux of at least
4 x 10\15\ neutrons/cm\2\-sec and related testing capabilities).
Associated facilities include those for the preparation of driver fuel
and test/experimental fuels and materials and those for the ensuing
examination of the test/experimental fuels and materials; existing
facilities would be used to the extent possible. The United States has
not had a viable domestic fast-neutron-spectrum testing capability for
over two decades. DOE needs to develop this capability to establish the
United States' testing capability for next-generation nuclear
reactors--many of which require a fast-neutron spectrum for operation--
thus enabling the United States to regain technology leadership for the
next generation nuclear fuels, material, and reactors. The lack of a
versatile fast-neutron-spectrum testing capability is a significant
national strategic risk affecting the ability of DOE to fulfill its
mission to advance the energy, environmental, and nuclear security of
the United States and promote scientific and technological innovation.
This testing capability is essential for the United States to modernize
its nuclear energy industry. Further, DOE needs to develop this
capability on an accelerated schedule to avoid further delay in the
United States' ability to develop and deploy advanced nuclear energy
technologies. If this capability is not available to U.S. innovators as
soon as possible, the ongoing shift of nuclear technology dominance to
other international states (e.g., China, the Russian Federation) will
accelerate, to the detriment of the U.S. nuclear industrial sector.
Proposed Action
The Proposed Action is for DOE to construct and operate the VTR at
a suitable DOE site. DOE would utilize existing or expanded,
collocated, post-irradiation examination capabilities as necessary to
accomplish the mission. DOE would use or expand existing facility
capabilities to fabricate VTR driver fuel and test items and to manage
radioactive wastes and spent nuclear fuel.
Versatile Test Reactor
The Nuclear Energy Innovation Capabilities Act of 2017 (Pub. L.
115-248) directed DOE, to the maximum extent practicable, to approve
the start of operations for the user facility by not later than
December 31, 2025. DOE recognized that a near-term deadline would
require the technology selected for the user facility to be a mature
technology, one not requiring significant testing or experimental
efforts to qualify the technology needed to provide the capability.
The generation of a high flux of high-energy or fast neutrons
requires a departure from the light-water-moderated technology of
current U.S. power reactors and use of other reactor moderating and
cooling technologies. The most mature technology that could provide the
high-energy neutron flux is a sodium-cooled reactor, for which
experience with a pool-type configuration and qualification of metallic
alloy fuels affords the desired level of technology maturity and safety
approach. Sodium-cooled reactor technology has been successfully used
in Idaho at the Experimental Breeder Reactor (EBR)-II, in Washington at
the Fast Flux Test Facility, and in Michigan at the Fermi 1 Nuclear
Generating Station.
The current VTR concept would make use of the proven, existing
technologies incorporated in the small, modular GE Hitachi Power
Reactor Innovative Small Module (PRISM) design. The PRISM design \2\
meets the need to use a sodium-cooled, pool-type reactor of proven
(mature) technology. The VTR would be a smaller (approximately 300
megawatt thermal) version of the GE Hitachi
[[Page 38024]]
PRISM power reactor. The reactor, primary heat removal system, and
safety systems would be similar to those of the PRISM design. VTR, like
PRISM, would use metallic alloy fuels. The conceptual design for the
first fuel core of the VTR proposes to utilize a uranium-plutonium-
zirconium alloy fuel. Such an alloy fuel was tested previously in the
EBR-II reactor. Later reactor fuel could consist of other mixtures and
varying enrichments of uranium and plutonium and could use other
alloying metals in place of zirconium.
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\2\ The PRISM design is based on the EBR-II reactor, which
operated for over 30 years. PRISM received a review by the Nuclear
Regulatory Commission as contained in NUREG-1368, Preapplication
Safety Evaluation Report for the Power Reactor Innovative Small
Module (PRISM) Liquid-Metal Reactor, which concluded that ``no
obvious impediments to licensing the PRISM design had been
identified.''
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The VTR core design, however, would differ from the PRISM core in
order to accommodate several positions for test and experimental
assemblies. Additional experiments could be placed in locations
normally occupied by driver fuel in the PRISM reactor. The VTR is not a
power reactor; there would be no PRISM power block for the generation
of electricity. Heat generated by the VTR would be dissipated through
air-cooled heat exchangers; no water would be used in reactor cooling
systems.
The VTR would provide the capability to test fuels, materials,
instrumentation, and sensors for a variety of existing and advanced
reactor designs, including sodium-cooled reactors, lead/lead-bismuth
eutectic-cooled reactors, gas-cooled reactors, and molten salt
reactors. Test vehicles for coolants other than sodium would consist of
closed loops containing the test material enclosed in cartridges that
isolate the experiments from the primary coolant, allowing performance
of tests on different coolant types. Due to the high flux possible in
the VTR, accelerated testing for reactor materials would be possible.
These experiments would extend the state-of-the art knowledge of
reactor technology. Tests and experiments could also be developed that
would improve safeguards technologies. In addition to fast reactor test
and experimentation, the VTR could be used for research on long-term
fuel cycles, fusion reactor materials, and neutrino science/detector
development.
The VTR would not be used as a breeder reactor. All of the driver
fuel removed from the reactor core would be stored to allow radioactive
decay to reduce dose rates, and then conditioned for disposal; no
nuclear materials would be removed from the fuel for the purpose of
reuse.
Post-Irradiation Examination Facilities
Concurrent with the irradiation capabilities provided by the VTR,
the mission need requires the capabilities to examine the test samples
irradiated in the reactor to determine the effects of a high flux of
high-energy or fast neutrons. Typically, the test samples would be
encapsulated in cartridges such that the material being tested is fully
contained. The highly radioactive test sample capsule would be removed
from the reactor after a period of irradiation, ranging from days to
years, depending on the nature of the test requirements, and
transferred to a fully shielded facility where the test item could be
analyzed and evaluated remotely. The examination facilities are ``hot-
cell'' facilities, which include concrete walls several feet thick,
multi-layered, leaded-glass windows several feet thick, and remote
manipulators that allow operators to perform a range of tasks remotely
without incurring substantial radiation dose from the test samples
within the hot cell; in some cases, an inert atmosphere is required to
prevent test sample degradation. DOE intends that the hot-cell
facilities where the test items are examined and analyzed after removal
from the reactor would be in close proximity to the VTR to minimize on-
or offsite transportation of the highly radioactive samples.
Other Support Facilities
Key nuclear infrastructure components required to support the VTR
and post-irradiation examination include:
Facilities for VTR driver fuel and test item fabrication
Facilities for managing radioactive wastes
Facilities for management of irradiated VTR driver fuel
Nuclear materials for the VTR driver fuel could come from several
locations including from within the DOE complex, commercial facilities,
or possibly foreign sources. The nuclear materials and zirconium would
be alloyed and formed into ingots from which the fuel would be
fabricated. The alloy ingots could be produced at one of the locations
providing the nuclear materials or the materials could be shipped to a
location within the DOE complex for creating the alloy. DOE anticipates
fabricating driver fuel from the ingots at the Savanah River site or
the Idaho National Laboratory.
DOE would collaborate with a range of university, commercial
industry, and national laboratory partners for experiment development.
Fabrication of the test and experimental modules could occur at DOE
facilities or at the university or commercial industry partners'
facilities.
Preliminary Description of Alternatives
As required by the Council on Environmental Quality and DOE NEPA
implementing regulations at 40 CFR parts 1500-1508 and 10 CFR part
1021, respectively, DOE will evaluate a range of reasonable
alternatives for the construction and operation of a VTR and its
associated facilities. As required by NEPA, the alternatives will
include a No Action Alternative to serve as a basis for comparison with
the action alternatives.
Specific action alternatives proposed for analysis in the EIS
include alternative DOE national laboratory sites for the construction
and operation of the VTR and the provision of post-irradiation
examination. Under all action alternatives and as described previously,
the VTR would be a small (approximately 300 megawatt thermal), sodium-
cooled, pool-type, metal-fueled reactor based on the GE Hitachi PRISM
power reactor. DOE projects approval for the start of operations to
occur as early as the end of 2026.
There are ancillary activities necessary to support any of the
action alternatives. These include the fabrication of driver fuel, the
assembly of test/experimental modules at existing, modified or newly
constructed test/experiment assembly facilities, and the management of
waste and spent nuclear fuel. After irradiation in the VTR, test/
experimental cartridges would be transferred to post irradiation
examination facilities. DOE would make use of existing facilities to
the extent possible, but these post-irradiation examination facilities
may require modification or expansion. These activities would be part
of each action alternative.
1. Idaho National Laboratory (INL) VTR Alternative
Under the INL VTR Alternative, DOE would site the VTR at the
Materials and Fuels Complex (MFC) at INL and use existing hot-cell and
other facilities at the MFC for post-irradiation examination. This area
of INL is the location of the Hot Fuel Examination Facility (HFEF), the
Irradiated Materials Characterization Laboratory (IMCL), the
Experimental Fuels Facility (EFF), the Fuel Conditioning Facility
(FCF), and the decommissioned Zero Power Physics Reactor (ZPPR). The
existing security fence would be expanded to include VTR.
The existing facilities within the MFC would be modified as
necessary to support fabrication of VTR driver fuel or test items and
to support post-irradiation examination of irradiated
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targets withdrawn from the VTR. These types of activities are ongoing
within the MFC. Under the conceptual design, the existing
infrastructure including utilities and waste management facilities
would be utilized to support construction and operation of the VTR.
While some modifications and upgrades to the infrastructure might be
necessary, the current infrastructure should be largely adequate to
support the VTR.
The post-irradiation examination capabilities at MFC, including
existing facilities, equipment, technical, engineering and support
staff, would be capable of supporting the anticipated post-irradiation
examination activities that the VTR would create. The potential
increase in workload among the MFC facilities in the post-startup
timeframe might require increased technical and operating staff.
Driver fuel for the VTR would likely be manufactured at the MFC or
the Savanah River site, depending on multiple factors including the
source of the nuclear material and the availability and capabilities of
DOE, commercial, or foreign suppliers.
2. Oak Ridge National Laboratory (ORNL) VTR Alternative
Under the ORNL VTR Alternative, the VTR would be sited at ORNL at a
location to be identified.
Several existing facilities would be used and/or modified to
provide operational support and needed post irradiation examination
capabilities. The existing Irradiated Fuels Examination Laboratory
(IFEL) Building 3525 and the Irradiated Materials Examination and
Testing (IMET) Building 3025E hot cell facility would be used to
support post irradiation examination and material testing. The IFEL is
a Category 2 nuclear facility and contains hot cells that are currently
used for examination of a wide variety of fuels. The IMET is a Category
3 nuclear facility and contains hot cells that are used for mechanical
testing and examination of highly irradiated structural alloys and
ceramics. Both facilities would need modifications to accommodate VTR
work activities.
The existing Radiochemical Engineering Development Center (REDC)
also would be used to support VTR operations. REDC consists of two hot-
cell facilities, both constructed during the mid-1960s. REDC operates
in conjunction with ORNL's High Flux Isotope Reactor (HFIR) in remote
and hands-on fabrication of targets for irradiation and subsequent
processing and recovery of valuable radioisotopes. The existing
capabilities of the REDC may not be adequate to support the anticipated
workload from the VTR and would need to be modified or expanded.
Existing glovebox laboratories in Building 7920, currently used for
chemical extraction and processing, could be used for fuel and/or test
item fabrication. Building 7930 houses heavily shielded hot cells and
analytical laboratories that could be used for remote examination of
irradiated fuels and test items.
Driver fuel for the VTR would likely be manufactured elsewhere,
depending on a number of factors including the source of the nuclear
material and the availability and capabilities of DOE, commercial, or
foreign suppliers.
3. No Action Alternative--Do Not Construct a VTR
As required by NEPA, DOE will include a No Action Alternative to
serve as a basis for comparison with the action alternatives. Under the
No Action alternative, DOE would not pursue the construction and
operation of a VTR and would make use of the limited capabilities of
existing facilities to the extent they are capable and available for
testing in the fast-neutron-flux spectrum.
Potential Environmental Issues for Analysis
DOE proposes to address the issues listed in this section when
considering the potential impacts of the construction and operations of
the proposed facilities (the VTR and associated pre- and post-
irradiation facilities) and the transportation of materials (non-
irradiated fuel, irradiated [spent] fuel and test materials, and
waste):
Potential effects on public health from exposure to
radionuclides under routine and credible accident scenarios including
natural disasters: Floods, hurricanes, tornadoes, and seismic events.
Potential impacts on surface and groundwater, floodplains
and wetlands, and on water use and quality.
Potential impacts on air quality (including global climate
change) and noise.
Potential impacts on plants, animals, and their habitats,
including species that are Federal- or state-listed as threatened or
endangered, or of special concern.
Potential impacts on geology and soils.
Potential impacts on cultural resources such as historic,
archeologic, and Native American culturally important sites.
Socioeconomic impacts on potentially affected communities.
Potential disproportionately high and adverse effects on
minority and low-income populations.
Potential impacts on land-use plans, policies and
controls, and visual resources.
Potential impacts on waste management practices and
activities.
Potential impacts of intentional destructive acts,
including sabotage and terrorism.
Unavoidable adverse impacts and irreversible and
irretrievable commitments of resources.
Potential cumulative environmental effects of past,
present, and reasonably foreseeable future actions.
Compliance with all applicable Federal, state, and local
statutes and regulations, and with international agreements, and
required Federal and state environmental permits, consultations and
notifications.
Public Scoping Process
NEPA implementing regulations require an early and open process for
determining the scope of an EIS and for identifying the significant
issues related to the proposed action. To ensure that a full range of
issues related to the proposed action are addressed, DOE invites
Federal agencies, state, local, and tribal governments, the general
public and the international community to comment on the scope of the
EIS. Specifically, DOE invites comment on the identification of
reasonable alternatives and specific environmental issues to be
addressed. Analysis of written and oral public comments provided during
the scoping period will help DOE further identify concerns and
potential issues to be considered in the Draft EIS.
Webcast Scoping Meeting Information
DOE will host two interactive webcasts during the scoping period as
listed under DATES. The purpose of the webcasts is two-fold--the first
is to provide the public with information about the NEPA process and
the VTR Project. The second purpose is to invite public comments on the
scope of the EIS.
The webcasts will begin with presentations on the NEPA process and
the VTR Project. Following the presentations, there will be a moderated
session during which members of the public can provide oral comments on
the scope of the EIS analysis. Commenters will be allowed 3 minutes to
provide comments. Comments will be recorded. Note that providing oral
comments will require joining the meeting by phone.
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Members of the public who would like to provide oral comments can
pre-register by sending an email to [email protected].
Alternatively, participants will be able to request to speak during the
webcast. Those who pre-register should indicate at which session they
want to speak and their name.
If you are joining the webcast scoping meeting via internet, copy
and paste the link below to login to the meeting site, then follow the
prompts. If you are joining the webcast meeting via phone, dial the
U.S. toll-free number below and follow the prompts. Comments will be
accepted during the webcast meeting, by mail, and by email.
Join webcast scoping meeting via the internet:
August 27: https://78449.themediaframe.com/dataconf/productusers/ldos/mediaframe/31759/indexl.html.
August 28: https://78449.themediaframe.com/dataconf/productusers/ldos/mediaframe/31762/indexl.html.
(Copy and Paste into web browser).
Join webcast public meeting by phone: U.S. toll-free: 877-
869-3847.
Signed in Washington, DC on July 29, 2019.
Dennis Miotla,
Chief Operating Officer for Nuclear Energy.
[FR Doc. 2019-16578 Filed 8-2-19; 8:45 am]
BILLING CODE 6450-01-P