83 FR 9847 - Interim Management of Nuclear Materials; Spent Nuclear Fuel Management at Savannah River Site

DEPARTMENT OF ENERGY

Federal Register Volume 83, Issue 46 (March 8, 2018)

Page Range		9847-9850
FR Document		2018-04670
The Department of Energy (DOE) is amending its record of decision (ROD) (published in the Federal Register on December 19, 1995) for the Final Environmental Impact Statement: Interim Management of Nuclear Materials at the Savannah River Site (IMNM EIS) (DOE/EIS-0220) and its ROD (published in the Federal Register on; August 7, 2000) for the Savannah River Site Spent Nuclear Fuel Management Environmental Impact Statement (SRS SNF EIS) (DOE/EIS-0279) with respect to management of 65 Mark-18A targets. The IMNM EIS evaluated the potential environmental consequences of alternatives for the disposition of a large number and variety of nuclear materials, including 65 Mark-18A targets. These targets were irradiated in a nuclear reactor at the Savannah River Site (SRS) to produce valued isotopes. The SRS SNF EIS evaluated the potential environmental consequences from alternatives for managing spent nuclear fuel at SRS, as well as other irradiated materials including the 65 Mark-18A targets. In both the IMNM EIS and SRS SNF EIS RODs, DOE decided to continue to store the 65 Mark-18A targets at SRS. DOE has now decided to process the 65 Mark-18A targets at SRS to recover valued isotopes in the form of solid oxides and to issue this amended ROD.
Federal Register, Volume 83 Issue 46 (Thursday, March 8, 2018)
[Federal Register Volume 83, Number 46 (Thursday, March 8, 2018)]
[Notices]
[Pages 9847-9850]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2018-04670]


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DEPARTMENT OF ENERGY


Interim Management of Nuclear Materials; Spent Nuclear Fuel 
Management at Savannah River Site

AGENCY: Office of Environmental Management, U.S. Department of Energy.

ACTION: Amended record of decision.

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SUMMARY: The Department of Energy (DOE) is amending its record of 
decision (ROD) (published in the Federal Register on December 19, 1995) 
for the Final Environmental Impact Statement: Interim Management of 
Nuclear Materials at the Savannah River Site (IMNM EIS) (DOE/EIS-0220) 
and its ROD (published in the Federal Register on; August 7, 2000) for 
the Savannah River Site Spent Nuclear Fuel Management Environmental 
Impact Statement (SRS SNF EIS) (DOE/EIS-0279) with respect to 
management of 65 Mark-18A targets. The IMNM EIS evaluated the potential 
environmental consequences of alternatives for the disposition of a 
large number and variety of nuclear materials, including 65 Mark-18A 
targets. These targets were irradiated in a nuclear reactor at the 
Savannah River Site (SRS) to produce valued isotopes. The SRS SNF EIS 
evaluated the potential environmental consequences from alternatives 
for managing spent nuclear fuel at SRS, as well as other irradiated 
materials including the 65 Mark-18A targets. In both the IMNM EIS and 
SRS SNF EIS RODs, DOE decided to continue to store the 65 Mark-18A 
targets at SRS. DOE has now decided to process the 65 Mark-18A targets 
at SRS to recover valued isotopes in the form of solid oxides and to 
issue this amended ROD.

FOR FURTHER INFORMATION CONTACT: For further information on this 
Amended ROD, or to receive related NEPA documents, please contact: Ms. 
Tracy L. Williams, NEPA Compliance Officer, Savannah River Operations 
Office, U.S. Department of Energy, P.O. Box B, Aiken, South Carolina 
29802; (803) 952-8278; or [email protected]. For information on 
DOE's NEPA process, please contact: Mr. Brian Costner, Acting Director, 
Office of NEPA Policy and Compliance (GC-54), U.S. Department of 
Energy, 1000 Independence Avenue SW, Washington, DC 20505; (202) 586-
4600; or leave a message at (800) 472-2756. This Amended ROD and 
related NEPA documents are available on the DOE NEPA website at 
www.energy.gov/nepa.

SUPPLEMENTARY INFORMATION: 

Background

A. Mark-18A Targets and Action

    DOE has decided to process the 65 Mark-18A targets at SRS to 
recover the \244\Pu and other valued isotopes in the form of solid 
oxides. Processing activities at SRS will occur at the Savannah River 
National Laboratory (SRNL) Shielded Cells Facility (SCF) in A-Area. 
These oxides will be transported to Oak Ridge National Laboratory 
(ORNL) in Tennessee for further processing and material recovery. 
Processing activities at ORNL will take place in accordance with its 
continuing research and development (R&D) mission.
    DOE manages materials containing long-lived isotopes produced from 
irradiating targets in nuclear reactors. A target is an object, 
typically a closed cylinder containing radioactive or nonradioactive 
material, placed within a nuclear reactor so that the material within 
the target may be bombarded by neutrons to produce desired isotopes.
    One reactor at SRS was configured to generate a high concentration 
of neutrons in order to produce isotopes for defense purposes, other 
DOE programmatic applications, and scientific research. Eighty-six 
Mark-18A targets were irradiated in this reactor, producing \244\Pu and 
other isotopes including \252\Cf and heavy curium. Twenty-one of the 86 
targets were processed at ORNL from 1971 through 1973 to recover these 
isotopes. The \244\Pu was apportioned to scientists for basic research 
and safeguards programs while the heavy curium was processed into 
targets for production of \252\Cf and other isotopes for medical and 
industrial uses. The remaining 65 targets were originally stored at SRS 
in the Receiving Basin for Offsite Fuels in H-Area, but are now stored 
in the L-Basin.
    Since the 1970s the 21 irradiated and processed Mark-18A targets 
have provided the world's supplies of \244\Pu and heavy curium, and the 
65 remaining targets represent the only practical source of additional 
supply.\244\Pu is a critical component of certified standards for high-
precision laboratory analyses supporting nuclear forensics and nuclear 
non-proliferation, while heavy curium is needed as production feed for 
other isotopes such as \252\Cf. Current international supplies of both 
\244\Pu and heavy curium are nearly depleted.
    To ensure the availability of \244\Pu and other valued isotopes, 
DOE will retrieve the 65 Mark-18A targets from storage in the L-Basin 
and process them in the SRNL SCF. The targets will be transported to 
the SRNL SCF (in the SRS A-Area) in a shipping cask modified to provide 
enhanced shielding against neutron radiation and to accommodate the 
radiation spectrum of the targets (e.g., shielding using lighter 
elements). Each cask will contain one Mark-18A target consistent with 
the cask's physical and safety analysis constraints. No modifications 
are needed at the L-Basin to retrieve the targets.
    At the SRNL SCF, the targets will be taken into shielded cells 
where the aluminum cladding will be chemically removed. The target 
material will be dissolved and the plutonium in the resulting solution 
separated from curium, americium, and fission products. The plutonium 
solution will be converted to oxide as will the solution containing the 
curium, americium, and fission products. Both oxides will be 
transported to ORNL using packaging that has been certified in 
accordance with U.S. Department of Transportation (DOT) and U.S. 
Nuclear Regulatory Commission (NRC) regulations.
    These operations are similar to activities performed at the SRNL 
SCF from the 1960s through the 1980s to process and recover actinides, 
and will be performed consistent with this facility's safety analysis 
constraints. Minor modifications, such as installation of special 
handling tools and temporary shielding, will be made at the SRNL SCF to 
configure it to facilitate safe receipt of the modified shipping cask 
and transfer of the targets to the shielded cells.
    Additional processing and material recovery will occur at ORNL. 
Processing activities will be performed in existing facilities as part 
of ORNL's continuing R&D mission. These ORNL mission activities are 
covered under an existing NEPA Categorical Exclusion determination, 
3059X (June 9, 2005).

B. NEPA Reviews and Decisions

    In the IMNM EIS, DOE evaluated the potential impacts of 
alternatives for interim management of a variety of nuclear materials 
stored at SRS. The major categories of nuclear material considered in 
the IMNM EIS were Stable Materials, Programmatic Materials, and 
Candidate Materials for Stabilization (60 FR 65315; December 19, 1995):

[[Page 9848]]

     Stable Materials. Materials that were unlikely to present 
a safety concern over the next 10 years and were stable and suitable 
for continued storage. These materials included 65 Mark-18A targets 
containing about 1.1 kilograms of nuclear material, as well as about 
380,000 discrete items including other types of irradiated targets, 
spent nuclear fuel, R&D material, and reactor materials such as control 
rods, plus about 700,000 liters (78,000 gallons) of depleted uranium 
solutions.
     Programmatic Materials. Materials that DOE needed to meet 
current or future program missions, mostly in a liquid form. These 
materials included 33,100 liters (8,900 gallons) of plutonium, 
americium, curium, and neptunium solutions, and 248 discrete solid 
items such as irradiated fuel assemblies, targets, and slugs. The 65 
Mark-18A targets were also evaluated in this category.
     Candidate Materials for Stabilization. Materials 
determined to be in a physical form or storage configuration that could 
present a safety concern within the next 10 years. These materials 
included a variety of irradiated targets and nuclear fuels, and other 
materials including 16,000 Mark-31 targets containing 147 metric tons 
(160 tons) of nuclear material (primarily uranium-238 and plutonium-239 
[\239\Pu]) and 3,450 Mark-16 and Mark-22 irradiated nuclear fuels. The 
total included about 22,600 discrete solid items as well as 34,000 
liters (9,000 gallons) of \239\Pu solutions and 228,000 liters (60,000 
gallons) of enriched uranium solutions. The alternatives differed 
depending on the category of nuclear material. For Stable Materials, 
DOE evaluated a No Action (continued storage) Alternative. For 
Programmatic Materials, including 65 Mark-18A targets, and Candidate 
Materials for Stabilization, DOE evaluated a range of action 
alternatives. One of the action alternatives evaluated was a Processing 
to Oxide Alternative under which the materials would be processed to an 
oxide using the separations capabilities in F- and H-Canyons.
    In the IMNM EIS ROD, DOE decided to implement the No Action 
Alternative for Stable Materials, including the 65 Mark-18A targets. 
However, DOE recognized the targets as Programmatic Materials. DOE 
indicated that storage would continue until ``DOE makes decisions 
relative to their future use or disposition'' (60 FR 65301; December 
19, 1995), and that the Processing to Oxide Alternative as applied to 
americium and curium solutions could be used for ``targets and slugs 
containing americium and curium isotopes'' (60 FR 65306; December 19, 
1995), a group of materials that includes the 65 Mark-18A targets.
    In the SRS SNF EIS, DOE evaluated technologies and five broad 
categories of alternatives (including processing in H-Area at SRS) for 
the management of about 68 metric tons of heavy metal (MTHM) of 
aluminum-clad spent nuclear fuel, about 20 MTHM of stainless-steel or 
zirconium-clad spent nuclear fuel, and other nuclear materials. With 
respect to the 65 Mark-18A targets, the SRS SNF EIS evaluated the 
impacts from continued storage at SRS, repackaging and shipping to 
another DOE site, and processing in H-Canyon at SRS with discharge to 
the liquid waste system and verification at DWPF. In the SRS SNF EIS 
ROD, DOE decided to continue to store the 65 Mark-18A targets at SRS.

Supplement Analysis and Summary of Impacts

    In accordance with the National Environmental Policy Act (NEPA) and 
DOE's implementing NEPA regulations, DOE prepared the Supplement 
Analysis of the Mark-18A Target Material Recovery Program at the 
Savannah River Site (Mark-18A SA, DOE/EIS-0220-SA-02 and DOE/EIS-0279-
SA-06, dated December 9, 2016) to evaluate whether the proposed action 
requires supplementing the existing IMNM EIS and SRS SNF EIS, or 
preparing a new EIS. The Mark-18A SA updates the evaluations from the 
IMNM EIS and SRS SNF EIS to reflect the changes in SRS facilities where 
the 65 Mark-18A targets will be managed, along with associated onsite 
transportation. The Mark-18A SA also evaluates the potential impacts of 
transporting the oxide resulting from processing the 65 Mark-18A 
targets to ORNL.
    The Mark-18A SA concluded that the environmental consequences of 
the proposed action would be very small and would not constitute 
substantial changes relative to the analyses and conclusions in the 
IMNM EIS and SRS SNF EIS, and that there are not significant new 
circumstances or information relevant to environmental concerns and 
bearing on the action or its impacts. Therefore, no further NEPA 
analysis is required.

A. IMNM EIS and SRS SNF EIS

    In the IMNM EIS, DOE determined that any of the alternatives where 
the materials would be processed at the large separations facilities at 
SRS (i.e., F- or H-Canyon) would have larger environmental impacts than 
alternatives involving continued interim storage, but the potential 
health effects of processing alternatives would be low and well within 
regulatory limits. No latent cancer fatalities (LCFs) were expected for 
members of the public and 1 LCF was projected for workers. The 
potential for accidents involving the processed and stabilized 
materials would be reduced, and some types of accidents would no longer 
be possible.
    The IMNM EIS also evaluated risks from onsite transportation of 
nuclear materials between SRS facilities. No radiation exposures were 
projected to members of the public from incident-free transport of the 
materials and no LCFs from radiation exposure were projected to 
workers. No LCFs to onsite or offsite populations or an offsite 
maximally exposed individual (MEI) were projected from potential 
transportation accidents considering a range of accidents from the very 
minor to the very severe.
    The IMNM EIS determined that implementing any of the alternatives 
would result in little or no impacts on geologic resources, ecological 
resources, cultural resources, aesthetic and scenic resources, noise, 
or land use. Emissions of hazardous air pollutants and releases of 
hazardous effluents would be well within regulatory standards and 
existing permitting limits for the SRS facilities. None of the 
alternatives would result in emissions of radioactive or nonradioactive 
constituents resulting in disproportionate impacts on minority or low-
income communities in the vicinity of SRS. Management of high-level 
liquid, transuranic (TRU), low-level radioactive waste (LLW), mixed 
low-level radioactive waste (MLLW), and hazardous waste would be within 
the capacities of existing SRS waste management facilities.
    The action addressed in this amended ROD will revise previously 
evaluated operations for the 65 Mark-18A targets evaluated in the IMNM 
EIS under the alternatives requiring processing operations at the SRS 
separations facilities. It will entail processing operations similar to 
those evaluated for tens of thousands of gallons of liquid nuclear 
solutions and tens of thousands of discrete solid items including the 
Mark-18A and Mark-31 targets and the Mark-16 and Mark-22 irradiated 
nuclear fuels. For example, the 1.1 kilograms of plutonium, americium, 
curium, and californium in the 65 Mark-18A targets represents about 7 x 
10 ^-4 percent (about 1/140,000) of the mass of the nuclear 
material contained in 16,000 Mark-31 targets evaluated in the IMNM EIS 
and subsequently processed in F-Canyon.

[[Page 9849]]

    The very small quantity of material addressed by the proposed 
action indicates that the proposed action will have only negligible 
impacts and represent a negligible change to the potential 
environmental consequences evaluated in the IMNM EIS. This conclusion 
is supported by the SRS SNF EIS which evaluated the impacts from 
processing the 65 Mark-18A targets at H-Canyon. DOE determined that 
processing all 65 Mark-18A targets at H-Canyon would result in a total 
radiation dose to an offsite MEI of 0.0035 millirem. Byproducts of the 
action addressed in this amended ROD will be similar in type to the 
byproducts of other nuclear material processed at SRS (e.g., Mark-31 
targets) and evaluated in the SRS SNF EIS. In the SRS SNF EIS ROD, DOE 
decided to continue to store the 65 Mark-18A targets at the L-Basin.
    The Mark-18A SA updates the evaluations from the IMNM EIS and SRS 
SNF EIS to reflect the changes in SRS facilities where the 65 Mark-18A 
targets will be managed: (1) Targets are now stored at the L-Basin 
(rather than the Receiving Basin for Offsite Fuels); (2) processing 
will occur at the SRNL SCF (rather than F- or H-Canyons); and (3) the 
65 Mark-18A targets will be transported onsite from the L-Basin to the 
SRNL SCF. In addition, the Mark-18A SA evaluates the potential impacts 
of transporting the oxide from processing the 65 Mark-18A targets from 
SRS to ORNL, an activity not specifically evaluated in the IMNM EIS or 
the SRS SNF EIS.

B. Modifications to Previously Evaluated Activities

    Considering the operational changes that will be required for 
implementing the Conversion to Oxide Alternative for the Mark-18A 
targets (minor modifications to the SRNL SCF cells, temporary 
shielding, equipment removal at the end of processing), DOE re-
evaluated the potential environmental consequences that could result, 
focusing on potential human health impacts; geologic, ecological, 
cultural, aesthetic, and scenic resources; noise; land use; waste 
generation and management; and cumulative impacts.
    L-Basin Retrieval and Onsite Transportation to the SRNL SCF. 
Removal of the 65 Mark-18A targets from the L-Basin will involve the 
same routine operations as those for other targets and spent nuclear 
fuel assemblies. Incident-free retrieval of targets from the L-Basin 
and transport to the SRNL SCF would not be expected to result in 
radiation doses and risks to members of the public in addition to those 
currently experienced. In addition, it is not expected that the 
proposed action would introduce additional accident risks. Potential 
radiation exposures to transport workers are expected to be within DOE 
regulations and be maintained at levels as low as reasonably 
achievable. Risks to workers from potential accidents will be 
comparable to or smaller than the risks evaluated in the SRS SNF EIS 
for onsite transfer of spent nuclear fuel. The action will not 
introduce additional accident risks to those evaluated in the SRS SNF 
EIS.
    SRNL SCF Processing. Processing activities at SRS will occur at the 
SRNL SCF in A-Area rather than at F- and/or H-Canyons as evaluated in 
the IMNM EIS and SRS SNF EIS. Whereas F- and H-Canyons are designed to 
process large quantities of materials, there are only about 21 grams of 
\244\Pu in the 65 Mark-18A targets. The SRNL SCF is a more appropriate 
facility for performing the separations and recovery of the 
comparatively small quantities of materials involved.
    Processing the targets will involve activities similar to those 
previously and currently conducted at the SRNL SCF. Operations will be 
performed within the SRNL safety and environmental basis, and will 
comply with DOE regulations, directives, and best management practices 
to minimize radiation exposures to workers and risks from industrial 
accidents or hazardous materials. Processing the 65 Mark-18A targets at 
the SRNL SCF will be within the scope of routine operations under its 
R&D mission. Although operations will vent nonradioactive volatile 
gases (nitrogen oxides, nitric acid, hydrogen) and fission products 
(krypton, xenon, iodine) through SRNL's E-wing ventilation system and 
the 791-A Sand filter stack, less than 100 liters of volatile compounds 
will be vented per target (6,500 liters total over a period of nine 
years).
    Releases of both nonradioactive volatile gases and fission products 
will be well below levels of potential regulatory or procedural impact. 
Releases of fission products will be within the facility operating 
basis of 0.1 millirem per year (a procedural guideline to monitor SRNL 
activities) and no additional sampling or approval from the South 
Carolina Department of Health and Environmental Control will be 
required. Therefore, minimal impacts to members of the public or to 
noninvolved workers are expected from processing the 65 Mark-18A 
targets. Including Mark-18A target processing, operations at the SRNL 
SCF will be conducted so radioactive and nonradioactive emissions from 
all activities will be within its existing basis of operations and the 
requirements for protection of the public under the National Emission 
Standards for Hazardous Air Pollutants.
    Offsite Transportation. Oxides recovered at the SRNL SCF will be 
prepared for transport to ORNL using packaging that has been certified 
in accordance with DOT and NRC regulations. All activities will be 
compliant with Federal regulations and DOE directives. DOE anticipates 
making approximately 65 shipments using Type A packaging (e.g., Type 
S300 special form configuration) for the americium/curium/fission 
product oxides and approximately 8 shipments using Type B packaging 
(e.g., Type 9975 or Type 9977) for the plutonium oxides. These Type A 
and Type B packages are approved for much larger quantities of 
radioactive materials than those projected for each shipment.
    DOE evaluated the potential impacts to transport crews and members 
of the public by scaling the analysis in the SRS SNF EIS for 1,400 
shipments of spent nuclear fuel from SRS to a geologic repository, 
considering the smaller number of expected shipments to ORNL (nominally 
65 shipments of americium/curium/fission products and nominally 8 
shipments of plutonium oxide), and risk factors appropriate for the 
populations along the evaluated transport route to ORNL. No LCFs 
(0.0015 calculated) are expected among transport crews or the general 
population (0.004 calculated) during incident-free transport. The risk 
of an LCF to the general population considering the range of potential 
accidents, from minor to severe, was determined to be about 6 x 
10^-\7\ (one chance of a fatal cancer in about 1.7 million) 
from all transport of the oxides, while the risk of a non-radiological 
accident fatality was determined to be 0.007 (1 chance in 140 of a 
fatality).
    Other Resource Areas. Under this decision, only minor modifications 
will occur within the existing SRNL SCF building (modifications to the 
SRNL SCF cells, temporary shielding, and equipment removal at the end 
of processing) in an industrialized portion of SRS, and operations will 
entail activities at existing facilities that are similar to those 
previously and currently conducted at SRS. Thus, there will be no 
change in land use and no impacts on soil and geology, or on visual, 
ecological, or cultural resources. There will be no discernible 
increase in noise above current levels. There will be no need for 
additional personnel, resulting in minimal socioeconomic impacts, and 
no change in impacts on

[[Page 9850]]

infrastructure (e.g., utilities), surface water resources, or 
groundwater resources from operation of the L-Basin and the SRNL SCF.
    Wastes will be generated primarily during operations at the SRNL 
SCF and will include laboratory samples, scrap, and contaminated 
equipment such as pipettes or gloves. These wastes will primarily 
consist of solid or liquid LLW, MLLW, and TRU waste that will be 
managed within the capacities of existing SRS waste management 
operations. Solid LLW will be disposed of onsite in E-Area, while MLLW 
will be shipped offsite for treatment and disposal in accordance with 
the Final Programmatic EIS for Managing Treatment, Storage, and 
Disposal of Radioactive and Hazardous Waste (DOE/EIS-0200) and amended 
ROD (65 FR 10061; February 25, 2000). Liquid waste will be discarded to 
the SRNL liquid radioactive waste system, or combined with an absorbent 
for disposal as LLW or management as MLLW. TRU waste will be stored on-
site in the SRS E-Area Solid Waste Facility until shipped to the Waste 
Isolation Pilot Plant for disposal.
    Cumulative Impacts. The action addressed in this amended ROD will 
require activities at existing SRS facilities that are the same as or 
comparable to past and present operations at these facilities. 
Therefore, the action addressed in this amended ROD is not expected to 
result in increases to the ranges of cumulative impacts evaluated in 
the IMNM EIS and SRS SNF EIS.

C. Supplement Analysis Conclusion

    The action addressed in this amended ROD will revise the management 
approach for a very small fraction of the materials evaluated in the 
IMNM EIS and SRS SNF EIS. The operational changes at SRS that will be 
required for implementing the action are expected to have only minor 
environmental consequences.

Environmentally Preferable Alternative

    In the IMNM EIS and IMNM EIS RODs, DOE determined that any of the 
alternatives involving continued interim storage would have smaller 
environmental impacts than alternatives involving processing at the 
large separations facilities at SRS (e.g., F- or H-Canyon) while the 
processing operations were underway. Of the evaluated processing 
alternatives, the environmentally preferable alternative identified in 
the IMNM EIS ROD for targets containing americium and curium was 
Processing and Storage for Nitrification. This remains the 
environmentally preferred alternative.
    The action addressed in this amended ROD does not involve 
processing operations at large separations facilities at SRS. The 
action addressed in this amended ROD will result in increased but small 
levels of short-term environmental impacts from target recovery, onsite 
transfer, and processing to recover desired isotopes, and transport of 
the recovered isotopes to ORNL.

Amended Decision

    To enable recovery of \244\Pu and other valued isotopes, DOE has 
decided to process the 65 Mark-18A targets stored in the L-Basin. The 
65 Mark-18A targets will be removed from the L-Basin and transferred to 
the SRNL SCF within a modified spent nuclear fuel cask. At the SRNL 
SCF, the targets will be processed to recover desired isotopes in two 
solid streams: A plutonium oxide stream and an oxide stream containing 
americium, heavy curium, and fission products. Minor modifications will 
be made within the SRNL SCF to enable efficient receipt and processing 
of the targets. The two oxide streams will be packaged and transported 
to ORNL for further processing and material recovery.
    DOE expects that processing activities at SRNL could begin as early 
as fiscal year 2020 and would continue through fiscal year 2029 
depending on how many targets can be processed per year.

Mitigation Measures

    No mitigation measures were identified in the IMNM EIS ROD, SRS SNF 
EIS ROD, or the subsequent supplemental and amended RODs. No 
environmental impacts resulting from operations under this amended 
decision will require specific mitigation measures. DOE will continue 
its current practices and policies to use all practicable means to 
avoid or minimize environmental harm and impacts to workers and the 
public when implementing the actions described in this amended ROD.

Basis for Decision

    This amended decision ensures the availability of \244\Pu, which is 
a critical component of certified standards for high-precision 
laboratory analyses supporting nuclear forensics and nuclear 
nonproliferation. In addition, this amended decision ensures the 
availability of heavy curium for use as feedstock for production of 
high-demand isotopes such as \252\Cf, which is used in many industrial 
and medical research and health care applications, such as cancer 
treatment. Implementing this action also provides a disposition pathway 
for all remaining Mark-18A targets in storage at SRS.
    The action addressed in this amended ROD will involve a very small 
fraction of the nuclear materials evaluated in the IMNM EIS and SRS SNF 
EIS and will entail use of an existing DOE facility performing 
activities similar to those previously conducted at SRS and within the 
scope of the facility's R&D mission. The action addressed in this 
amended ROD will not result in potential health or environmental 
consequences that will be significantly different from the small 
consequences that were determined in the IMNM EIS and SRS SNF EIS.

    Issued in Washington, DC, on February 27, 2018.
James M. Owendoff,
Principal Deputy Assistant Secretary for Environmental Management.
[FR Doc. 2018-04670 Filed 3-7-18; 8:45 am]
 BILLING CODE 6450-01-P
9848 Federal Register / Vol. 83, No. 46 / Thursday, March 8, 2018 / Notices

• Stable Materials. Materials that americium and curium isotopes’’ (60 FR the potential health effects of processing
were unlikely to present a safety 65306; December 19, 1995), a group of alternatives would be low and well
concern over the next 10 years and were materials that includes the 65 Mark-18A within regulatory limits. No latent
stable and suitable for continued targets. cancer fatalities (LCFs) were expected
storage. These materials included 65 In the SRS SNF EIS, DOE evaluated for members of the public and 1 LCF
Mark-18A targets containing about 1.1 technologies and five broad categories of was projected for workers. The potential
kilograms of nuclear material, as well as alternatives (including processing in H- for accidents involving the processed
about 380,000 discrete items including Area at SRS) for the management of and stabilized materials would be
other types of irradiated targets, spent about 68 metric tons of heavy metal reduced, and some types of accidents
nuclear fuel, R&D material, and reactor (MTHM) of aluminum-clad spent would no longer be possible.
materials such as control rods, plus nuclear fuel, about 20 MTHM of The IMNM EIS also evaluated risks
about 700,000 liters (78,000 gallons) of stainless-steel or zirconium-clad spent from onsite transportation of nuclear
depleted uranium solutions. nuclear fuel, and other nuclear materials between SRS facilities. No
• Programmatic Materials. Materials materials. With respect to the 65 Mark- radiation exposures were projected to
that DOE needed to meet current or 18A targets, the SRS SNF EIS evaluated members of the public from incident-
future program missions, mostly in a the impacts from continued storage at free transport of the materials and no
liquid form. These materials included SRS, repackaging and shipping to LCFs from radiation exposure were
33,100 liters (8,900 gallons) of another DOE site, and processing in H- projected to workers. No LCFs to onsite
plutonium, americium, curium, and Canyon at SRS with discharge to the or offsite populations or an offsite
neptunium solutions, and 248 discrete liquid waste system and verification at maximally exposed individual (MEI)
solid items such as irradiated fuel DWPF. In the SRS SNF EIS ROD, DOE were projected from potential
assemblies, targets, and slugs. The 65 decided to continue to store the 65 transportation accidents considering a
Mark-18A targets were also evaluated in Mark-18A targets at SRS. range of accidents from the very minor
this category. to the very severe.
• Candidate Materials for Supplement Analysis and Summary of
Impacts The IMNM EIS determined that
Stabilization. Materials determined to
In accordance with the National implementing any of the alternatives
be in a physical form or storage
Environmental Policy Act (NEPA) and would result in little or no impacts on
configuration that could present a safety
concern within the next 10 years. These DOE’s implementing NEPA regulations, geologic resources, ecological resources,
materials included a variety of DOE prepared the Supplement Analysis cultural resources, aesthetic and scenic
irradiated targets and nuclear fuels, and of the Mark-18A Target Material resources, noise, or land use. Emissions
other materials including 16,000 Mark- Recovery Program at the Savannah of hazardous air pollutants and releases
31 targets containing 147 metric tons River Site (Mark-18A SA, DOE/EIS– of hazardous effluents would be well
(160 tons) of nuclear material (primarily 0220–SA–02 and DOE/EIS–0279–SA– within regulatory standards and existing
uranium-238 and plutonium- 06, dated December 9, 2016) to evaluate permitting limits for the SRS facilities.
239 [239Pu]) and 3,450 Mark-16 and whether the proposed action requires None of the alternatives would result in
Mark-22 irradiated nuclear fuels. The supplementing the existing IMNM EIS emissions of radioactive or
total included about 22,600 discrete and SRS SNF EIS, or preparing a new nonradioactive constituents resulting in
solid items as well as 34,000 liters EIS. The Mark-18A SA updates the disproportionate impacts on minority or
(9,000 gallons) of 239Pu solutions and evaluations from the IMNM EIS and SRS low-income communities in the vicinity
228,000 liters (60,000 gallons) of SNF EIS to reflect the changes in SRS of SRS. Management of high-level
enriched uranium solutions. The facilities where the 65 Mark-18A targets liquid, transuranic (TRU), low-level
alternatives differed depending on the will be managed, along with associated radioactive waste (LLW), mixed low-
category of nuclear material. For Stable onsite transportation. The Mark-18A SA level radioactive waste (MLLW), and
Materials, DOE evaluated a No Action also evaluates the potential impacts of hazardous waste would be within the
(continued storage) Alternative. For transporting the oxide resulting from capacities of existing SRS waste
Programmatic Materials, including 65 processing the 65 Mark-18A targets to management facilities.
Mark-18A targets, and Candidate ORNL. The action addressed in this amended
Materials for Stabilization, DOE The Mark-18A SA concluded that the ROD will revise previously evaluated
evaluated a range of action alternatives. environmental consequences of the operations for the 65 Mark-18A targets
One of the action alternatives evaluated proposed action would be very small evaluated in the IMNM EIS under the
was a Processing to Oxide Alternative and would not constitute substantial alternatives requiring processing
under which the materials would be changes relative to the analyses and operations at the SRS separations
processed to an oxide using the conclusions in the IMNM EIS and SRS facilities. It will entail processing
separations capabilities in F- and H- SNF EIS, and that there are not operations similar to those evaluated for
Canyons. significant new circumstances or tens of thousands of gallons of liquid
In the IMNM EIS ROD, DOE decided information relevant to environmental nuclear solutions and tens of thousands
to implement the No Action Alternative concerns and bearing on the action or its of discrete solid items including the
for Stable Materials, including the 65 impacts. Therefore, no further NEPA Mark-18A and Mark-31 targets and the
Mark-18A targets. However, DOE analysis is required. Mark-16 and Mark-22 irradiated nuclear
recognized the targets as Programmatic fuels. For example, the 1.1 kilograms of
Materials. DOE indicated that storage A. IMNM EIS and SRS SNF EIS plutonium, americium, curium, and
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would continue until ‘‘DOE makes In the IMNM EIS, DOE determined californium in the 65 Mark-18A targets
decisions relative to their future use or that any of the alternatives where the represents about 7 × 10 ¥4 percent
disposition’’ (60 FR 65301; December materials would be processed at the (about 1/140,000) of the mass of the
19, 1995), and that the Processing to large separations facilities at SRS (i.e., F- nuclear material contained in 16,000
Oxide Alternative as applied to or H-Canyon) would have larger Mark-31 targets evaluated in the IMNM
americium and curium solutions could environmental impacts than alternatives EIS and subsequently processed in F-
be used for ‘‘targets and slugs containing involving continued interim storage, but Canyon.

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Federal Register / Vol. 83, No. 46 / Thursday, March 8, 2018 / Notices 9849

The very small quantity of material addition, it is not expected that the activities will be within its existing
addressed by the proposed action proposed action would introduce basis of operations and the requirements
indicates that the proposed action will additional accident risks. Potential for protection of the public under the
have only negligible impacts and radiation exposures to transport workers National Emission Standards for
represent a negligible change to the are expected to be within DOE Hazardous Air Pollutants.
potential environmental consequences regulations and be maintained at levels Offsite Transportation. Oxides
evaluated in the IMNM EIS. This as low as reasonably achievable. Risks recovered at the SRNL SCF will be
conclusion is supported by the SRS SNF to workers from potential accidents will prepared for transport to ORNL using
EIS which evaluated the impacts from be comparable to or smaller than the packaging that has been certified in
processing the 65 Mark-18A targets at H- risks evaluated in the SRS SNF EIS for accordance with DOT and NRC
Canyon. DOE determined that onsite transfer of spent nuclear fuel. The regulations. All activities will be
processing all 65 Mark-18A targets at H- action will not introduce additional compliant with Federal regulations and
Canyon would result in a total radiation accident risks to those evaluated in the DOE directives. DOE anticipates making
dose to an offsite MEI of 0.0035 SRS SNF EIS. approximately 65 shipments using Type
millirem. Byproducts of the action SRNL SCF Processing. Processing A packaging (e.g., Type S300 special
addressed in this amended ROD will be activities at SRS will occur at the SRNL form configuration) for the americium/
similar in type to the byproducts of SCF in A-Area rather than at F- and/or curium/fission product oxides and
other nuclear material processed at SRS H-Canyons as evaluated in the IMNM approximately 8 shipments using Type
(e.g., Mark-31 targets) and evaluated in EIS and SRS SNF EIS. Whereas F- and B packaging (e.g., Type 9975 or Type
the SRS SNF EIS. In the SRS SNF EIS H-Canyons are designed to process large 9977) for the plutonium oxides. These
ROD, DOE decided to continue to store quantities of materials, there are only Type A and Type B packages are
the 65 Mark-18A targets at the L-Basin. about 21 grams of 244Pu in the 65 Mark- approved for much larger quantities of
The Mark-18A SA updates the 18A targets. The SRNL SCF is a more radioactive materials than those
evaluations from the IMNM EIS and SRS appropriate facility for performing the projected for each shipment.
SNF EIS to reflect the changes in SRS separations and recovery of the DOE evaluated the potential impacts
facilities where the 65 Mark-18A targets comparatively small quantities of to transport crews and members of the
will be managed: (1) Targets are now materials involved. public by scaling the analysis in the SRS
stored at the L-Basin (rather than the Processing the targets will involve SNF EIS for 1,400 shipments of spent
Receiving Basin for Offsite Fuels); (2) activities similar to those previously nuclear fuel from SRS to a geologic
processing will occur at the SRNL SCF and currently conducted at the SRNL repository, considering the smaller
(rather than F- or H-Canyons); and (3) SCF. Operations will be performed number of expected shipments to ORNL
the 65 Mark-18A targets will be within the SRNL safety and (nominally 65 shipments of americium/
transported onsite from the L-Basin to environmental basis, and will comply curium/fission products and nominally
the SRNL SCF. In addition, the Mark- with DOE regulations, directives, and 8 shipments of plutonium oxide), and
18A SA evaluates the potential impacts best management practices to minimize risk factors appropriate for the
of transporting the oxide from radiation exposures to workers and risks populations along the evaluated
processing the 65 Mark-18A targets from from industrial accidents or hazardous transport route to ORNL. No LCFs
SRS to ORNL, an activity not materials. Processing the 65 Mark-18A (0.0015 calculated) are expected among
specifically evaluated in the IMNM EIS targets at the SRNL SCF will be within transport crews or the general
or the SRS SNF EIS. the scope of routine operations under its population (0.004 calculated) during
R&D mission. Although operations will incident-free transport. The risk of an
B. Modifications to Previously Evaluated vent nonradioactive volatile gases LCF to the general population
Activities (nitrogen oxides, nitric acid, hydrogen) considering the range of potential
Considering the operational changes and fission products (krypton, xenon, accidents, from minor to severe, was
that will be required for implementing iodine) through SRNL’s E-wing determined to be about 6 × 10¥7 (one
the Conversion to Oxide Alternative for ventilation system and the 791–A Sand chance of a fatal cancer in about 1.7
the Mark-18A targets (minor filter stack, less than 100 liters of million) from all transport of the oxides,
modifications to the SRNL SCF cells, volatile compounds will be vented per while the risk of a non-radiological
temporary shielding, equipment target (6,500 liters total over a period of accident fatality was determined to be
removal at the end of processing), DOE nine years). 0.007 (1 chance in 140 of a fatality).
re-evaluated the potential Releases of both nonradioactive Other Resource Areas. Under this
environmental consequences that could volatile gases and fission products will decision, only minor modifications will
result, focusing on potential human be well below levels of potential occur within the existing SRNL SCF
health impacts; geologic, ecological, regulatory or procedural impact. building (modifications to the SRNL
cultural, aesthetic, and scenic resources; Releases of fission products will be SCF cells, temporary shielding, and
noise; land use; waste generation and within the facility operating basis of 0.1 equipment removal at the end of
management; and cumulative impacts. millirem per year (a procedural processing) in an industrialized portion
L-Basin Retrieval and Onsite guideline to monitor SRNL activities) of SRS, and operations will entail
Transportation to the SRNL SCF. and no additional sampling or approval activities at existing facilities that are
Removal of the 65 Mark-18A targets from the South Carolina Department of similar to those previously and
from the L-Basin will involve the same Health and Environmental Control will currently conducted at SRS. Thus, there
routine operations as those for other be required. Therefore, minimal impacts will be no change in land use and no
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targets and spent nuclear fuel to members of the public or to impacts on soil and geology, or on
assemblies. Incident-free retrieval of noninvolved workers are expected from visual, ecological, or cultural resources.
targets from the L-Basin and transport to processing the 65 Mark-18A targets. There will be no discernible increase in
the SRNL SCF would not be expected to Including Mark-18A target processing, noise above current levels. There will be
result in radiation doses and risks to operations at the SRNL SCF will be no need for additional personnel,
members of the public in addition to conducted so radioactive and resulting in minimal socioeconomic
those currently experienced. In nonradioactive emissions from all impacts, and no change in impacts on

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9850 Federal Register / Vol. 83, No. 46 / Thursday, March 8, 2018 / Notices

infrastructure (e.g., utilities), surface Nitrification. This remains the this action also provides a disposition
water resources, or groundwater environmentally preferred alternative. pathway for all remaining Mark-18A
resources from operation of the L-Basin The action addressed in this amended targets in storage at SRS.
and the SRNL SCF. ROD does not involve processing The action addressed in this amended
Wastes will be generated primarily operations at large separations facilities ROD will involve a very small fraction
during operations at the SRNL SCF and at SRS. The action addressed in this of the nuclear materials evaluated in the
will include laboratory samples, scrap, amended ROD will result in increased IMNM EIS and SRS SNF EIS and will
and contaminated equipment such as but small levels of short-term entail use of an existing DOE facility
pipettes or gloves. These wastes will environmental impacts from target performing activities similar to those
primarily consist of solid or liquid LLW, recovery, onsite transfer, and processing previously conducted at SRS and within
MLLW, and TRU waste that will be to recover desired isotopes, and the scope of the facility’s R&D mission.
managed within the capacities of transport of the recovered isotopes to The action addressed in this amended
existing SRS waste management ORNL. ROD will not result in potential health
operations. Solid LLW will be disposed Amended Decision or environmental consequences that
of onsite in E-Area, while MLLW will be will be significantly different from the
shipped offsite for treatment and To enable recovery of 244Pu and other small consequences that were
disposal in accordance with the Final valued isotopes, DOE has decided to determined in the IMNM EIS and SRS
Programmatic EIS for Managing process the 65 Mark-18A targets stored SNF EIS.
Treatment, Storage, and Disposal of in the L-Basin. The 65 Mark-18A targets
will be removed from the L-Basin and Issued in Washington, DC, on February 27,
Radioactive and Hazardous Waste 2018.
(DOE/EIS–0200) and amended ROD (65 transferred to the SRNL SCF within a
modified spent nuclear fuel cask. At the James M. Owendoff,
FR 10061; February 25, 2000). Liquid Principal Deputy Assistant Secretary for
waste will be discarded to the SRNL SRNL SCF, the targets will be processed
to recover desired isotopes in two solid Environmental Management.
liquid radioactive waste system, or [FR Doc. 2018–04670 Filed 3–7–18; 8:45 am]
combined with an absorbent for streams: A plutonium oxide stream and
disposal as LLW or management as an oxide stream containing americium, BILLING CODE 6450–01–P

MLLW. TRU waste will be stored on-site heavy curium, and fission products.
in the SRS E-Area Solid Waste Facility Minor modifications will be made
within the SRNL SCF to enable efficient DEPARTMENT OF ENERGY
until shipped to the Waste Isolation
Pilot Plant for disposal. receipt and processing of the targets.
Proposed Agency Information
The two oxide streams will be packaged
Cumulative Impacts. The action Collection
and transported to ORNL for further
addressed in this amended ROD will
processing and material recovery. U.S. Department of Energy.
AGENCY:
require activities at existing SRS DOE expects that processing activities
facilities that are the same as or Notice and request for
ACTION:
at SRNL could begin as early as fiscal comments.
comparable to past and present year 2020 and would continue through
operations at these facilities. Therefore, fiscal year 2029 depending on how
the action addressed in this amended SUMMARY: The Department of Energy
many targets can be processed per year. (DOE) invites public comment on a
ROD is not expected to result in
increases to the ranges of cumulative Mitigation Measures proposed collection of information that
impacts evaluated in the IMNM EIS and DOE is developing for submission to the
No mitigation measures were Office of Management and Budget
SRS SNF EIS. identified in the IMNM EIS ROD, SRS (OMB) pursuant to the Paperwork
C. Supplement Analysis Conclusion SNF EIS ROD, or the subsequent Reduction Act of 1995. Comments are
supplemental and amended RODs. No invited on: (a) Whether the proposed
The action addressed in this amended environmental impacts resulting from
ROD will revise the management collection of information is necessary
operations under this amended decision for the proper performance of the
approach for a very small fraction of the will require specific mitigation
materials evaluated in the IMNM EIS functions of the agency, including
measures. DOE will continue its current whether the information shall have
and SRS SNF EIS. The operational practices and policies to use all
changes at SRS that will be required for practical utility; (b) the accuracy of the
practicable means to avoid or minimize agency’s estimate of the burden of the
implementing the action are expected to environmental harm and impacts to
have only minor environmental proposed collection of information,
workers and the public when including the validity of the
consequences. implementing the actions described in methodology and assumptions used; (c)
Environmentally Preferable Alternative this amended ROD. ways to enhance the quality, utility, and
In the IMNM EIS and IMNM EIS Basis for Decision clarity of the information to be
RODs, DOE determined that any of the This amended decision ensures the collected; and (d) ways to minimize the
alternatives involving continued interim availability of 244Pu, which is a critical burden of the collection of information
storage would have smaller component of certified standards for on respondents, including through the
environmental impacts than alternatives high-precision laboratory analyses use of automated collection techniques
involving processing at the large supporting nuclear forensics and or other forms of information
separations facilities at SRS (e.g., F- or nuclear nonproliferation. In addition, technology.
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H-Canyon) while the processing this amended decision ensures the DATES: Comments regarding this
operations were underway. Of the availability of heavy curium for use as proposed information collection must
evaluated processing alternatives, the feedstock for production of high- be received on or before May 7, 2018.
environmentally preferable alternative demand isotopes such as 252Cf, which is If you anticipate difficulty in submitting
identified in the IMNM EIS ROD for used in many industrial and medical comments within that period, contact
targets containing americium and research and health care applications, the person listed in ADDRESSES as soon
curium was Processing and Storage for such as cancer treatment. Implementing as possible.

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Document Created: 2018-03-08 01:47:38
Document Modified: 2018-03-08 01:47:38
Category		Regulatory Information
Collection		Federal Register
sudoc Class		AE 2.7: GS 4.107: AE 2.106:
Publisher		Office of the Federal Register, National Archives and Records Administration
Section		Notices
Action		Amended record of decision.
Contact		For further information on this Amended ROD, or to receive related NEPA documents, please contact: Ms. Tracy L. Williams, NEPA Compliance Officer, Savannah River Operations Office, U.S. Department of Energy, P.O. Box B, Aiken, South Carolina 29802; (803) 952-8278; or [email protected] For information on DOE's NEPA process, please contact: Mr. Brian Costner, Acting Director, Office of NEPA Policy and Compliance (GC-54), U.S. Department of Energy, 1000 Independence Avenue SW, Washington, DC 20505; (202) 586- 4600; or leave a message at (800) 472-2756. This Amended ROD and related NEPA documents are available on the DOE NEPA website at www.energy.gov/nepa.
FR Citation		83 FR 9847