[Federal Register Volume 61, Number 252 (Tuesday, December 31, 1996)]
[Notices]
[Pages 69085-69089]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-33131]


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DEPARTMENT OF ENERGY


Notice of Intent

AGENCY: Department of Energy.

ACTION: Notice of Intent.

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SUMMARY: The Department of Energy (DOE) announces its intent to prepare 
an Environmental Impact Statement (EIS) on the management of a portion 
of the aluminum-clad spent nuclear fuel 1 at the Savannah River 
Site. The Department's objective is to identify and implement 
appropriate actions to safely and efficiently manage all aluminum-clad 
spent nuclear fuel and targets assigned to the Savannah River Site, 
including placing these materials in forms suitable for disposition. To 
this end, this EIS will cover that portion of the aluminum-clad spent 
nuclear fuel inventory currently in storage at the Savannah River Site, 
as well as aluminum-clad foreign, domestic and government research 
reactor aluminum-clad spent nuclear fuel that has been assigned to, but 
has not yet been received at the Savannah River Site. Approximately 188 
metric tons of spent nuclear fuel and targets currently stored at the 
SRS are not considered within the scope of this EIS because the 
Department has already decided on the management strategy for these 
materials. The spent nuclear fuel included in this EIS consists of 
approximately 62 metric tons heavy metal of spent nuclear fuel: 34 
metric tons currently at the Savannah River Site and 28 metric tons, 
foreign and domestic, to be shipped to the Savannah River Site. This 
Notice of Intent briefly describes the proposed DOE action and 
alternatives, announces the schedule for the public scoping meeting, 
and solicits public involvement.

    \1\ Aluminum-clad spent nuclear fuel is nuclear reactor fuel 
that has been withdrawn from a reactor following irradiation, the 
constituent elements of which have not been separated. The ``spent 
nuclear fuel'' consists primarily of the fuel (usually enriched 
uranium), fission products, and the aluminum structural material 
that serves as cladding. For the purposes of the SRS Spent Nuclear 
Fuel Management EIS, spent nuclear fuel also includes uranium/
neptunium target materials, blanket subassemblies, pieces of fuel, 
and debris.
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DATES: DOE invites comments on the proposed scope of the SRS Spent 
Nuclear Fuel Management EIS from the public. Comments must be 
postmarked or submitted by fax or electronic mail by March 3, 1997 to 
ensure consideration in the preparation of the draft EIS. DOE will 
consider late comments to the extent practicable. DOE will conduct an 
informational workshop and public scoping meeting on January 30, 1997, 
from 1:00 p.m. to 4:00 p.m. and 6:00 p.m. to 9:00 p.m., at the North 
Augusta Community Center, 101 Brookside Drive, North Augusta, South 
Carolina. The purpose of the workshop and scoping meeting is to discuss 
spent nuclear fuel management issues at the SRS and provide an 
opportunity for the public to assist the Department in determining the 
appropriate scope of the EIS. The date, time and location of the 
workshop and scoping meeting that appear in this Notice will be 
announced in the SRS Environmental Bulletin and local newspapers well 
in advance of the meeting.

ADDRESSES: Questions and comments concerning the SRS Spent Nuclear Fuel 
Management EIS and comments on the scope of the EIS can be submitted in 
writing to Andrew R. Grainger, NEPA Compliance Officer, Savannah River 
Operations Office, P.O. Box 5031, Aiken, South Carolina 29804-5031. 
Internet addresses are [email protected] or [email protected]. 
Questions and comments may also be submitted by telephone or fax to the 
toll-free telephone number 1-800-242-8269.
    For general information on the DOE NEPA process, contact: Ms. Carol 
M. Borgstrom, Director, Office of NEPA Policy and Assistance, U.S. 
Department of Energy, 1000 Independence Avenue, S.W., Washington, D.C. 
20585; telephone (202) 586-4600 or leave a message at (800) 472-2756.

SUPPLEMENTARY INFORMATION:

Purpose and Need for Action

    DOE needs to safely and efficiently manage all aluminum-clad spent 
nuclear fuel and targets assigned to the SRS until ultimate 
disposition. The management alternatives could involve the use of 
existing, modified, or new facilities or processes, consistent with DOE 
policies regarding the protection of the environment, public and worker 
safety and health, nonproliferation, and recent DOE decisions regarding 
the

[[Page 69086]]

programmatic management of spent nuclear fuel and the decision to 
accept and manage in the United States foreign research reactor spent 
nuclear fuel containing uranium enriched in the United States.

Spent Nuclear Fuel Currently Stored at the SRS

    The current SRS inventory of spent nuclear fuel consists of 
approximately 222 metric tons 2 heavy metal (MTHM, which is the 
uranium mass, excluding cladding, alloy materials and structural 
materials). The inventory includes various forms, as follows: (a) SRS 
spent production reactor fuels consisting of aluminum-clad highly 
enriched uranium; (b) aluminum-clad targets or slugs containing 
plutonium or other isotopes; (c) aluminum-clad spent nuclear fuels from 
offsite domestic and foreign research reactors; and (d) offsite 
research and test reactor spent nuclear fuels clad in zirconium, 
stainless steel, or other materials. The SRS spent production reactor 
fuels, targets and slugs are currently stored under water in the K-, 
and L-Reactor disassembly basins, while the offsite domestic and 
foreign research reactor spent nuclear fuel is stored under water in 
the Receiving Basin for Offsite Fuels. Foreign research reactor spent 
nuclear fuel is also scheduled to be stored in the L-Reactor 
disassembly basin.
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    \2\ A metric ton is 1,000 kilograms, equal to about 2,200 
pounds.
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    The spent nuclear fuel and targets that are the subject of the SRS 
Spent Nuclear Fuel Management EIS will be: that portion of the spent 
nuclear fuel and targets (34 metric tons) currently stored at the SRS 
that has been determined to be stable, but whose management pending 
ultimate disposition has not yet been determined under an environmental 
impact statement prepared under the National Environmental Policy Act; 
and approximately 28 metric tons heavy metal of spent nuclear fuel 
consisting of the foreign research reactor spent nuclear fuel that will 
be shipped to SRS over the next 13 years, and the DOE and domestic 
research reactor spent nuclear fuel that will be shipped to SRS for the 
foreseeable future (i.e., until at least the year 2035).
    The proposed action and alternatives considered in this EIS would 
be consistent with recent Departmental decisions regarding the 
programmatic management of spent nuclear fuel (Record of Decision, 
Spent Nuclear Fuel and Idaho National Engineering Laboratory 
Environmental Restoration and Waste Management Programmatic 
Environmental Impact Statement, 60 FR 28680 (June 1, 1995), and 
Amendment of Record of Decision, 61 FR 9441 (March 8, 1996), and 
Departmental decisions to accept and manage foreign research reactor 
spent nuclear fuel in the United States (Record of Decision, 
Environmental Impact Statement on a Proposed Nuclear Weapons 
Nonproliferation Policy Concerning Foreign Research Reactor Spent 
Nuclear Fuel, 61 FR 25092, May 17, 1996).
    Approximately 188 metric tons of spent nuclear fuel and targets 
currently stored at the SRS are not considered within the scope of this 
EIS because the Department has already decided on the management 
strategy for these materials. These materials were evaluated in the 
Interim Management of Nuclear Materials (IMNM) EIS (DOE/EIS-0220, 
October 1995). In that EIS, DOE considered alternatives for stabilizing 
spent nuclear fuel and other radioactive materials stored at the SRS 
that DOE determined could not be safely stored over the next decade in 
their present condition. Following completion of the IMNM EIS, DOE 
decided (60 FR 65300, December 19, 1995) to stabilize the Mark-31 
targets, 81 failed Taiwan Research Reactor elements, and a failed 
Experimental Breeder Reactor II element (totaling about 159 MTHM) by 
dissolving them in the F-Canyon facility and by reducing the plutonium 
component to metal in the FB-Line facility, after which the resulting 
materials would be stored. Subsequently, DOE announced its decision (61 
FR 6633, February 21, 1996) to stabilize Mark-16 and Mark-22 production 
reactor spent fuels by processing them and blending down the highly 
enriched uranium component to low enriched uranium in SRS facilities. 
Other aluminum-clad targets stored in the reactor basins would be 
stabilized by dissolving them in the canyon facilities and storing the 
solutions in the SRS high-level waste tanks for eventual conversion to 
a glass form in the Defense Waste Processing Facility. The glass logs 
would then be stored at the SRS until ultimate disposition. While these 
materials are considered spent fuel, their management is not considered 
within the scope of the SRS Spent Nuclear Fuel Management EIS because, 
once stabilized, they will be suitable for disposition under existing 
DOE programs. Accordingly, no other management alternatives need be 
considered.
    The management and disposition of the 62 MTHM \3\ are the subject 
of this EIS. Table 1 provides information on the spent nuclear fuel 
inventory currently located at the SRS that the Department plans to 
evaluate in this EIS.
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    \3\ The 34 MTHM currently stored at SRS do not include about 22 
MTHM spent fuel clad in stainless steel or zirconium and stored in 
the Receiving Basin for Offsite Fuels. This material will be shipped 
to the Idaho National Engineering Laboratory for management there 
(60 FR 28680, June 1, 1995).

[[Page 69087]]



    Table 1.-- Existing SRS Inventory of Aluminum-Clad SNF (as of September 30, 1996) to be Evaluated in EIS    
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                                                  Number of                                  Metric tons heavy  
           Fuel type                Location        items                Units                     metal        
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Fuels:                                                                                                          
    Mark-14...................  RBOF \1\                   1  Can \2\...................  <0.001                
    Taiwan Research Reactor...  RBOF                      62  Cans......................  8.7                   
    Experimental Breeder        RBOF                      59  Cans......................  16.7                  
     Reactor.                                                                                                   
    Sodium Experimental         RBOF                      36  Cans......................  2.1                   
     Reactor.                                                                                                   
    Argonne National            RBOF                      19  Assemblies \3\............  0.003                 
     Laboratory Janus Reactor.                                                                                  
    Advanced Thermal Source     RBOF                      21  Assemblies................  0.003                 
     Reactor.                                                                                                   
    Massachusetts Institute of  RBOF                      56  Assemblies................  0.016                 
     Technology Reactor.                                                                                        
    University of Missouri      RBOF                     112  Assemblies................  0.049                 
     Research Reactor.                                                                                          
    Rhode Island Nuclear        RBOF                      70  Assemblies................  0.004                 
     Center Reactor.                                                                                            
    University of Michigan      RBOF                      48  Assemblies................  0.034                 
     Reactor.                                                                                                   
    University of Virginia      RBOF                      44  Assemblies................  6.062                 
     Reactor.                                                                                                   
    Nereide (French) Research   RBOF                      46  Assemblies................  0.035                 
     Reactor.                                                                                                   
    Japanese Material Test      RBOF                      71  Assemblies................  0.017                 
     Reactor.                                                                                                   
    French Hot Flux Research    RBOF                       4  Assemblies................  0.026                 
     Reactor.                                                                                                   
    Oak Ridge Research Reactor  RBOF                     165  Assemblies................  0.111                 
    Sterling Forest...........  RBOF                     678  Cans......................  0.094                 
                                                         200  Assemblies................  0.028                 
    Urgent Relief Receipts....  RBOF                     252  Assemblies................  0.05                  
Targets:                                                                                                        
    Mark-42 targets...........  RBOF                       7  Assemblies................  <0.1                  
    Mark-18 americium-241       RBOF                      65  targets \4\...............  <0.1                  
     targets.                                                                                                   
    Special curium and other    RBOF                     114  slugs \5\.................  <0.1                  
     targets.                                                                                                   
                                                                                         -----------------------
      Total...................  ...............  ...........  ..........................  About 34 MTHM         
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\1\ The Receiving Basin for Offsite Fuels facility at the SRS.                                                  
\2\ The term ``can'' indicates that the spent nuclear fuel was placed in an aluminum can, which was then sealed 
  to provide a suitable storage container for the fuel element(s).                                              
\3\ The term ``assembly'' refers to the nuclear fuel in its assembled form (i.e., fuel, cladding and handling   
  features are all present). In this case, the term ``assembly'' is synonymous with ``fuel element.''           
\4\ The term ``target'' refers to uranium or transuranic material, clad in aluminum, that was irradiated in a   
  reactor for the purpose of producing special isotopes, e.g., plutonium-238.                                   
\5\ The term ``slug'' normally refers to a disassembled target.                                                 

    Foreign Research Reactor Fuel Assigned to the SRS. Following 
completion of the EIS on a Proposed Nuclear Weapons Nonproliferation 
Policy Concerning Foreign Research Reactor Spent Nuclear Fuel, DOE and 
the Department of State decided to implement a new foreign research 
reactor spent nuclear fuel policy by accepting from foreign reactors 
spent nuclear fuel containing uranium enriched in the United States 
(Record of Decision, 61 FR 25092. May 17, 1996). Implementation of this 
policy will result in the acceptance of up to 22,700 foreign research 
reactor spent fuel elements (about 19.2 MTHM) by the United States. Of 
this number, about 17,800 are aluminum-clad fuel elements (about 18.2 
MTHM) which have been assigned to the Savannah River Site for 
management. The remaining foreign research reactor spent fuel elements 
(about 1 MTHM) have been assigned to the Idaho National Engineering 
Laboratory for management.
    In the Record of Decision (61 FR 25092, May 17, 1996) for the EIS 
on a Proposed Nuclear Weapons Nonproliferation Policy Concerning 
Foreign Research Reactor Spent Nuclear Fuel, DOE decided to implement a 
three-point strategy for managing these fuel elements. First, DOE has 
started an accelerated program to identify, develop, and demonstrate 
one or more non-processing, cost-effective treatment or packaging 
technologies to prepare the foreign research reactor spent nuclear fuel 
for disposition. The purpose of any new facilities that might be 
constructed to implement these technologies would be to change the 
foreign research reactor spent nuclear fuel into a form that is 
suitable for geologic disposal without necessarily separating the 
fissile materials. Examples of such treatment technologies could 
include: press and dilute/poison, melt and dilute/poison, plasma arc 
treatment, electrometallurgical treatment, glass materials oxidation 
and dissolution, dissolve and vitrify, direct disposal in small 
packages, and direct co-disposal with high-level waste.
    In conjunction with the examination of new technologies, variations 
of conventional direct disposal methods would also be explored. After 
treatment or packaging, the foreign research reactor spent nuclear fuel 
would be managed on site in dry storage. (After such treatment or 
packaging, the spent nuclear fuel would then be in a condition often 
referred to as ``road ready,'' meaning that no further packaging or 
treatment would be required before being transported off-site for 
continued storage or disposal.) DOE would select, develop, and 
implement, if appropriate, one or more of these treatment or packaging 
technologies by the year 2000. DOE is committed to avoiding indefinite 
storage of this spent nuclear fuel in a form that is unsuitable for 
disposal.
    Should a new treatment or packaging technology not be ready for 
implementation by the year 2000, the second part of the strategy would 
involve use of F-Canyon to chemically separate some foreign research 
reactor spent nuclear fuel elements while the F-Canyon facility is 
operating in order to stabilize ``at-risk'' materials (i.e., materials 
that pose a health or safety concern) in accordance with the 
Implementation Plan for Defense Nuclear Facilities Safety Board 
Recommendation 94-1. DOE would use the F-Canyon to process only that 
quantity of foreign research reactor fuel that could be accommodated by 
the available canyon capacity. Current schedules show that this 
activity could take place after the year 2000. As part

[[Page 69088]]

of the assessment and analysis of this contingency, DOE committed to 
commission or conduct an independent study of the nonproliferation and 
other implications of processing spent nuclear fuel from foreign 
research reactors. The results of this study will be applicable to all 
the spent nuclear fuel within the scope of the SRS Spent Nuclear Fuel 
Management EIS and will be incorporated into a final decision on spent 
nuclear fuel management at SRS.
    The third part of the strategy for managing foreign research 
reactor spent nuclear fuel is embodied in a program of closely 
monitoring such fuel placed in wet storage at the SRS. DOE is presently 
unaware of any technical basis for believing that the foreign research 
reactor spent nuclear fuel cannot be safely stored until one or more of 
the new packaging or treatment technologies becomes available. 
Nevertheless, if health and safety concerns involving any of the 
foreign research reactor spent fuel materials are identified prior to 
development of an appropriate treatment or packaging technology, DOE 
would use the F-Canyon to process the affected spent nuclear fuel 
materials, while F-Canyon is operating to stabilize the at-risk 
materials.
    DOE and Domestic Research Reactor Fuel to be Shipped to SRS. 
Following completion of the Programmatic Spent Nuclear Fuel and Idaho 
National Engineering Laboratory Environmental Restoration and Waste 
Management EIS, DOE decided that the SRS will be the management site of 
aluminum-clad fuel that is currently in or may become a part of DOE's 
inventory (DOE reactor fuel, excluding spent fuel at the Hanford site, 
university and other domestic research test reactor fuel, and fuel from 
foreign research reactors) (Record of Decision, 60 FR 28680, June 1, 
1996) and Amendment to the Record of Decision, 61 FR 9441, March 8, 
1996). This decision will result in the shipment of about 4,500 
aluminum-clad spent fuel elements to the SRS from the Idaho National 
Engineering Laboratory and up to 9,600 aluminum-clad spent fuel 
elements from domestic DOE and research reactors (for a total of about 
10 MTHM). Table 2 provides information on the expected future receipts 
of spent nuclear fuel at the SRS that the Department plans to evaluate 
in this EIS.

               Table 2.--Expected Future Receipts of Spent Nuclear Fuel at the Savannah River Site              
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                  Source                               Number of elements                        MTHM           
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Domestic Research Reactors...............  9,600....................................  6.2                       
Foreign Research Reactors................  17,800...................................  18.2                      
Idaho National Engineering Laboratory....  4,500....................................  3.8                       
                                          ----------------------------------------------------------------------
      Total..............................  About 31,900 elements....................  About 28.2 MTHM           
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Alternatives:

    DOE will evaluate several alternatives for the management of both 
the aluminum-clad spent nuclear fuel currently stored at the Savannah 
River Site and the foreign and domestic research reactor spent nuclear 
fuel that is expected to be shipped to the Savannah River Site in the 
future. Each of the following alternatives will be considered for the 
spent nuclear fuel currently in storage and that is expected to be 
shipped to the SRS.

Continued Wet Storage (No Action)

    The no action alternative would continue storage of spent fuel in 
the Receiving Basin for Offsite Fuel and the L-Reactor disassembly 
basin. Future receipts of domestic and foreign fuel would be stored at 
these locations. This alternative also involves continuation of the 
enhanced monitoring program and water chemistry management activities 
at the basins to ensure the safe storage of spent fuel. Under this 
alternative, DOE would also use the F-Canyon (or H-Canyon) facility to 
process those fuel elements that are determined to present health and 
safety vulnerabilities during wet storage, in accordance with the 
Records of Decision for the Proposed Nuclear Weapons Nonproliferation 
Policy Concerning Foreign Research Reactor Spent Nuclear Fuel EIS (61 
FR 25092, May 17, 1996) and the Interim Management of Nuclear Material 
EIS (60 FR 65300 and 61 FR 6633, December 19, 1995 and February 21, 
1996 respectively). Because each alternative evaluated in this EIS 
involves some period of wet storage prior to implementation, the 
potential for processing fuels which are determined to present health 
and safety vulnerabilities is applicable to all the alternatives. DOE 
notes that processing for health and safety reasons is already 
authorized under existing analyses.

New Processing/Packaging Technologies

    This alternative would include evaluating one or more cost-
effective treatment or packaging technologies as described in the 
Record of Decision (61 FR 25092, May 17, 1996) for the Proposed Nuclear 
Weapons Nonproliferation Policy Concerning Foreign Research Reactor 
Spent Nuclear Fuel EIS. Most of these technologies would employ 
packaging or processing activities that would not separate fissile 
material from fission products. In the SRS Spent Nuclear Fuel 
Management EIS, DOE will evaluate the potential impacts of the 
application of these technologies to the spent nuclear fuel that is the 
subject of this EIS for the purpose of placing these materials in forms 
suitable for geologic disposal.

Dry Storage

    This alternative assesses the potential impacts associated with the 
construction and operation of a facility (Transfer and Storage 
Facility) to receive, characterize, condition, package, and dry store 
SNF prior to shipment to a geologic repository for disposal. DOE would 
evaluate dry storage for managing existing stable spent nuclear fuel 
inventories as well as future receipts.

Conventional Processing

    This alternative would involve processing spent nuclear fuel in the 
existing chemical separation facilities. For foreign research reactor 
spent fuel, this alternative would be applicable only to address health 
and safety concerns, as described above. For stable non-foreign 
research reactor SNF, DOE would evaluate the potential environmental 
impacts associated with processing, even where not required for health 
or safety concerns. This alternative could result in the separation of 
some fissile materials (generally, highly enriched uranium) from the 
spent nuclear fuel, which would be blended down to low-enriched uranium 
prior to removing the material from the processing facility complex. 
Low-enriched uranium is not weapons-grade nuclear material. Some amount 
of plutonium-239 would also be separated.

[[Page 69089]]

However, there would be no plutonium-239 separated from the vast 
majority of the fuel, even in instances where plutonium-239 may be 
present. Plutonium-239 separation would only occur in cases where it 
was required in order to ensure criticality safety in high-level waste 
tanks and the subsequent high-level waste vitrification process. In any 
case, no effort would be made to maintain the purity of the plutonium-
239. DOE would process the plutonium to metal for storage in accordance 
with the DOE standard for storage of plutonium prior to the application 
of International Atomic Energy Agency (IAEA) safeguards. Any separated 
plutonium-239 would be placed under IAEA control when such controls are 
instituted.

Identification of Environmental and Other Issues

    DOE has identified the following issues for analysis in the EIS. 
Additional issues may be identified during the scoping process, and DOE 
specifically solicits comments on the appropriateness of these issues 
for consideration in the EIS.
    1. Public and worker safety: radiological and nonradiological 
impacts of the alternatives, including potential effects on workers and 
the public from the normal operation and accident conditions.
    2. Impacts to plants, animals, and habitat, including impacts to 
wetlands, and threatened and endangered species and their habitat.
    3. The consumption of natural resources and energy including water, 
natural gas, and electricity.
    4. Socioeconomic impacts to affected communities from the 
operations labor force and any required construction labor force, and 
support services, in the SRS region of influence.
    5. Potential disproportionately high or adverse human health or 
environmental impacts on minority and low-income populations.
    6. Transportation of spent nuclear fuel to the Savannah River Site. 
DOE believes that these impacts are adequately addressed in other 
environmental impact statements and intends to incorporate the analysis 
by reference into this EIS.
    7. Impacts on cultural resources, historic, archaeological, 
scientific, or culturally important sites.
    8. Status of compliance with all applicable Federal, state, and 
local statutes and regulation; required Federal and state environmental 
consultations and notifications; and DOE orders on waste management, 
waste minimization initiatives, and environmental protection.
    9. Potential impact on U.S. nonproliferation policy, especially as 
the actions considered may produce weapons usable fissile materials 
that may need to be safeguarded.
    10. Cumulative impacts from the proposed action and other past, 
present, and reasonably foreseeable actions at the Savannah River Site.
    11. Potential irreversible and irretrievable commitments of 
resources.

Related Documents

    The following documents, which are available for review at DOE 
Reading Rooms, contain information related to the issues to be 
addressed in the SRS Spent Nuclear Fuel EIS.

U.S. Department of Energy. 1995. Department of Energy Programmatic 
Spent Nuclear Fuel Management and Idaho National Engineering Laboratory 
Environmental Restoration and Waste Management Programs Final 
Environmental Impact Statement, DOE/EIS-0203F. Idaho Operations Office, 
Idaho Falls, ID, April 1996.
U.S. Department of Energy. 1996. Final Environmental Impact Statement 
on a Proposed Nuclear Weapons Nonproliferation Policy Concerning 
Foreign Research Reactor Spent Nuclear Fuel, DOE/EIS-0218F. Assistant 
Secretary for Environmental Management, Washington, D.C. February 1996.
U.S. Department of Energy. 1995. Final Environmental Impact Statement, 
Interim Management of Nuclear Materials, DOE/EIS-0220. Savannah River 
Operations Office, Aiken, South Carolina. October 1995.
U.S. Department of Energy. 1995. Facility Utilization Strategy for the 
Savannah River Site Chemical Separations Facilities. Savannah River 
Operations Office, Aiken, South Carolina. December 1995.
U.S. Department of Energy. 1994. Environmental Assessment of Urgent-
Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel, DOE/
EA-0912. Washington, D.C. April 1994.

    Issued in Washington, D.C., this 23rd day of December 1996.
Peter N. Brush,
Principal Deputy Assistant Secretary, Environment, Safety and Health.
[FR Doc. 96-33131 Filed 12-30-96; 8:45 am]
BILLING CODE 6450-01-P