97-10611. A Study of the Nonproliferation Implications of Chemical Separation of Aluminum-based Research Reactor Spent Nuclear Fuel  

  • [Federal Register Volume 62, Number 79 (Thursday, April 24, 1997)]
    [Notices]
    [Pages 20001-20002]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 97-10611]
    
    
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    DEPARTMENT OF ENERGY
    
    
    A Study of the Nonproliferation Implications of Chemical 
    Separation of Aluminum-based Research Reactor Spent Nuclear Fuel
    
    AGENCY: Department of Energy.
    
    ACTION: Request for comments on nonproliferation study's scope and 
    proposed outline.
    
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    SUMMARY: The Department of Energy (DOE) announces its intent to prepare 
    a study on the nuclear nonproliferation and other (e.g., cost and 
    scheduling) implications of chemically separating (i.e., reprocessing) 
    aluminum-based research reactor spent nuclear fuel at DOE's Savannah 
    River Site, and requests comments from the public on the scope and 
    proposed outline of the study. The objective of the study is to assess 
    the nonproliferation benefits and disadvantages, and cost and timing 
    issues involved with chemically separating aluminum-based research 
    reactor spent nuclear fuel. The study will also identify potential ways 
    to mitigate any disadvantages identified by the study. DOE announced 
    its intent to perform this study in the Record of Decision on a Nuclear 
    Weapons Nonproliferation Policy Concerning Foreign Research Reactor 
    Spent Nuclear Fuel. Although the Record of Decision specified that the 
    study would only address foreign research reactor spent fuel, the 
    Department has subsequently decided also to cover domestic research 
    reactor spent fuel at the Savannah River Site in the study because 
    many, if not all, of the same considerations that apply to management 
    of the foreign spent fuel also apply to the domestic spent fuel. The 
    Department of Energy has already proposed to manage domestic spent 
    research reactor fuel in a manner consistent with foreign spent 
    research reactor fuel.
    
    DATES: Comments on the scope and proposed outline for the study must be 
    postmarked or submitted by fax or electronic mail by May 27, 1997 to 
    ensure that they will be considered in the drafting of this study. 
    Comments received after the close of the comment period will be 
    considered to the extent practicable. DOE plans to hold at least two 
    public meetings (in Washington, D.C. and near the Savannah River Site) 
    to discuss the draft study. The locations, dates, and times for these 
    meetings will be announced later by appropriate means.
    
    ADDRESSES: Questions and comments concerning the Study of the 
    Nonproliferation and Other Implications of Chemical Separation of 
    Aluminum-based Research Reactor Spent Nuclear Fuel, as well as comments 
    on the scope of the study, may be submitted by writing to: Spent Fuel 
    Nonproliferation Study, Office of Arms Control and Nonproliferation, 
    NN-42/JBW, U.S. Department of Energy, 1000 Independence Avenue, SW, 
    Washington, DC 20585.
        Questions and comments can also be submitted via electronic mail 
    at: Assessment@hq.doe.gov. Questions and comments may also be submitted 
    to the following toll-free telephone numbers: phone 800-930-2014 or fax 
    800-930-2019.
    
    SUPPLEMENTARY INFORMATION: The Record of Decision on a Nuclear Weapons 
    Nonproliferation Policy Concerning Foreign Research Reactor Spent 
    Nuclear Fuel, 61 FR 25091, May 17,1996, stated, in part, that:
    
        In order to provide a sound policy basis for making a 
    determination on whether and how to utilize the F-Canyon for 
    chemical separation tasks that are not driven by health and safety 
    considerations, DOE will commission or conduct an independent study 
    of the nonproliferation and other (e.g., cost and timing) 
    implications of chemical separation of spent nuclear fuel from 
    foreign research reactors. The study * * * will be completed in a 
    timely fashion to allow a subsequent decision about possible * * * 
    chemical separation of foreign research reactor spent nuclear fuel 
    to be fully considered by the public, the Congress and Executive 
    Branch agencies.
    
    Background
    
        Following completion of the Final Environmental Impact Statement on 
    a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign 
    Research Reactor Spent Nuclear Fuel (the Final EIS, DOE/EIS-218F of 
    February 1996), DOE and the Department of State decided to implement a 
    new policy for accepting from foreign research reactors spent nuclear 
    fuel containing uranium enriched in the United States (Record of 
    Decision, 61 FR 25091). Implementation of this policy will result in 
    the acceptance by the United States of up to 22,700 individual spent 
    nuclear fuel elements [about 19.2 metric tons of heavy metal (MTHM)]. 
    Of the total, about 17,800 elements (about 18.2 MTHM) are aluminum-
    based spent fuel elements which have been assigned to DOE's Savannah 
    River Site for management. The remaining foreign research reactor spent 
    nuclear fuel elements (about 1 MTHM) will be managed at the Idaho 
    National Engineering and Environmental Laboratory.
        In the Record of Decision, DOE announced that it will implement the 
    new spent fuel acceptance policy through a three-point strategy. First, 
    DOE has initiated an accelerated program to identify, develop, and 
    demonstrate one or more non-reprocessing, cost-effective treatment and/
    or packaging technologies to prepare the foreign research reactor spent 
    nuclear fuel for ultimate disposal. The purpose of these technologies 
    would be to put the foreign research reactor spent nuclear fuel into a 
    form or package that is suitable for geologic disposal and meets all 
    applicable safety and environmental requirements, without necessarily 
    separating the fissile materials. Examples of such treatment or 
    packaging technologies could include: (1) press and dilute or poison, 
    (2) melt and dilute or poison, (3) plasma arc treatment, (4) 
    electrometallurgical treatment, (5) glass materials oxidation and 
    dissolution, (6) dissolve and vitrify, (7) direct disposal in small 
    packages, and (8) direct co-disposal with high-level radioactive 
    waste.\1\
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        \1\ These alternatives are discussed in ``Technical Strategy for 
    the Treatment, Packaging, and Disposal of Aluminum-Based Spent 
    Nuclear Fuel: A Report of the Research Reactor Spent Nuclear Fuel 
    Task Team,'' Volume I, June 1996, United States Department of 
    Energy.
    
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        DOE would select, develop, and implement, if possible, one or more 
    of these treatment or packaging technologies by the year 2000. After 
    treatment and/or packaging, the foreign research reactor spent nuclear 
    fuel would be managed onsite in ``road ready'' dry storage until 
    transported offsite for continued storage elsewhere or for disposal. 
    DOE is committed to avoiding indefinite storage of this spent nuclear 
    fuel in a form that is unsuitable for disposal.
        The second part of this strategy addresses the possibility that, 
    despite DOE's best efforts, a new treatment and/or packaging technology 
    may not be ready for implementation by the year 2000. In this instance, 
    the Department has stated that it will consider chemically separating 
    some of the foreign research reactor spent fuel elements, if Savannah 
    River Site canyon operations are still being conducted to stabilize at-
    risk materials in accordance with the Records of Decision (60 FR 65300 
    of December 19, 1995, 61 FR 6633 of February 21, 1996 and 61 FR 48474 
    of September 6, 1996) issued after completion of the Interim Management 
    of Nuclear Materials Final Environmental Impact Statement (DOE/EIS-0220 
    of October 1995). In order to provide a sound policy basis for 
    determining whether and how to use chemical separation when health and 
    safety considerations are not implicated, DOE committed to commission 
    or conduct an independent study of the nonproliferation and other 
    (e.g., cost and timing) implications of chemically separating spent 
    nuclear fuel \2\ from foreign research reactors (i.e., the study 
    discussed in this request for comments). Although the Record of 
    Decision specified that the study would only address foreign research 
    reactor spent fuel, the Department has subsequently decided also to 
    cover domestic research reactor spent fuel at the Savannah River Site 
    in the study since many, if not all, of the same considerations that 
    apply to management of the foreign spent fuel also apply to the 
    domestic spent fuel.
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        \2\ The term ``spent nuclear fuel,'' in the context of the 
    planned study, includes domestic as well as foreign research reactor 
    fuel, and target material from research reactors.
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        The third part of DOE's strategy for managing foreign research 
    reactor spent nuclear fuel involves closely monitoring the spent fuel 
    placed in wet storage at the Savannah River Site to allow prompt 
    detection of any health or safety problems that might arise. DOE 
    currently is unaware of any technical basis for believing that this 
    spent nuclear fuel cannot be safely stored until one or more of the new 
    packaging and/or treatment technologies becomes available. 
    Nevertheless, if health and safety concerns involving any of the 
    foreign research reactor spent nuclear fuel are identified prior to 
    development of an appropriate new treatment or packaging technology, 
    DOE would use either or both of the reprocessing facilities at the 
    Savannah River Site, if those facilities are operating, to process the 
    affected spent fuel elements.
    
    Scope of the Study
    
        This request for comments presents the scope of the study of the 
    nonproliferation implications, including cost and scheduling aspects, 
    of possible chemical separation of the foreign and domestic research 
    reactor spent nuclear fuel in DOE's inventory at the Savannah River 
    Site, for reasons other than health and safety. The study will examine 
    the following issues:
        (1) nonproliferation impacts of chemical separation of the foreign 
    and domestic research reactor spent nuclear fuel in either or both of 
    the Savannah River Site reprocessing canyons;
        (2) comparable nonproliferation impacts of other alternatives for 
    managing the spent nuclear fuel;
        (3) potential ways to mitigate any nonproliferation disadvantages 
    associated with chemical separation of this spent fuel; and
        (4) the impacts of cost and scheduling considerations on 
    nonproliferation implications.
        In examining these issues, the following outline is proposed:
    
    Study Outline 3
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        \3\ This outline is included to indicate the types of 
    information that the Department plans to include in the study and 
    how it might be presented. The Department may revise the outline, as 
    the study progresses, as appropriate.
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    I. Introduction
    
         A review of the origins of the proposed study in the 
    Record of Decision on a Nuclear Weapons Nonproliferation Policy 
    Concerning Foreign Research Reactor Spent Nuclear Fuel (61 FR 25091).
         Scope, factors for analysis, and plan of the study.
    
    II. Background and Context
    
         U.S. nonproliferation policy dealing with the 
    proliferation risks of fissile materials, including highly enriched 
    uranium (HEU).
         The Reduced Enrichment for Research and Test Reactors 
    (RERTR) Program.
         The use of weapons-usable fissile material in the civilian 
    nuclear fuel cycle.
         Research reactor spent nuclear fuel--acceptance, 
    inventories, status and expectations.
         Status and future of DOE reprocessing facilities.
         New technologies and other alternatives for disposal of 
    spent nuclear fuel without chemical separation.4
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        \4\ These alternatives may include, but are not necessarily 
    limited to, direct disposal, HEU dilution, and advanced treatment 
    technologies as discussed in the report cited in footnote 1.
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    III. Technological Aspects of Chemical Separation Versus Alternative 
    Treatments
    
         Description of treatment technology.
         Quantities of foreign and domestic fuels under study.
         Scheduling the input/output stream.
         Relative cost.
         Physical form of output products.
    
    IV. Nonproliferation Impacts of Chemical Separation Versus Alternative 
    Treatments
    
         Reducing access to weapons-usable materials.
         Reducing inventories of weapons capable materials abroad.
         U.S. nonproliferation and arms control policy and goals.
         Foreign fuel cycle choices and policies.
         Foreign cooperation with the United States on broader 
    nonproliferation issues.
         IAEA safeguards and transparency.
         Broader U.S. policies on storage and disposition of excess 
    weapons-usable fissile materials.
         Cost and/or schedule implications for nonproliferation.
    
    V. Implications for Other Fuels Under DOE Management
    
        Domestic research reactor fuels.
        Other materials.
    
    VI. Possible Mitigation Steps for Nonproliferation Disadvantages
    
    VII. Conclusions
    
        Issued in Washington, D.C. on April 15, 1997.
    Cherie P. Fitzgerald,
    Acting Director, Office of Arms Control and Nonproliferation.
    [FR Doc. 97-10611 Filed 4-23-97; 8:45 am]
    BILLING CODE 6450-01-P