94-10010. Sierra Nuclear Corporation; Environmental Assessment and Finding of No Significant Impact  

  • [Federal Register Volume 59, Number 80 (Tuesday, April 26, 1994)]
    [Unknown Section]
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    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 94-10010]
    
    
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    [Federal Register: April 26, 1994]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket No. 72-1007]
    
     
    
    Sierra Nuclear Corporation; Environmental Assessment and Finding 
    of No Significant Impact
    
        The U.S. Nuclear Regulatory Commission (NRC or the Commission) is 
    considering issuance of an exemption to Sierra Nuclear Corporation 
    (SNC) (formerly Pacific Sierra Nuclear Associates), located in Roswell, 
    Georgia, to fabricate (but not use) a modified version of its NRC-
    approved Ventilated Storage Casks (VSC-24). These modified casks are 
    intended to be used by Entergy Operations, Inc. (Entergy) to store 
    spent fuel at its Arkansas Nuclear One (ANO) plant (Docket Nos. 50-313/
    368, License Nos. DPR-51/ NPF6) located near Russellville, Arkansas.
    
    Environmental Assessment
    
    Identification of Proposed Action
    
        The request, proposed by SNC letter dated January 24, 1994, would 
    exempt SNC from the requirements of 10 CFR 72.234(c), which states that 
    ``Fabrication of casks under the Certificate of Compliance must not 
    start prior to receipt of the Certificate of Compliance for the cask 
    model.'' Specifically, SNC proposed to fabricate the first fourteen 
    (14) casks prior to the Commission's issuance of a revised Certificate 
    of Compliance. The Commission is considering granting the exemption for 
    four (4) casks and deferring action with respect to the remaining ten 
    (10) casks. Granting the exemption at this time for fabrication of four 
    (4) casks would readily enable ANO to proceed with activities to 
    support its scheduled plant outages. The proposed exemption for 
    fabrication would not authorize use of the casks to store spent fuel.
    
    The Need for the Proposed Action
    
        SNC's request for exemption is to ensure the availability of 
    storage casks for planned loading in October 1994, in order to support 
    ANO's upcoming refueling outages. SNC has indicated that in order to 
    meet this schedule, purchase of the cask components and materials must 
    begin promptly and fabrication must commence thereafter. The 
    application for a revised Certificate of Compliance for the VSC-24, 
    dated June 14, 1993, is being considered by the Commission.
        Procurement, fabrication, and construction activities by SNC under 
    the exemption would be entirely at SNC's own risk. Favorable NRC action 
    on the exemption request shall not be construed as an NRC commitment to 
    favorably consider SNC's application for a revised certificate, or to 
    approve SNC's modified proposed design for the VSC-24. SNC would bear 
    the risk of any activities conducted under the exemption, including the 
    risk of modification of the casks, if necessary, in light of NRC's 
    forthcoming action on SNC's application and proposed design.
    
    Environmental Impacts of the Proposed Action
    
        The Commission has evaluated the environmental impacts of the 
    proposed action, which is limited to fabrication only and would not 
    authorize any action with respect to use of the casks to store spent 
    fuel. The NRC reviewed the VSC-24 design Final Safety Analysis Report 
    (SAR), and on April 28, 1993, issued a Safety Evaluation Report (SER) 
    approving the SAR, and on May 3, 1993, issued a Certificate of 
    Compliance for use of the VSC-24 under a general license. As a result 
    of this SAR review and approval, SNC has an NRC-approved quality 
    assurance program under which the VSCs can be fabricated. SNC has 
    developed procurement and fabrication specifications under this 
    approved QA program, which will be used to control procurement and 
    fabrication activities related to construction of these casks. 
    Environmental impact from the limited fabrication activities would be 
    similar to small concrete construction activities at an existing 
    facility and similar to the assembly of metal components at a large 
    machine shop. The environmental assessments for the Proposed Rule (54 
    FR 19397) and Final Rule (55 FR 29181), ``Storage of Spent Fuel in NRC-
    approved Storage Casks at Power Reactor Sites,'' and Final Rule (58 FR 
    19849), ``List of Approved Spent Fuel Storage Casks: Additions'' 
    considered the environmental impact associated with the construction 
    and use of such certified casks and concluded that these activities 
    would have no significant impact on the environment. Accordingly, the 
    Commission concludes that the exemption to fabricate (but not use) the 
    limited number of casks, will have no significant radiological or 
    nonradiological environmental impacts.
    
    Alternative to the Proposed Action
    
        The alternative would be to deny the requested exemption. This 
    would result potentially in the loss of lead time for procurement and 
    fabrication necessary for the availability of casks intended for 
    Entergy, and could thereby cause disruptions in planned activities for 
    a series of plant outages beginning in 1995.
    
    Agencies and Persons Consulted
    
        The Commission's staff reviewed SNC's request and did not consult 
    other agencies or persons.
    
    Finding of No Significant Impact
    
        Based upon the foregoing environmental assessment, the Commission 
    concludes that the proposed action would not have a significant effect 
    on the quality of the human environment. Accordingly, the Commission 
    has determined not to prepare an environmental impact statement for the 
    proposed exemption.
        For further details with respect to this action, the request for 
    exemption dated January 24, 1994, and other documents are available for 
    public inspection at the Commission's Public Document Room, the Gelman 
    Building, 2120 L Street, NW., Washington, DC 20555, and the Local 
    Public Document Room at the Tomlinson Library (Depository), Arkansas 
    Tech University, Russellville, Arkansas 72801.
    
        Dated at Rockville, Maryland, this 20th day of April, 1994.
    
        For the Nuclear Regulatory Commission.
    E. William Brach,
    Deputy Director, Division of Industrial and Medical Nuclear Safety, 
    Office of Nuclear Material Safety and Safeguards.
    [FR Doc. 94-10010 Filed 4-25-94; 8:45 am]
    BILLING CODE 7590-01-M
    
    
    

Document Information

Published:
04/26/1994
Department:
Nuclear Regulatory Commission
Entry Type:
Uncategorized Document
Document Number:
94-10010
Pages:
0-0 (1 pages)
Docket Numbers:
Federal Register: April 26, 1994, Docket No. 72-1007