99-7761. Portland General Electric Company; Issuance of Environmental Assessment and Finding of No Significant Impact Regarding the Proposed Exemption From Certain Requirements of 10 CFR Part 72  

  • [Federal Register Volume 64, Number 60 (Tuesday, March 30, 1999)]
    [Notices]
    [Pages 15184-15185]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 99-7761]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [DOCKET 72-17]
    
    
    Portland General Electric Company; Issuance of Environmental 
    Assessment and Finding of No Significant Impact Regarding the Proposed 
    Exemption From Certain Requirements of 10 CFR Part 72
    
        The U.S. Nuclear Regulatory Commission (NRC or the Commission) is 
    considering issuance of an exemption, pursuant to 10 CFR 72.7, from the 
    requirements of 10 CFR 72.124(b) to Portland General Electric Company 
    (PGE). Exemption from10 CFR 72.124(b) would provide relief to PGE from 
    the requirement to use positive means to verify the continued efficacy 
    of neutron absorbing materials for spent fuel storage casks stored at 
    an independent spent fuel storage installation (ISFSI) at the Trojan 
    Nuclear Plant (Docket Nos. 72-17 and 50-344) in Columbia County, 
    Oregon. The proposed ISFSI would store spent nuclear fuel from the 
    Trojan Nuclear Plant.
    
    Environmental Assessment (EA)
    
    Identification of Proposed
    
        By letter dated March 20, 1997, PGE requested an exemption from the 
    requirement in 10 CFR 72.124(b) which states: ``When practicable the 
    design of an ISFSI or MRS must be based on favorable geometry, 
    permanently fixed neutron absorbing materials (poisons), or both. Where 
    solid neutron absorbing materials are used [as a means for criticality 
    control], the design shall provide for positive means to verify their 
    continued efficacy.'' Specifically, PGE is requesting exemption from 
    the requirement to provide a positive means to verify the continued 
    efficacy of neutron absorbing materials.
        The proposed action before the Commission is whether to grant this 
    exemption under 10 CFR 72.7 to release PGE from the requirement to use 
    positive means to verify the continued efficacy of neutron absorbing 
    materials for spent fuel storage casks stored at an ISFSI in accordance 
    with 10 CFR 72.124(a).
    
    Need for the Proposed Action
    
        The applicant is preparing to build and operate the Trojan ISFSI as 
    described in its application and SAR, subject to approval of the 
    pending licensing application. The exemption to 10 CFR 72.124(b) is 
    necessary because, while this requirement is appropriate for wet spent 
    fuel storage systems, it is not appropriate for dry spent fuel storage 
    systems such as the one PGE plans to use for storage of spent fuel at 
    the Trojan ISFSI. Periodic verification of neutron poison effectiveness 
    is neither necessary nor practical for these casks.
    
    Environmental Impacts of the Proposed Action
    
        Section 72.124(b) currently requires that where the design of an 
    ISFSI uses solid neutron absorbing material as a method of criticality 
    control, the design of the ISFSI shall provide a positive means to 
    verify the continued efficacy of the absorbing material. On June 9, 
    1998, the Commission issued a proposed rule (63 FR 31364) to revise 10 
    CFR 72.124(b). The Commission proposed that for dry spent fuel storage 
    systems, the continued efficacy of neutron absorbing material may be 
    confirmed by a demonstration and analysis before use, showing that 
    significant degradation of the material cannot occur over the life of 
    the facility. The Commission stated in the proposed rule that the 
    potentially corrosive environment under wet storage conditions is not 
    present in dry storage systems because an inert environment is 
    maintained. Under these conditions, there is no mechanism to 
    significantly degrade the neutron absorbing material. Consequently, a 
    positive means for verifying the continued efficacy of the
    
    [[Page 15185]]
    
    material is not required. A final rule to revise this regulation has 
    not yet been issued by the Commission.
        The review of the applicant's SAR showed that credit was taken for 
    only 75% of the original neutron absorbing material being present and 
    that the neutron flux produced by the spent nuclear fuel would deplete 
    only a small percentage of neutron absorbing material during the 
    expected life of this facility. The neutron absorbing material (poison) 
    is in a form that exposure to the ambient atmosphere of the basket 
    interior will not cause a significant deterioration of the structural 
    properties of the material over the expected life of the facility.
    
    Alternative to the Proposed Action
    
        Since there is no significant environmental impact associated with 
    the proposed action, any alternatives with equal or greater 
    environmental impact are not evaluated. The alternative to the proposed 
    action would be to deny approval of the 10 CFR 72.124(b) exemption and, 
    therefore, not allow elimination of the requirement to verify the 
    continued efficacy of neutron absorbing materials. This alternative 
    would have the same or greater environmental impacts.
    
    Agencies and Persons Consulted
    
        On March 1, 1999, Adam Bless from the Oregon Office of Energy was 
    contacted about this EA for the proposed action and had no concerns.
    
    Finding of No Significant Impact
    
        The environmental impacts of the proposed action have been reviewed 
    in accordance with the requirements set forth in 10 CFR Part 51. Based 
    upon the foregoing EA, the Commission finds that the proposed action of 
    granting an exemption from 10 CFR 72.124(b) will not significantly 
    impact the quality of the human environment. Accordingly, the 
    Commission has determined not to prepare an environmental impact 
    statement for the proposed exemption.
        This application was docketed under 10 CFR Part 72, Docket 72-17. 
    For further details with respect to this action, see the application 
    for an ISFSI license dated March 26, 1996, and the request for 
    exemption dated March 20, 1997, which are available for public 
    inspection at the Commission's Public Document Room, 2120 L Street, NW, 
    Washington, DC 20555, and the Local Public Document Room at the 
    Portland State University, Branford Price Millar Library, 934 SW 
    Harrison, Portland, Oregon 97207.
    
        Dated at Rockville, Maryland, this 24th day of March 1999.
        For the Nuclear Regulatory Commission.
    E. William Brach,
    Director, Spent Fuel Project Office, Office of Nuclear Material Safety 
    and Safeguards.
    [FR Doc. 99-7761 Filed 3-29-99; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
03/30/1999
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
99-7761
Pages:
15184-15185 (2 pages)
Docket Numbers:
DOCKET 72-17
PDF File:
99-7761.pdf