94-20756. Arkansas Nuclear One; Sierra Nuclear Corporation; Receipt of Petition for Director's Decision Under 10 CFR 2.206  

  • [Federal Register Volume 59, Number 163 (Wednesday, August 24, 1994)]
    [Unknown Section]
    [Page 0]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 94-20756]
    
    
    [[Page Unknown]]
    
    [Federal Register: August 24, 1994]
    
    
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    NUCLEAR REGULATORY COMMISSION
    [Docket Nos. 50-313/368, 72-1007; License Nos. DPR-51/NPF-6]
    
     
    
    Arkansas Nuclear One; Sierra Nuclear Corporation; Receipt of 
    Petition for Director's Decision Under 10 CFR 2.206
    
        Notice is hereby given that by Petition dated July 5, 1994, Dennis 
    Dums, on behalf of the Wisconsin Citizen's Utility Board (CUB or 
    Petitioner) requested that the Nuclear Regulatory Commission (NRC) take 
    action with regard to Arkansas Nuclear One Units 1 and 2 (ANO). The 
    Wisconsin CUB has previously corresponded with NRC concerning issues 
    related to the NRC-certified VSC-24 dry storage cask due to Wisconsin 
    Electric Power Company's planned use of the cask at its Point Beach 
    nuclear power plant. Petitioner requests that: (1) The NRC determine 
    the applicability of 10 CFR 72.48 to 10 CFR Subparts K and L and inform 
    the public of this determination; (2) the NRC direct its legal counsel 
    to determine whether Entergy Operations, Inc. (Entergy) is in violation 
    of any NRC regulations regarding Entergy's use of 10 CFR 72.48 with 
    respect to making modifications to the VSC-24 Cask Safety Analysis 
    Report (SAR) for use at Arkansas Nuclear One (ANO) and inform the 
    public of this determination; (3) the NRC determine whether Entergy's 
    directions to Sierra Nuclear Corporation (SNC) to construct more casks 
    than were approved was a violation of NRC regulations and order Entergy 
    to cease its use of 10 CFR 72.48 until the NRC completes an 
    investigation of the applicability of 10 CFR 72.48 to 10 CFR Part 72, 
    Subparts K and L; and (4) the NRC determine whether SNC's construction 
    of the casks for use at ANO was a violation of NRC regulations and 
    order SNC to cease all construction of VSC-24 casks for use at ANO that 
    are being constructed based on Entergy's 10 CFR 72.48 evaluation.
        Petitioner asserts as bases for these requests that: ANO is 
    currently pursuing spent fuel storage at ANO through use of 10 CFR 
    Subparts K and L; ANO currently intends to utilize the VSC-24 
    constructed by vendor SNC under an SAR submitted in October, 1991 and 
    safety evaluation report (SER), issued by the NRC in April, 1993; an 
    NRC response, dated January 31, 1994, to an October 13, 1993, public 
    request for information, stated that Subparts K and L of 10 CFR Part 72 
    are silent on cask SAR and certificate changes after the final rule; 
    and ANO request for a rule exemption to 10 CFR 72.234(c) was granted by 
    the NRC to allow for the fabrication of four VSC-24 casks to the longer 
    length prior to NRC approval of SNC's June 14, 1993, submittal of 
    Revision 1 to the 1991 VSC-24 Cask SAR; a February 14, 1994, memorandum 
    to NRC Assistant General Counsel Treby requested a legal interpretation 
    of the applicability of 10 CFR 72.48 to general licenses issued under 
    10 CFR 72.210; a May 19, 1994, meeting was held regarding SNC's 
    revisions to VSC-24 SAR and the applicability of 10 CFR 72.48 to 
    general license users, as well as a June 3, 1994, memorandum regarding 
    this meeting which stated that ``the license can make its own 
    interpretation of the regulations;'' and a letter, dated June 2, 1994, 
    from Entergy to the NRC which stated that Entergy has directed SNC to 
    fabricate all fourteen planned casks with the increased length and that 
    Entergy plans to continue to conduct evaluations in accordance with 10 
    CFR 72.48.
        The Petition has been referred to the Office of Nuclear Material 
    Safety and Safeguards pursuant to 10 CFR 2.206. As provided by Section 
    2.206, appropriate action will be taken with regard to the specific 
    issues raised by the Petition in a reasonable time.
        A copy of the Petition is available for inspection at the 
    Commission's Public Document Room at 2120 L Street, NW., Washington, DC 
    20555.
    
        Dated at Rockville, Mayland, this 16th day of August 1994.
    
        For the Nuclear Regulatory Commission.
    Robert M. Bernero,
    Director, Office of Nuclear Material Safety and Safeguards.
    [FR Doc. 94-20756 Filed 8-23-94; 8:45 am]
    BILLING CODE 7590-01-M
    
    
    

Document Information

Published:
08/24/1994
Department:
Nuclear Regulatory Commission
Entry Type:
Uncategorized Document
Document Number:
94-20756
Pages:
0-0 (1 pages)
Docket Numbers:
Federal Register: August 24, 1994, Docket Nos. 50-313/368, 72-1007, License Nos. DPR-51/NPF-6