94-13385. List of Approved Spent Fuel Storage Casks: Addition  

  • [Federal Register Volume 59, Number 105 (Thursday, June 2, 1994)]
    [Unknown Section]
    [Page 0]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 94-13385]
    
    
    [[Page Unknown]]
    
    [Federal Register: June 2, 1994]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    10 CFR Part 72
    
    RIN 3150-AF02
    
     
    
    List of Approved Spent Fuel Storage Casks: Addition
    
    AGENCY: Nuclear Regulatory Commission.
    
    ACTION: Proposed rule.
    
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    SUMMARY: The Nuclear Regulatory Commission (NRC) is proposing to amend 
    its regulations to add the Standardized NUHOMS Horizontal Modular 
    Storage System to the List of Approved Spent Fuel Storage Casks. This 
    amendment will allow the holders of power reactor operating licenses to 
    store spent fuel in this approved cask under a general license.
    
    DATES: Submit comments by August 16, 1994. Comments received after this 
    date will be considered if it is practical to do so, but the Commission 
    is able to assure consideration only for comments received on or before 
    this date.
    
    ADDRESSES: Send comments to: The Secretary, U.S. Nuclear Regulatory 
    Commission, Washington, DC 20555. ATTN: Docketing and Service Branch.
        Deliver comments to: One White Flint North, 11555 Rockville Pike, 
    Rockville, Maryland, between 7:45 a.m. and 4:15 p.m. Federal workdays.
        Copies of the comments received and the environmental assessment 
    and finding of no significant impact can be examined at the NRC Public 
    Document Room, 2120 L Street NW. (Lower Level), Washington, DC. Single 
    copies of these documents can be obtained from Mr. G. E. Gundersen, 
    Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory 
    Commission, Washington, DC 20555, telephone (301) 492-3803.
    
    FOR FURTHER INFORMATION CONTACT: Mr. G. E. Gundersen, Office of Nuclear 
    Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 
    20555, telephone (301) 492-3803; or Mr K. C. Leu, Office of Nuclear 
    Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
    Washington, DC 20555, telephone (301) 504-2685.
    
    SUPPLEMENTARY INFORMATION:
    
    Background
    
        Section 218(a) of the Nuclear Waste Policy Act of 1982 (NWPA) 
    directs that, ``[T]he Secretary [of the Department of Energy (DOE)] 
    shall establish a demonstration program in cooperation with the private 
    sector, for the dry storage of spent nuclear fuel at civilian power 
    reactor sites, with the objective of establishing one or more 
    technologies that the [Nuclear Regulatory] Commission may, by rule, 
    approve for use at the sites of civilian nuclear power reactors 
    without, to the maximum extent practicable, the need for additional 
    site-specific approvals by the NRC.'' Section 133 of the NWPA states, 
    in part, that ``the Commission shall, by rule, establish procedures for 
    the licensing of any technology approved by the Commission under 
    Section 218(a) for use at the site of any civilian nuclear power 
    reactor.''
        To implement this mandate, the Commission approved dry storage of 
    spent nuclear fuel in NRC-approved casks, publishing a final rule on 10 
    CFR Part 72 entitled ``General License for Storage of Spent Fuel at 
    Power Reactor Sites'' (55 FR 29181). This rule also established a new 
    subpart L within 10 CFR part 72 entitled ``Approval of Spent Fuel 
    Storage Casks,'' containing procedures and criteria for obtaining NRC 
    approval of dry storage cask designs.
        The 1990 rulemaking listed four casks in Sec. 72.214 of subpart K 
    as approved by the NRC for storage of spent fuel at power reactor sites 
    under general license by persons authorized to possess or operate 
    nuclear power reactors. Since then, two more casks have been listed in 
    Sec. 72.214, one on April 7, 1993 (58 FR 17948) and another on October 
    5, 1993 (58 FR 51762).
    
    Discussion
    
        This proposed rulemaking would add the Standardized NUHOMS 
    Horizontal Modular Storage System to the list of NRC approved casks for 
    spent fuel storage in Sec. 72.214. Following the procedures specified 
    in Sec. 72.230 of Subpart L, VECTRA Technologies, Inc. (formerly 
    Pacific Nuclear Fuel Services, Inc. (PNFSI))\1\ submitted an 
    application for NRC approval, together with a ``Safety Analysis Report 
    for the Standardized NUHOMS Horizontal Modular Storage System for 
    Irradiated Nuclear Fuel'' (SAR), NUH-003, Revision 2, dated November 
    1993. The NRC evaluated VECTRA's submittal and issued a draft Safety 
    Evaluation Report (SER) on VECTRA'S SAR and a draft certificate of 
    compliance for the Standardized NUHOMS Horizontal Modular Storage 
    System. On January 24, 1994, Pacific Nuclear Systems, Inc., (parent 
    company of PNSFI) changed its name to VECTRA Technologies, Inc., after 
    it acquired ABB Impell Corporation.
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        \1\On January 24, 1994, Pacific Nuclear Systems, Inc., (parent 
    company of PNFSI) changed its name to VECTRA Technologies Inc.
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        The NRC is proposing to approve VECTRA's Standardized NUHOMS 
    Modular Storage System for Irradiated Nuclear Fuel, for storage of 
    spent fuel under the conditions specified in the draft certificate of 
    compliance. This cask, when used in accordance with the conditions 
    specified in the certificate of compliance and NRC regulations, will 
    meet the requirements of 10 CFR Part 72; thus, adequate protection of 
    the public health and safety would be ensured. This cask is being 
    proposed for listing under Sec. 72.214, ``List of Approved Spent Fuel 
    Storage Casks'' to allow holders of power reactor operating licensees 
    to store spent fuel in this cask under a general license. The 
    certificate of compliance would terminate 20 years after the effective 
    date of the final rule listing the cask in Sec. 72.214, unless the 
    cask's certificate of compliance is renewed. The certificate contains 
    conditions for use which are similar to those for other NRC approved 
    casks, however, the certificate of compliance for each cask may differ 
    in some specifics--such as, certificate number, operating procedures, 
    training exercises, spent fuel specification. The draft certificate of 
    compliance for the Standardized NUHOMS cask and the underlying draft 
    SER, are available for inspection and comment at the NRC Public 
    Document Room, 2120 L Street, NW. (Lower Level), Washington, DC. Single 
    copies of the proposed certificate of compliance may be obtained from 
    Mr. K. C. Leu, Office of Nuclear Material Safety and Safeguards, U.S. 
    Nuclear Regulatory Commission, Washington, DC 20555, telephone (301) 
    504-2685.
    
    Submission of Comments in Electronic Format
    
        In addition to the original paper copy, commenters are encouraged 
    to submit a copy of the letter in electronic format on IBM PC-
    compatible 5.25- or 3.5-inch computer diskette. Data files should be 
    provided in one of the following formats: WordPerfect, IBM Document 
    Content Architecture/Revisable-Form-Text (DCA/RFT), or unformatted 
    ASCII text.
    
    Finding of No Significant Environmental Impact: Availability
    
        Under the National Environmental Policy Act of 1969, as amended, 
    and the NRC regulations in Subpart A of 10 CFR Part 51, the NRC has 
    determined that this rule, if adopted, would not be a major Federal 
    action significantly affecting the quality of the human environment, 
    and therefore, an environmental impact statement is not required. The 
    rule is mainly administrative in nature. It would not change safety 
    requirements and would not have significant environmental impacts. The 
    proposed rule would add one cask known as the Standardized NUHOMS 
    Modular Storage System to the list of approved spent fuel storage casks 
    that power reactor licensees can use to store spent fuel at reactor 
    sites without additional site-specific approvals by the NRC. The 
    environmental assessment and finding of no significant impact on which 
    this determination is based are available for inspection at the NRC 
    Public Document Room, 2120 L Street NW. (Lower Level), Washington, DC. 
    Single copies of the environmental assessment and finding of no 
    significant impact are available from Mr. G. Gundersen, Office of 
    Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 
    Washington, DC 20555, Telephone (301) 492-3803.
    
    Paperwork Reduction Act Statement
    
        This proposed rule does not contain a new or amended information 
    collection requirement subject to the Paperwork Reduction Act of 1980 
    (44 U.S.C. 3501 et seq.). Existing requirements were approved by the 
    Office of Management and Budget, Approval Number 3150-0132.
    
    Regulatory Analysis
    
        On July 18, 1990 (55 FR 29181), the Commission issued an amendment 
    to 10 CFR Part 72. The amendment provided for the storage of spent 
    nuclear fuel under a general license. Any nuclear power reactor 
    licensee can use these casks if (1) they notify the NRC in advance, (2) 
    the spent fuel is stored under the conditions specified in the cask's 
    certificate of compliance, and (3) the conditions of the general 
    license are met. In that rulemaking, four spent fuel storage casks were 
    approved for use at reactor sites, and were listed in 10 CFR 72.214. 
    That rulemaking envisioned that storage casks certified in the future 
    could be routinely added to the listing in Sec. 72.214 through 
    rulemaking procedures. Procedures and criteria for obtaining NRC 
    approval of new spent fuel storage cask designs were provided in 10 CFR 
    72.230. Subsequently, two additional casks were added to the listing in 
    Sec. 72.214 in 1993.
        The alternative to this proposed action is to withhold 
    certification of this new design and give a site-specific license to 
    each utility that proposed to use the cask. This alternative however, 
    would cost the NRC more time and money for each site-specific review. 
    In addition, withholding certification would ignore the procedures and 
    criteria currently in place for the addition of new cask designs. 
    Further, it is in conflict with NWPA direction to the Commission to 
    approve technologies for the use of spent fuel storage at the sites of 
    civilian nuclear power reactors without, to the extent practicable, the 
    need for additional site reviews. Also, this alternative is 
    anticompetitive in that it would exclude new vendors without cause and 
    would arbitrarily limit the choice of cask designs available to power 
    reactor licensees.
        Approval of the proposed rulemaking would eliminate the above 
    problems. Further, the proposed rule will have no adverse effect on the 
    public health and safety.
        The benefit of this proposed rule to nuclear power reactor 
    licensees is to make available a greater choice of spent fuel storage 
    cask designs which can be used under a general license. However, the 
    newer cask design may have a market advantage over the existing designs 
    in that power reactor licensees may prefer to use the newer casks with 
    improved features. The new cask vendors with casks to be listed in 
    Sec. 72.214 benefit by having to obtain NRC certificates only once for 
    a design which can then be used by more than one power reactor 
    licensee. Vendors with cask designs already listed may be adversely 
    impacted in that power reactor licensees may choose a newly listed 
    design over an existing one. However, the NRC is required by its 
    regulations and NWPA direction to certify and list approved casks. The 
    NRC also benefits because it will need to certify a cask design only 
    once for use by multiple licensees. Casks approved through rulemaking 
    are to be suitable for use under a range of environmental conditions 
    sufficiently broad to encompass multiple nuclear power plants in the 
    United States without the need for farther site-specific approval by 
    NRC.
        This proposed rulemaking has no significant identifiable impact or 
    benefit on other Government agencies.
        Based on the above discussion of the benefits and impacts of the 
    alternatives, the NRC concludes that the requirements of the proposed 
    rule are commensurate with the Commission's responsibilities for public 
    health and safety and the common defense and security. No other 
    available alternative is believed to be as satisfactory, and thus, this 
    action is recommended.
    
    Regulatory Flexibility Certification
    
        In accordance with the Regulatory Flexibility Act of 1980, (5 
    U.S.C. 605(b)), the Commission certifies that this rule will not, if 
    promulgated, have a significant economic impact on a substantial number 
    of small entities. This proposed rule affects only the licensing and 
    operation of nuclear power plants and cask vendors. The companies that 
    own these plants do not fall within the scope of the definition of 
    ``small entities'' set forth in the Regulatory Flexibility Act or the 
    Small Business Size Standards set out in regulations issued by the 
    Small Business Administration at 13 CFR part 121.
    
    Backfit Analysis
    
        The NRC has determined that the backfit rule (10 CFR 50.109 or 10 
    CFR 72.62) does not apply to this proposed rule, and thus, a backfit 
    analysis is not required for this proposed rule because this amendment 
    does not involve any provisions which would impose backfits as defined 
    in the backfit rule.
    
    List of Subjects In 10 CFR Part 72
    
        Manpower training programs, Nuclear materials, Occupational safety 
    and health, Reporting and recordkeeping requirements, Security 
    measures, Spent fuel.
    
        For the reasons set out in the preamble and under the authority of 
    the Atomic Energy Act of 1954, as amended; the Energy Reorganization 
    Act of 1974, as amended; and 5 U.S.C. 553; the NRC is proposing to 
    adopt the following amendments to 10 CFR part 72.
    
    PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF 
    SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE
    
        The authority citation for part 72 continues to read as follows:
    
        Authority: Secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183, 
    184, 186, 187, 189, 68 Stat. 929, 930, 932, 933, 934, 935, 948, 953, 
    954, 955, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C. 
    2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233, 
    2234, 2236, 2237, 2238, 2282); sec. 274, Pub. L. 86-373, 73 Stat. 
    688, as amended (42 U.S.C. 2021); sec. 201, as amended, 202, 206, 88 
    Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846); 
    Pub. L. 95-601, sec. 10, 92 Stat. 2951 (42 U.S.C. 5851); sec. 102, 
    Pub. L. 91-190, 83 Stat. 853 (42 U.S.C. 4332); secs. 131, 132, 133, 
    135, 137, 141, Pub. L. 97-425, 96 Stat. 2229, 2230, 2232, 2241, sec. 
    148, Pub. L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10151, 10152, 
    10153, 10155, 10157, 10161, 10168).
        Section 72.44(g) also issued under secs. 142(b) and 148(c), (d), 
    Pub. L. 100-203, 101 Stat. 1330-232, 1330-236 (42 U.S.C. 10162(b), 
    1068(c)(d)). Section 72.46 also issued under sec. 189, 68 Stat. 955 
    (42 U.S.C. 2239); sec. 134, Pub. L. 97-425, 96 Stat. 2230 (42 U.S.C. 
    10154). Section 72.96(d) also issued under sec. 145 (g), Pub. L. 
    100-203, 101 Stat. 1330-235 (42 U.S.C. 10165(g)). Subpart J also 
    issued under secs. 2(2), 2(15), 2(19), 117(a), 141(h), Pub. L. 97-
    425, 96 Stat. 2202, 2203, 2204, 2222, 2244, (42 U.S.C. 10101, 
    10137(a), 10161(h)). Subparts K and L are also issued under sec. 
    133, 98 Stat. 2230 (42 U.S.C. 10153) and sec. 218(a), 96 Stat. 2252 
    (42 U.S.C. 10198).
    
        In Sec. 72.214, Certificate of Compliance 1004 is added to read as 
    follows:
    
    
    Sec. 72.214.  List of approved spent fuel storage casks.
    
    * * * * *
    Certificate Number: 1004
    SAR Submitted by: VECTRA Technologies, Inc.
    SAR Title: Safety Analysis Report for the Standardized NUHOMS 
    Horizontal Modular Storage System for Irradiated Nuclear Fuel, Revision 
    2
    Docket Number: 72-1004
    Certification Expiration Date: (20 years after final rule effective 
    date)
    Model Numbers: NUHOMS-24P for Pressurized Water Reactor fuel; NUHOMS-
    52B for Boiling Water Reactor fuel.
    * * * * *
        Dated at Rockville, Maryland, this 12th day of May 1994.
    
        For the Nuclear Regulatory Commission.
    James M. Taylor,
    Executive Director for Operations.
    [FR Doc. 94-13385 Filed 6-1-94; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
06/02/1994
Department:
Nuclear Regulatory Commission
Entry Type:
Uncategorized Document
Action:
Proposed rule.
Document Number:
94-13385
Dates:
Submit comments by August 16, 1994. Comments received after this date will be considered if it is practical to do so, but the Commission is able to assure consideration only for comments received on or before this date.
Pages:
0-0 (1 pages)
Docket Numbers:
Federal Register: June 2, 1994
RINs:
3150-AF02
CFR: (1)
10 CFR 72.214