[Federal Register Volume 65, Number 121 (Thursday, June 22, 2000)]
[Proposed Rules]
[Pages 38795-38796]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 00-15541]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

RIN 3150-AG55


List of Approved Spent Fuel Storage Casks: VSC-24 Revision

AGENCY: Nuclear Regulatory Commission.

ACTION: Proposed rule.

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SUMMARY: The Nuclear Regulatory Commission (NRC) is proposing to amend 
its regulations revising the Pacific Sierra Nuclear Associates (PSNA) 
VSC-24 cask system listing within the ``List of approved spent fuel 
storage casks'' to include Amendment No. 2 to the Certificate of 
Compliance (CoC). Amendment No. 2 will revise the Technical 
Specifications and CoC regarding welding and nondestructive examination 
of welds, the method for determining cask drain time during loading, 
the minimum temperature for moving the loaded multi-assembly sealed 
basket (MSB), artificial thermal loads other than spent fuel that may 
be used to obtain temperature data, and the maximum permissible air 
outlet temperature. In addition, the amendment includes changes to the 
Technical Specifications and CoC to correct typographical errors and to 
make other minor clarifications and changes. This amendment will allow 
the holders of power reactor operating licenses to store spent fuel in 
the VSC-24 cask system, as amended, under a general license.

DATES: Comments on the proposed rule must be received on or before July 
24, 2000.

ADDRESSES: Submit comments to: Secretary, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001. Attention: Rulemakings and 
Adjudications Staff.
    Deliver comments to 11555 Rockville Pike, Rockville, Maryland, 
between 7:30 a.m. and 4:15 p.m. on Federal workdays.
    You may also provide comments via the NRC's interactive rulemaking 
website (http://ruleforumllnl.gov). This site provides the capability 
to upload comments as files (any format), if your web browser supports 
that function. For information about the interactive rulemaking 
website, contact Ms. Carol Gallagher, (301) 415-5905 (e-mail: 
[email protected]).
    Copies of any comments received may be examined at the NRC Public 
Document Room, 2120 L Street, NW. (Lower Level), Washington, DC.

FOR FURTHER INFORMATION CONTACT: Gordon Gundersen, telephone (301) 415-
6195, e-mail, [email protected] of the Office of Nuclear Material Safety and 
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.

SUPPLEMENTARY INFORMATION: For additional information see the Direct 
Final Rule published in the rules section of this Federal Register.

Procedural Background

    Because NRC considers this action noncontroversial and routine, we 
are publishing this proposed rule concurrently as a direct final rule. 
The direct final rule will become effective on September 5, 2000. 
However, if the NRC receives significant adverse comments on the direct 
final rule by July 24, 2000, then the NRC will publish a notice to 
withdraw the direct final rule. If the direct final rule is withdrawn, 
the NRC will address the comments received in response to the proposed 
revisions in a subsequent final rule. Absent significant modifications 
to the proposed revisions requiring republication, the NRC will not 
initiate a second comment period for this action in the event the 
direct final rule is withdrawn.

List of Subjects in 10 CFR Part 72

    Criminal penalties, 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

    1. 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.

[[Page 38796]]

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 as amended 
by Pub. L. 10d-48b, sec. 7902, 10b Stat. 31b3 (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), 
10168(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).

    2. Section 72.214, Certificate of Compliance (CoC) 1007 is revised 
to read as follows:


Sec. 72.214  List of approved spent fuel storage casks.

* * * * *
Certificate Number: 1007.
Initial Certificate Effective Date: May 7, 1993.
Amendment Number 1 Effective Date: May 30, 2000.
Amendment Number 2 Effective Date: September 5, 2000.
SAR Submitted by: Pacific Sierra Nuclear Associates.
SAR Title: Final Safety Analysis Report for the Ventilated Storage Cask 
System.
Docket Number: 72-1007.
Certificate Expiration Date: May 7, 2013.
Model Number: VSC-24.
* * * * *

    Dated at Rockville, Maryland, this 25th day of May, 2000.

    For the Nuclear Regulatory Commission.
William D. Travers,
Executive Director for Operations.
[FR Doc. 00-15541 Filed 6-21-00; 8:45 am]
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