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Proposed Rule

List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision

Document Details

Information about this document as published in the Federal Register.

Published Document

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AGENCY:

Nuclear Regulatory Commission.

ACTION:

Proposed rule.

SUMMARY:

The Nuclear Regulatory Commission (NRC) is proposing to amend its regulations revising the Holtec International HI-STORM 100 cask system listing within the list of approved spent fuel storage casks to include Amendment 1 to the Certificate of Compliance (CoC). This amendment would modify the present cask system design to permit a licensee, under a general license, to: add four new multipurpose canisters; add new containers for damaged fuel; add the HI-STORM 100S overpack and the 100A and 100SA high-seismic anchored overpacks; allow the storage of high-burnup fuel; delete the Technical Specifications for special requirements for the first systems in place and for training requirements and relocate these requirements to the main body of CoC 1014; and allow the storage of selected nonfuel hardware. The amendment would also use revised thermal analysis tools to include natural convection heat transfer, revise the helium backfill requirements to allow a helium density measurement to be used, allow a helium drying system rather than the existing vacuum drying system, and require soluble boron during canister loading for certain higher enriched fuels. In addition, modifications would be made applicable to CoC conditions and sections of Appendix A and Appendix B to the CoC to reflect the changes.

DATES:

Comments on the proposed rule must be received on or before April 26, 2002.

ADDRESSES:

Submit comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attn: Rulemakings and Adjudications Staff.

Deliver comments to 11555 Rockville Pike, Rockville, MD, between 7:30 a.m. and 4:15 p.m. on Federal workdays.

Certain documents related to this rulemaking, as well as all public comments received on this rulemaking, may be viewed and downloaded electronically via the NRC's rulemaking website at http://ruleforum.llnl.gov. You may also provide comments via this website by uploading comments as files (any format) if your web browser supports that function. For information about the interactive rulemaking site, contact Ms. Carol Gallagher, (301) 415-5905; email CAG@nrc.gov.

Certain documents related to this rule, including comments received by the NRC, may be examined at the NRC Public Document Room, 11555 Rockville Pike, Rockville, MD. For more information, contact the NRC Public Document Room (PDR) Reference staff at 1-800-397-4209, 301-415-4737 or by email to pdr@nrc.gov.

Documents created or received at the NRC after November 1, 1999, are also available electronically at the NRC's Public Electronic Reading Room on the Internet at http://www.nrc.gov/​reading-rm.html. From this site, the public can gain entry into the NRC's Agencywide Documents Access and Management System (ADAMS), which provides text and image files of NRC's public documents. An electronic copy of the proposed CoC and preliminary safety evaluation report (SER) can be found under ADAMS Accession No. ML013330457. If you do not have access to ADAMS or if their problems in accessing the documents located in ADAMS, contact the NRC PDR Reference staff at 1-800-397-4209, 301-415-4737 or by email to pdr@nrc.gov.

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FOR FURTHER INFORMATION CONTACT:

Jayne M. McCausland, telephone (301) 415-6219, email jmm2@nrc.gov, of the Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

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SUPPLEMENTARY INFORMATION:

For additional information see the direct final rule published in the final rules section of this Federal Register.

Procedural Background

This rule is limited to the changes contained in Amendment 1 to CoC No. 1014 and does not include other aspects of the Holtec HI-STORM 100 cask system design. The NRC is using the “direct final rule procedure” to issue this amendment because it represents a limited and routine change to an existing CoC that is expected to be noncontroversial. Adequate protection of public health and safety continues to be ensured.

Because NRC considers this action noncontroversial and routine, the proposed rule is being published concurrently as a direct final rule. The direct final rule will become effective on June 10, 2002. However, if the NRC receives significant adverse comments by April 26, 2002, then the NRC will publish a document that withdraws this action and will address the comments received in response to the proposed amendments published elsewhere in this issue of the Federal Register. A significant adverse comment is a comment where the commenter explains why the rule would be inappropriate, including challenges to the rule's underlying premise or approach, or would be ineffective or unacceptable without a change. A comment is adverse and significant if:

(1) The comment opposes the rule and provides a reason sufficient to require a substantive response in a notice-and-comment process. For example, in a substantive response:

(a) The comment causes the NRC staff to reevaluate (or reconsider) its position or conduct additional analysis;

(b) The comment raises an issue serious enough to warrant a substantive response to clarify or complete the record; or

(c) The comment raises a relevant issue that was not previously addressed or considered by the NRC staff.

(2) The comment proposes a change or an addition to the rule, and it is apparent that the rule would be ineffective or unacceptable without incorporation of the change or addition.

(3) The comment causes the NRC staff to make a change (other than editorial) to the CoC or TS.

These comments will be addressed in a subsequent final rule. The NRC will not initiate a second comment period on this action.

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List of Subjects in 10 CFR Part 72

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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.

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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:

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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 as amended by Pub. L. 102-486, sec. 7902, 106 Stat. 3123 (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).

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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. In § 72.214, Certificate of Compliance 1014 is revised to read as follows:

List of approved spent fuel storage casks.
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Certificate Number: 1014.

Initial Certificate Effective Date: June 1, 2000.

Amendment Number 1 Effective Date: June 10, 2002.

SAR Submitted by: Holtec International.

SAR Title: Final Safety Analysis Report for the HI-STORM 100 Cask System.

Docket Number: 72-1014.

Certificate Expiration Date: June 1, 2020.

Model Number: HI-STORM 100.

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Dated at Rockville, Maryland, this 13th day of March, 2002.

For the Nuclear Regulatory Commission.

William D. Travers,

Executive Director for Operations.

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[FR Doc. 02-7321 Filed 3-26-02; 8:45 am]

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