01-6169. List of Approved Spent Fuel Storage Casks: HI-STAR 100 Revision

AGENCY:

Nuclear Regulatory Commission.

ACTION:

Proposed rule.

SUMMARY:

The Nuclear Regulatory Commission (NRC) is proposing to amend its regulations by revising the Holtec International HI-STAR 100 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 revises the HI-STAR 100 cask system Appendix B of the Technical Specifications (TS), Item 1.4.6, “Specific Parameters and Analysis for the Storage Pad and Foundation” to simplify the language of this specification. The current 60-g limit for cask drop and tipover events in TS Item 1.4.6 would remain unchanged. This amendment would allow the holders of power reactor operating licenses to store spent fuel in the HI-STAR 100 cask system, as amended, under a general license.

DATES:

Comments on the proposed rule must be received on or before April 12, 2001.

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://ruleforum.llnl.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, [phone] (e-mail: [e-mail]).

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. These documents also may be viewed and downloaded electronically via the rulemaking website.

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/​NRC/​ADAMS/​index.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 the NRC's public documents. An electronic copy of the proposed CoC and Preliminary Safety Evaluation Report (SER) can be found in ADAMS under Accession No. ML003770774. For more information, contact the NRC Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737 or by email to [e-mail].

FOR FURTHER INFORMATION CONTACT:

Stan Turel, telephone [phone], e-mail, [e-mail] 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 with a direct final rule. The direct final rule will become effective on May 29, 2001. However, if the NRC receives significant adverse comments on the direct final rule by April 12, 2001, then the NRC will publish a document 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. 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) 1008 is revised to read as follows:

§ 72.214

List of approved spent fuel storage casks.

* * * * *

Certificate Number: 1008.

Initial Certificate Effective Date: October 4, 1999.

Amendment Number 1 Effective Date: December 26, 2000.

Amendment Number 2 Effective Date: May 29, 2001.

SAR Submitted by: Holtec International.

SAR Title: Final Safety Analysis Report for the HI-STAR 1008 Cask System.

Docket Number: 72-1008.

Certificate Expiration Date: October 4, 2019.

Model Number: HI-STAR 100.

* * * * *

Dated at Rockville, Maryland, this 1st day of March, 2001.

For the Nuclear Regulatory Commission.

William D. Travers,

Executive Director for Operations.