E9-24562. List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 7

AGENCY:

Nuclear Regulatory Commission.

ACTION:

Proposed rule.

SUMMARY:

The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage cask regulations by revising the Holtec International (Holtec) HI-STORM 100 dry storage cask system listing within the “List of Approved Spent Fuel Storage Casks” to include Amendment No. 7 to Certificate of Compliance (CoC) Number 1014. Amendment No. 7 would modify the CoC to add the HI-STORM 100U system to the HI-STORM 100 cask system. The HI-STORM 100U system allows for the underground storage of dry spent nuclear fuel (SNF) by utilizing an underground vertical ventilated module (VVM) that can accept certain multipurpose canisters (MPCs) previously certified for storage of SNF in the Holtec aboveground HI-STORM system. In addition, the amendment would reinstate the decay heat limits for damaged fuel and fuel debris in Appendix B, Technical Specification (TS) 2.4, for the aboveground system that had been inadvertently deleted from Amendment Nos. 5 and 6; incorporate separate TS Appendices A and B for the aboveground system (Apps. A and B) and for the HI-STORM 100U system (Apps. A-100U and B-100U); revise Appendix B, TS 3.4.5, to be consistent with the required system thermal boundary conditions, as submitted in the applicant's safety analysis report for a fire accident condition, and with Holtec's original (i.e., initial certificate application or Amendment 0) submittal and the NRC's original safety evaluation report; and revise and add certain definitions in Appendix A, TS 1.1, to include the VVM. The amendment will also incorporate minor editorial corrections in the TS for the aboveground system.

DATES:

Comments on the proposed rule must be received on or before November 12, 2009.

ADDRESSES:

You may submit comments by any one of the following methods. Please include Docket ID NRC-2009-0349 in the subject line of your comments. Comments submitted in writing or in electronic form will be posted on the NRC Web site and on the Federal rulemaking Web site Regulations.gov. Because your comments will not be edited to remove any identifying or contact information, the NRC cautions you against including any information in your submission that you do not want to be publicly disclosed.

The NRC requests that any party soliciting or aggregating comments received from other persons for submission to the NRC inform those persons that the NRC will not edit their comments to remove any identifying or contact information, and therefore, they should not include any information in their comments that they do not want publicly disclosed.

Federal Rulemaking Web site: Go to http://www.regulations.gov and search for documents filed under Docket ID NRC-2009-0349. Address questions about NRC dockets to Carol Gallagher 301-492-3668; e-mail [e-mail].

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

E-mail comments to: [e-mail]. If you do not receive a reply e-mail confirming that we have received your comments, contact us directly at 301-415-1677.

Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 am and 4:15 pm Federal workdays. (Telephone [phone])

Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at 301-415-1101.

You can access publicly available documents related to this proposed rule using the following methods:

NRC's Public Document Room (PDR): The public may examine and have copied for a fee publicly available documents at NRC's PDR, Public File Area O1 F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland.

NRC's Agencywide Documents Access and Management System (ADAMS): Publicly available documents created or received at the NRC are available electronically at the NRC's Electronic Reading Room at http://www.nrc.gov/​reading-rm/​adams.html. From this site, the public can gain entry into ADAMS, which provides text and image files of NRC's public documents. If you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS, contact the NRC's PDR reference staff at 1-800-397-4209, 301-415-4737 or by e-mail to [e-mail].

Federal Rulemaking Web site: Public comments and supporting materials related to this proposed rule can be found at http://www.regulations.gov by searching on Docket ID NRC-2009-0349.

FOR FURTHER INFORMATION CONTACT:

Neelam Bhalla, Office of Federal and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone [phone], e-mail [e-mail].

SUPPLEMENTARY INFORMATION:

For additional supplementary information, see the direct final rule published in the Rules and Regulations section of this Federal Register.

Procedural Background

This rule is limited to the changes contained in Amendment 7 to CoC No. 1014 and does not include other aspects of the HI-STORM 100 design. Because NRC considers this action noncontroversial and routine, the NRC is publishing this proposed rule concurrently as a direct final rule in the Rules and Regulations section of this Federal Register. Adequate protection of public health and safety continues to be ensured. The direct final rule will become effective on December 28, 2009. However, if the NRC receives significant adverse comments on the direct final rule by November 12, 2009 then the NRC will publish a document that withdraws 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 on this action in the event the direct final rule is withdrawn.

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, a substantive response is required when:

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 rule, CoC, or TS.

For additional procedural information and the regulatory analysis, see the direct final rule published in the Rules and Regulations section of this Federal Register.

List of Subjects in 10 CFR Part 72

• Administrative practice and procedure
• Hazardous waste
• Nuclear materials
• Occupational safety and health
• Radiation protection
• Reporting and recordkeeping requirements
• Security measures
• Spent fuel
• Whistleblowing

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; the Nuclear Waste Policy Act of 1982, 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, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C 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. 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); sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504 note); sec. 651(e), Pub. L. 109-58, 119 Stat. 806-10 (42 U.S.C. 2014, 2021, 2021b, 2111).

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:

§ 72.214

List of approved spent fuel storage casks.

* * * * *

Certificate Number: 1014.

Initial Certificate Effective Date: May 31, 2000.

Amendment Number 1 Effective Date: July 15, 2002.

Amendment Number 2 Effective Date: June 7, 2005.

Amendment Number 3 Effective Date: May 29, 2007.

Amendment Number 4 Effective Date: January 8, 2008.

Amendment Number 5 Effective Date: July 14, 2008.

Amendment Number 6 Effective Date: August 17, 2009

Amendment Number 7 Effective Date: December 28, 2009.

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: May 31, 2020.

Model Number: HI-STORM 100 System.

* * * * *

Dated at Rockville, Maryland, this 24th day of September 2009.

For the Nuclear Regulatory Commission.

R.W. Borchardt,

Executive Director for Operations.