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List of Approved Spent Fuel Storage Casks: Transnuclear, Inc. Standardized NUHOMS® Cask System

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AGENCY:

Nuclear Regulatory Commission.

ACTION:

Direct final rule.

SUMMARY:

The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Transnuclear, Inc. Standardized NUHOMS® Cask System listing within the “List of Approved Spent Fuel Storage Casks” to include Amendment No. 11 to Certificate of Compliance (CoC) No. 1004. Amendment No. 11 revises authorized contents to include: adding a new transfer cask (TC), the OS197L, for use with the 32PT and 61BT dry shielded canisters (DSC); and converting the CoC No. 1004 Technical Specifications (TS) to the format in NUREG-1745, “Standard Format and Content for Technical Specifications for 10 CFR [Title 10 of the Code of Federal Regulations] Part 72 Cask Certificates of Compliance.” In addition, the amendment makes several other changes as described under the “Discussion of Changes” heading in the SUPPLEMENTARY INFORMATION section of this document.

DATES:

The final rule is effective January 7, 2014, unless significant adverse comments are received by November 25, 2013. If the rule is withdrawn as a result of such comments, timely notice of the withdrawal will be published in the Federal Register. Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date.

ADDRESSES:

Please refer to Docket ID NRC-2012-0020 when contacting the NRC about the availability of information for this final rule. You may access information and comment submittals related to this final rulemaking, which the NRC possesses and is publicly available by any of the following methods:

  • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0020. Address questions about NRC dockets to Carol Gallagher, telephone: 301-287-3422, email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURHTER INFORMATION CONTACT section of this document.
  • NRC's Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC Library at http://www.nrc.gov/​reading-rm/​adams.html. To begin the search, select “ADAMS Public Documents” and then select “Begin Web-based ADAMS Search.” For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced in this document (if that document is available in ADAMS) is provided the first time that a document is referenced. The proposed CoC and preliminary safety evaluation report (SER) are available in ADAMS under Package Accession No. ML120130550. The ADAMS Accession No. for the Transnuclear, Inc. Standardized NUHOMS® Cask System Amendment No. 11 application dated April 10, 2007, is ML071240088.
  • NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room O-1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
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FOR FURTHER INFORMATION CONTACT:

Gregory R. Trussell, Office of Federal and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone: 301-415-6445, email: Gregory.Trussell@nrc.gov.

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SUPPLEMENTARY INFORMATION:

Table of Contents

I. Procedural Background

II. Background

III. Discussion of Changes

IV. Voluntary Consensus Standards

V. Agreement State Compatibility

VI. Plain Writing

VII. Finding of No Significant Environmental Impact: Availability

VIII. Paperwork Reduction Act Statement

IX. Regulatory Analysis

X. Regulatory Flexibility Certification

XI. Backfitting and Issue Finality

XII. Congressional Review Act

I. Procedural Background

This rule is limited to the changes contained in Amendment No. 11 to CoC No. 1004 and does not include other aspects of the Transnuclear, Inc. Standardized NUHOMS® 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. The amendment to the rule will become effective on January 7, 2014. However, if the NRC receives significant adverse comments on this direct final rule by November 25, 2013, then the NRC will publish a document that withdraws this action and will subsequently address the comments received in a final rule as a response to the companion proposed rule published in the Proposed Rule section of this issue of the Federal Register. Absent significant modifications to the proposed revisions requiring republication, the NRC will not initiate a second comment period on this action.

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 TSs.

For detailed instructions on submitting comments, please see the companion proposed rule published in the Proposed Rule section of this issue of the Federal Register.

II. Background

Section 218(a) of the Nuclear Waste Policy Act (NWPA) of 1982, as amended, requires that “the Secretary [of the Department of Energy] shall establish a demonstration program, in cooperation with the private sector, for the dry storage of spent nuclear fuel at civilian nuclear 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 Start Printed Page 63376nuclear power reactors without, to the maximum extent practicable, the need for additional site-specific approvals by the Commission.” 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 219(a) [sic: 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 under a general license by publishing a final rule in 10 CFR part 72, which added a new subpart K within 10 CFR part 72 entitled, “General License for Storage of Spent Fuel at Power Reactor Sites” (55 FR 29181; July 18, 1990). This rule also established a new subpart L within 10 CFR part 72 entitled, “Approval of Spent Fuel Storage Casks,” which contains procedures and criteria for obtaining NRC approval of spent fuel storage cask designs. The NRC subsequently issued a final rule on December 22,1994 (59 FR 65898), that approved the Standardized NUHOMS® Cask System design and added it to the list of NRC-approved cask designs in 10 CFR 72.214 as CoC No. 1004.

III. Discussion of Changes

On April 10, 2007 (ADAMS Accession No. ML071240088), and as supplemented on August 23, 2007 (ADAMS Accession No. ML072410293), December 21, 2007 (ADAMS Accession No. ML080020420), June 12, 2008 (ADAMS Accession No. ML081700238), August 14, 2009 (ADAMS Accession No. ML13149A438), August 5, 2010 (ADAMS Accession No. ML102230097), and February 25, 2011 (ADAMS Accession No. ML110590060), Transnuclear, Inc., the holder of CoC No. 1004, submitted to the NRC a request to amend CoC No. 1004. Specifically, Transnuclear, Inc. requested changes to: (1) add a new TC, the OS197L, for use with the 32PT and 61BT DSC; and (2) convert the CoC No. 1004 TS to the format in NUREG-1745. The previously approved payloads and the corresponding TSs have been retained “as-is” in the new format of the proposed TSs, including tables and figures. In addition, this change removes the bases for the Limiting Conditions for Operation and Surveillance Requirements from the TSs and relocates the bases to Chapter 10 of the Updated Final Safety Analysis Report (UFSAR). Specific changes to the TSs are:

  • Converting the existing TSs for CoC No. 1004 proposed Amendment 10 TS, to the improved TS format and content consistent with NUREG-1745 requirements.
  • Deleting the TC dose rates for all currently licensed payloads (TSs 1.2.11, 1.2.11 a, 1.2.11 b, 1.2.11 c, 1.2.11d, and 1.2.11e). These TS are redundant to TS 1.2.7 which regulates dose limits for a loaded DSC when stored inside a horizontal storage module where a payload resides during its 20 year licensed life span.
  • Deleting DSC vacuum drying duration limits for all the licensed payloads (TSs 1.2.17, 1.2.17a, 1.2.17b, and 1.2.17c).
  • Implementing the following NRC suggested revisions that were adopted by letter dated August 14, 2009 (ADAMS Accession No. ML092330146).

○ Adding Sections 4.4.1 and 4.4.2 to the proposed TSs to reflect additional restrictions for the use of the OS197L TC.

○ Revising Section 5.2.4, “Radiation Protection Program,” of the proposed TSs to include dose assessment for occupational exposures during loading operations. If remote handling devices are used for movement of a transfer cask during loading, then the dose assessment shall include recovery from a potential malfunction of these devices.

○ Adding Section 4.2.1 of the proposed TSs to reflect the additional restrictions for all horizontal storage modules if an independent spent fuel storage installation (ISFSI) is located in a coastal salt water marine environment.

  • Changing the following conditions in the CoC:

○ Revising CoC Condition 6 to clarify that general licensees may use either the original issue of the certificate or use previously approved amendments of this certificate for storage under the provisions of 10 CFR 72.210.

○ Deleting CoC Conditions 7 and 8 as they have been moved to proposed TSs 5.5 and 5.6, respectively.

  • Revising the CoC and TSs to add requirements for the OS197L TC.

As documented in the SER (ADAMS Accession No. ML120130593), the NRC staff performed a detailed safety evaluation of the proposed CoC amendment request. There are no significant changes to cask design requirements in the proposed CoC amendment. Considering the specific design requirements for each accident condition, the design of the cask would prevent loss of containment, shielding, and criticality control. If there is no loss of containment, shielding, or criticality control, the environmental impacts would be insignificant. This amendment does not reflect a significant change in design or fabrication of the cask. In addition, any resulting occupational exposure or offsite dose rates from the implementation of Amendment No. 11 would remain well within the 10 CFR part 20 limits. Thus, the proposed

CoC changes will not result in any radiological or non-radiological environmental impacts that significantly differ from the environmental impacts evaluated in the environmental assessment supporting the July 18, 1990, final rule. There will be no significant change in the types or significant revisions in the amounts of any effluent released, no significant increase in the individual or cumulative radiation exposure, and no significant increase in the potential for or consequences from radiological accidents.

This direct final rule revises the Standardized NUHOMS® Cask System listing in 10 CFR 72.214 by adding Amendment No. 11 to CoC No.1004. The amendment consists of the changes previously described, as set forth in the revised CoC and TSs. The revised TSs are identified in the SER.

The amended Standardized NUHOMS® cask design, when used under the conditions specified in the CoC, the TSs, and the NRC's regulations, will meet the requirements of 10 CFR part 72; thus, adequate protection of public health and safety will continue to be ensured. When this direct final rule becomes effective, persons who hold a general license under 10 CFR 72.210 may load spent nuclear fuel into Standardized NUHOMS® Cask Systems that meet the criteria of Amendment No. 11 to CoC No. 1004 under 10 CFR 72.212.

IV. Voluntary Consensus Standards

The National Technology Transfer and Advancement Act of 1995 (Pub. L. 104-113) requires that Federal agencies use technical standards that are developed or adopted by voluntary consensus standards bodies unless the use of such a standard is inconsistent with applicable law or otherwise impractical. In this direct final rule, the NRC will revise the Standardized NUHOMS® Cask System design listed in 10 CFR 72.214, “List of Approved Spent Fuel Storage Casks.” This action does not constitute the establishment of a standard that contains generally applicable requirements.

V. Agreement State Compatibility

Under the “Policy Statement on Adequacy and Compatibility of Agreement State Programs” approved by the Commission on June 30, 1997, and published in the Federal Register on September 3, 1997 (62 FR 46517), this rule is classified as Compatibility Start Printed Page 63377Category “NRC.” Compatibility is not required for Category “NRC” regulations. The NRC program elements in this category are those that relate directly to areas of regulation reserved to the NRC by the Atomic Energy Act of 1954, as amended, or the provisions of 10 CFR. Although an Agreement State may not adopt program elements reserved to the NRC, it may wish to inform its licensees of certain requirements via a mechanism that is consistent with the particular State's administrative procedure laws, but does not confer regulatory authority on the State.

VI. Plain Writing

The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal agencies to write documents in a clear, concise, well-organized manner that also follows other best practices appropriate to the subject or field and the intended audience. The NRC has attempted to use plain language in promulgating this rule consistent with the Federal Plain Writing Act guidelines.

VII. Finding of No Significant Environmental Impact: Availability

A. The Action

The action is to amend 10 CFR 72.214 to revise the Transnuclear, Inc. Standardized NUHOMS® Cask System listing within the “List of Approved Spent Fuel Storage Casks” to include Amendment No. 11 to CoC No. 1004.

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 NRC has made a finding of no significant impact on the basis of this environmental assessment.

B. The Need for the Action

This rule amends the CoC for the Standardized NUHOMS® Cask System design within the list of approved spent fuel storage casks that power reactor licensees can use to store spent fuel at reactor sites under a general license. Specifically, Transnuclear, Inc. requested changes to revise authorized contents to include: (1) adding a new TC, the OS197L, for use with the 32PT and 61BT DSC; and (2) converting the CoC No. 1004 TSs to the format in NUREG-1745, “Standard Format and Content for Technical Specifications for 10 CFR Part 72 Cask Certificates of Compliance.” The previously approved payloads and the corresponding TSs have been retained “as-is” in the new format of the proposed TSs, including tables and figures. In addition, this change removes the bases for the Limiting Conditions for Operation and Surveillance Requirements from the TSs and relocates the bases to Chapter 10 of the UFSAR.

C. Environmental Impacts of the Action

On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10 CFR part 72 to provide for the storage of spent nuclear fuel under a general license in cask designs approved by the NRC. The potential environmental impact of using NRC approved storage casks was initially analyzed in the environmental assessment for the 1990 final rule. The environmental assessment for this Amendment No. 11 tiers off of the environmental assessment for the July 18, 1990, final rule. Tiering on past environmental assessments is a standard process under the National Environmental Policy Act.

Standardized NUHOMS® Cask Systems are designed to mitigate the effects of design basis accidents that could occur during storage. Design basis accidents account for human-induced events and the most severe natural phenomena reported for the site and surrounding area. Postulated accidents analyzed for an ISFSI, the type of facility at which a holder of a power reactor operating license would store spent fuel in casks in accordance with 10 CFR part 72, include tornado winds and tornado-generated missiles, a design basis earthquake, a design basis flood, an accidental cask drop, lightning effects, fire, explosions, and other incidents.

Based upon its review, the NRC staff has reasonable assurance that the design of the shielding system associated with the OS197L light weight transfer cask (a component of the Standardized NUHOMS® System), as currently proposed, and when limited to use of the 61BT and 32PT DSCs, is in compliance with 10 CFR part 72 and that the applicable design and acceptance criteria, including 10 CFR part 20, have been satisfied. The evaluation of the shielding design provides reasonable assurance that the OS197L light weight transfer cask will allow safe transfer of spent fuel to dry storage in accordance with 10 CFR 72.236(d). Considering the specific design requirements for each accident condition, the design of the cask would prevent loss of containment, shielding, and criticality control. If there is no loss of containment, shielding, or criticality control, the environmental impacts would be insignificant. This amendment does not reflect a significant change in design or fabrication of the cask. There are no significant changes to cask design requirements in the proposed CoC amendment. In addition, any resulting occupational exposure or offsite dose rates from the implementation of Amendment No. 11 would remain well within the 10 CFR part 20 limits. Therefore, the proposed CoC changes will not result in any radiological or non-radiological environmental impacts that significantly differ from the environmental impacts evaluated in the environmental assessment supporting the July 18, 1990, final rule. There will be no significant change in the types or significant revisions in the amounts of any effluent released, no significant increase in the individual or cumulative radiation exposure, and no significant increase in the potential for or consequences from radiological accidents.

The staff documented its findings in a safety evaluation report which is available in ADAMS under Accession No. ML120130550.

D. Alternative to the Action

The alternative to this action is to deny approval of Amendment No. 11 and end the final rulemaking. Consequently, any 10 CFR part 72 general licensee that seeks to load spent nuclear fuel into the Standardized NUHOMS® Cask System in accordance with the changes described in proposed Amendment No. 11 would have to request an exemption from the requirements of 10 CFR 72.212 and 72.214. Under this alternative, interested licensees would have to prepare, and the NRC would have to review, a separate exemption request, thereby increasing the administrative burden upon the NRC and the costs to each licensee. Therefore, the environmental impacts would be the same or less than the action.

E. Alternative Use of Resources

Approval of Amendment No. 11 to CoC No. 1004 would result in no irreversible commitments of resources.

F. Agencies and Persons Contacted

No agencies or persons outside the NRC were contacted in connection with the preparation of this environmental assessment.

G. Finding of No Significant Impact

The environmental impacts of the action have been reviewed under the requirements in 10 CFR part 51.

Based on the foregoing environmental assessment, the NRC concludes that this Start Printed Page 63378rulemaking entitled, “List of Approved Spent Fuel Storage Casks: Standardized NUHOMS® Cask System,” will not have a significant effect on the human environment. Therefore, the NRC has determined that an environmental impact statement is not necessary for this rule.

Documents related to this rulemaking, including comments received by the NRC, may be examined at the NRC Public Document Room, Room O-1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.

VIII. Paperwork Reduction Act Statement

This rule does not contain any information collection requirements and, therefore, is not subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements were approved by the Office of Management and Budget (OMB), Approval Number 3150-0132.

Public Protection Notification

The NRC may not conduct or sponsor, and a person is not required to respond to a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.

IX. Regulatory Analysis

On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10 CFR part 72 to provide for the storage of spent nuclear fuel under a general license in cask designs approved by the NRC. Any nuclear power reactor licensee can use NRC-approved cask designs to store spent nuclear fuel if it notifies the NRC in advance, the spent fuel is stored under the conditions specified in the cask's CoC, and the conditions of the general license are met. A list of NRC-approved cask designs is contained in 10 CFR 72.214. On December 22, 1994 (59 FR 65898), the NRC issued an amendment to 10 CFR part 72 that approved the Standardized NUHOMS® Cask System design by adding it to the list of NRC-approved cask designs in 10 CFR 72.214.

On April 10, 2007 (ADAMS Accession No. ML071240088), and as supplemented on August 23, 2007 (ML072410293), December 21, 2007 (ML080020420), June 12, 2008 (ML081700238), August 14, 2009 (ML13149A438), August 5, 2010 (ML102230097), and February 25, 2011 (ML110590060), Transnuclear, Inc. submitted an application to amend the Standardized NUHOMS® Cask System as described in Section III.

The alternative to this action is to withhold approval of Amendment No. 11 and to require any 10 CFR part 72 general licensee seeking to load spent nuclear fuel into Standardized NUHOMS® Cask Systems under the changes described in Amendment No. 11 to request an exemption from the requirements of 10 CFR 72.212 and 72.214. Under this alternative, each interested 10 CFR part 72 licensee would have to prepare, and the NRC would have to review, a separate exemption request, thereby increasing the administrative burden upon the NRC and the costs to each licensee.

Approval of the direct final rule is consistent with previous NRC actions. Further, as documented in the SER and the environmental assessment, the direct final rule will have no adverse effect on public health and safety or the environment. This direct final rule has no significant identifiable impact or benefit on other Government agencies. Based on this regulatory analysis, the NRC concludes that the requirements of the direct final rule are commensurate with the NRC's responsibilities for public health and safety and the common defense and security. No other available alternative is believed to be as satisfactory, and therefore, this action is recommended.

X. Regulatory Flexibility Certification

Under the Regulatory Flexibility Act of 1980 (5 U.S.C. 605(b)), the NRC certifies that this rule will not, if issued, have a significant economic impact on a substantial number of small entities. This direct final rule affects only nuclear power plant licensees and Transnuclear, Inc. These entities do not fall within the scope of the definition of small entities set forth in the Regulatory Flexibility Act or the size standards established by the NRC (10 CFR 2.810).

XI. Backfitting and Issue Finality

The NRC has determined that the backfit rule (10 CFR 72.62) does not apply to this direct final rule. Therefore, a backfit analysis is not required. This direct final rule revises the CoC No. 1004 for the Transnuclear, Inc. Standardized NUHOMS® Cask System, as currently listed in 10 CFR 72.214, “List of Approved Spent Fuel Storage Casks.” The revision consists of Amendment No. 11, which: (i) Adds a new transfer cask, the OS197L, for use with the 32PT and 61BT dry shielded canisters, and associated changes to address the use of the new transfer cask; (ii) converts the TS in the CoC to the format in NUREG-1745, “Standard Format and Content for Technical Specifications for 10 CFR [Title 10 of the Code of Federal Regulations] Part 72 Cask Certificates of Compliance;” (iii) deletes the TC dose rates for all currently licensed payloads, which are redundant to TS 1.2.7 (regulating dose limits for a loaded DSC when stored inside a horizontal storage module where a payload resides during its 20 year licensed life span); (iv) deletes DSC vacuum drying duration limits for all the licensed payloads; (v) revises Section 5.2.4, “Radiation Protection Program,” of the TS to include dose assessment for occupational exposures during loading operations, and require that if remote handling devices are used for movement of a transfer cask during loading, then the dose assessment shall include recovery from a potential malfunction of these devices; (vi) adds Section 4.2.1 to the TSs to reflect additional restrictions for all horizontal storage modules if an ISFSI is located in a coastal salt water marine environment; (vii) revises CoC Condition 6 to clarify that general licensees may use either the original issue of the certificate or use previously approved amendments of this certificate for storage; and (vi) deletes CoC Conditions 7 and 8 as they are moved to TSs 5.5 and 5.6, respectively.

Amendment 11 to CoC No. 1004 for the Standardized NUHOMS® Cask System was initiated by Transnuclear, Inc. and was not submitted in response to new NRC requirements, or an NRC request for amendment. Amendment 11 applies only to new casks fabricated and used under Amendment 11. These changes do not affect existing users of the Standardized NUHOMS® Cask System, and the current amendment (10) continues to be effective for existing users, consistent with new CoC Condition 6. While current CoC users may comply with the new requirements in Amendment 11, this would be a voluntary decision on the part of current users. For these reasons, Amendment 11 to CoC No. 1004 does not constitute backfitting under 10 CFR 72.62, 10 CFR 50.109(a)(1), or otherwise represent an inconsistency with the issue finality provisions applicable to combined licenses in Part 52. Accordingly, no backfit analysis or additional documentation addressing the issue finality criteria in Part 52 has been prepared by the staff.

XII. Congressional Review Act

The Office of Management and Budget has not found this to be a major rule as defined in the Congressional Review Act.

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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; the Nuclear Waste Policy Act of 1982, as amended; and 5 U.S.C. 552 and 553; the NRC is adopting the following amendments to 10 CFR part 72.

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PART 72—LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE

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1. The authority citation for part 72 continues to read as follows:

End Amendment Part Start Authority

Authority: Atomic Energy Act secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42 U.S.C. 2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233, 2234, 2236, 2237, 2238, 2273, 2282, 2021); Energy Reorganization Act sec. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); National Environmental Policy Act sec. 102 (42 U.S.C. 4332); Nuclear Waste Policy Act secs. 131, 132, 133, 135, 137, 141 148 (42 U.S.C. 10151, 10152, 10153, 10155, 10157, 10161, 10168); sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504 note); Energy Policy Act of 2005, Pub. L. No. 109-58, 119 Stat. 549 (2005).

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Section 72.44(g) also issued under secs. Nuclear Waste Policy Act 142(b) and 148(c), (d) (42 U.S.C. 10162(b), 10168(c), (d)). Section 72.46 also issued under Atomic Energy Act sec. 189 (42 U.S.C. 2239); Nuclear Waste Policy Act sec. 134 (42 U.S.C. 10154). Section 72.96(d) also issued under Nuclear Waste Policy Act sec. 145(g) (42 U.S.C. 10165(g)). Subpart J also issued under Nuclear Waste Policy Act secs. 117(a), 141(h) (42 U.S.C. 10137(a), 10161(h)). Subpart K is also issued under sec. 218(a) (42 U.S.C. 10198).

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2. In § 72.214, Certificate of Compliance 1004 is revised to read as follows:

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List of approved spent fuel storage casks.
* * * * *

Certificate Number: 1004.

Initial Certificate Effective Date: January 23, 1995.

Amendment Number 1 Effective Date: April 27, 2000.

Amendment Number 2 Effective Date: September 5, 2000.

Amendment Number 3 Effective Date: September 12, 2001.

Amendment Number 4 Effective Date: February 12, 2002.

Amendment Number 5 Effective Date: January 7, 2004.

Amendment Number 6 Effective Date: December 22, 2003.

Amendment Number 7 Effective Date: March 2, 2004.

Amendment Number 8 Effective Date: December 5, 2005.

Amendment Number 9 Effective Date: April 17, 2007.

Amendment Number 10 Effective Date: August 24, 2009.

Amendment Number 11 Effective Date: January 7, 2014.

SAR Submitted by: Transnuclear, Inc.

SAR Title: Final Safety Analysis Report for the Standardized NUHOMS® Horizontal Modular Storage System for Irradiated Nuclear Fuel.

Docket Number: 72-1004.

Certificate Expiration Date: January 23, 2015.

Model Number: NUHOMS® -24P, -24PHB, -24PTH, -32PT, -32PTH1, -52B, -61BT, and -61BTH.

* * * * *
Start Signature

Dated at Rockville, Maryland, this 2nd day of October 2013.

For the Nuclear Regulatory Commission.

Mark A. Satorius,

Executive Director for Operations.

End Signature End Supplemental Information

[FR Doc. 2013-24906 Filed 10-23-13; 8:45 am]

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