List of Approved Spent Fuel Storage Casks: Standardized NUHOMS®, 4615-4618 [E7-1644]

Download as PDF 4615 Rules and Regulations Federal Register Vol. 72, No. 21 Thursday, February 1, 2007 This section of the FEDERAL REGISTER contains regulatory documents having general applicability and legal effect, most of which are keyed to and codified in the Code of Federal Regulations, which is published under 50 titles pursuant to 44 U.S.C. 1510. The Code of Federal Regulations is sold by the Superintendent of Documents. Prices of new books are listed in the first FEDERAL REGISTER issue of each week. NUCLEAR REGULATORY COMMISSION 10 CFR Part 72 RIN 3150–AI03 List of Approved Spent Fuel Storage Casks: Standardized NUHOMS System Revision 9 Nuclear Regulatory Commission. ACTION: Direct final rule. AGENCY: The Nuclear Regulatory Commission (NRC) is amending its regulations revising the Transnuclear, Inc., Standardized NUHOMS System listing within the ‘‘List of Approved Spent Fuel Storage Casks’’ to include Amendment No. 9 to Certificate of Compliance (CoC) Number 1004. Amendment No. 9 will modify the CoC by revising Technical Specifications 1.2.1 and 1.2.14 to add the FramatomeANP, Version 9x9–2 fuel assemblies as approved contents for storage in the NUHOMS–61BT dry shielded canister, under the general license provisions of 10 CFR part 72. DATES: The final rule is effective April 17, 2007, unless significant adverse comments are received by March 5, 2007. 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. If the rule is withdrawn, timely notice will be published in the Federal Register. ADDRESSES: You may submit comments by any one of the following methods. Please include the following number (RIN 3150–AI03) in the subject line of your comments. Comments on rulemakings submitted in writing or in electronic form will be made available for public inspection. Because your comment will not be edited to remove rmajette on PROD1PC67 with RULES SUMMARY: VerDate Aug<31>2005 15:01 Jan 31, 2007 Jkt 211001 any identifying or contact information, the NRC cautions you against including personal information such as social security numbers and birth dates in your submission. Mail comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, ATTN: Rulemakings and Adjudications Staff. E-mail comments to: SECY@nrc.gov. If you do not receive a reply e-mail confirming that we have received your comments, contact us directly at (301) 415–1966. You may also submit comments via the NRC’s rulemaking Web site at http://rulemaking.llnl.gov. Address questions about our rulemaking Web site to Carol Gallagher (301) 415– 5905; e-mail cag@nrc.gov. Comments can also be submitted via the Federal eRulemaking Portal http:// www.regulations.gov. Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. Federal workdays [telephone (301) 415– 1966]. Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at (301) 415–1101. Publicly available documents related to this rulemaking may be viewed electronically on the public computers at the NRC’s Public Document Room (PDR), O–1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. Selected documents, including comments, can be viewed and downloaded electronically via the NRC rulemaking Web site at http:// ruleforum.llnl.gov. Publicly available documents created or received at the NRC after November 1, 1999, are available electronically at the NRC’s Electronic Reading Room at http://www.nrc.gov/NRC/ADAMS/ index.html. From this site, the public can gain entry into the NRC’s Agencywide Document Access and Management System (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 PDR Reference staff at 1–800–397–4209, 301–415–4737, or by e-mail to pdr@nrc.gov. An electronic copy of the CoC No. 1004, the proposed Technical Specifications (TS), and the preliminary safety evaluation report (SER) for Amendment 9 can be found under PO 00000 Frm 00001 Fmt 4700 Sfmt 4700 ADAMS Accession Nos. ML062830065, ML062830067, and ML062830069. CoC No. 1004, the proposed TS, the preliminary SER for Amendment No. 9, and the environmental assessment, are available for inspection at the NRC PDR, 11555 Rockville Pike, Rockville, MD. Single copies of these documents may be obtained from Jayne M. McCausland, Office of Federal and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, telephone (301) 415–6219, e-mail jmm2@nrc.gov. FOR FURTHER INFORMATION CONTACT: Jayne M. McCausland, Office of Federal and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone (301) 415– 6219, e-mail jmm2@nrc.gov. SUPPLEMENTARY INFORMATION: Background Section 218(a) of the Nuclear Waste Policy Act of 1982, as amended (NWPA), requires that ‘‘[t]he Secretary [of the Department of Energy (DOE)] 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 nuclear 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 ‘‘[t]he Commission shall, by rule, establish procedures for the licensing of any technology approved by the Commission under Section 218(a) for use at the site of any civilian nuclear power reactor.’’ To implement this mandate, the NRC 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 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’’ containing procedures and criteria for obtaining NRC approval of spent fuel storage cask designs. The NRC subsequently issued a final rule on E:\FR\FM\01FER1.SGM 01FER1 4616 Federal Register / Vol. 72, No. 21 / Thursday, February 1, 2007 / Rules and Regulations December 22, 1994 (59 FR 65898), that approved the Standardized NUHOMS System (NUHOMS–24P and –52B) cask designs and added them to the list of NRC-approved cask designs in 10 CFR 72.214 as CoC No. 1004. Amendments 3, 5, and 6, respectively, added the –61BT, –32PT, –24PHB designs to the Standardized NUHOMS System. Discussion On April 18, 2006, and as supplemented on June 21, 2006, the certificate holder (Transnuclear, Inc.) submitted an application to the NRC to amend CoC No. 1004 to permit a Part 72 licensee to store Framatome-ANP, Version 9x9–2 fuel assemblies (FANP9 9x9–2) in the NUHOMS–61BT dry shielded canister. No other changes to the Standardized NUHOMS System design were requested in this application. The NRC staff performed a detailed safety evaluation of the proposed CoC amendment request and found that an acceptable safety margin is maintained. In addition, the NRC staff has determined that there continues to be reasonable assurance that public health and safety and the environment will be adequately protected. This direct final rule revises the Standardized NUHOMS System cask design listing in 10 CFR 72.214 by adding Amendment No. 9 to CoC No. 1004. The amendment consists of changes to the TS that will allow for the addition of the FANP9 9x9–2 fuel assemblies as approved contents for storage in the NUHOMS–61BT dry shielded canister. The particular TS which are changed are identified in the NRC staff’s SER for Amendment No. 9. The amended Standardized NUHOMS System, when used under the conditions specified in the CoC, the TS, and NRC regulations, will meet the requirements of Part 72; thus, adequate protection of public health and safety will continue to be ensured. Discussion of Amendments by Section Section 72.214 List of Approved Spent Fuel Storage Casks Certificate No. 1004 is revised by adding the effective date of Amendment No. 9. rmajette on PROD1PC67 with RULES Procedural Background This rule is limited to the changes contained in Amendment 9 to CoC No. 1004 and does not include other aspects of the Standardized NUHOMS 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 VerDate Aug<31>2005 15:01 Jan 31, 2007 Jkt 211001 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 April 17, 2007. However, if the NRC receives significant adverse comments by March 5, 2007, 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 elsewhere in this Federal Register. 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-andcomment 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. 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 System design listed in § 72.214 (List of NRC-approved spent fuel storage cask designs). This action does not constitute the establishment of a standard that contains generally applicable requirements. Agreement State Compatibility Under the ‘‘Policy Statement on Adequacy and Compatibility of Agreement State Programs’’ approved by PO 00000 Frm 00002 Fmt 4700 Sfmt 4700 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 Category ‘‘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 (AEA), or the provisions of Title 10 of the Code of Federal Regulations. Although an Agreement State may not adopt program elements reserved to 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. Plain Language The Presidential Memorandum, ‘‘Plain Language in Government Writing,’’ published June 10, 1998 (63 FR 31883), directed that the Government’s documents be in clear and accessible language. The NRC requests comments on this direct final rule specifically with respect to the clarity and effectiveness of the language used. Comments should be sent to the address listed under the heading ADDRESSES above. Finding of No Significant Environmental Impact: Availability 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 prepared an environmental assessment and, on the basis of this environmental assessment, has made a finding of no significant impact. This rule will amend the CoC for the Standardized NUHOMS System 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. The amendment will modify the CoC by revising TS 1.2.1 and 1.2.14 to add the FANP9 9x9–2 fuel assemblies as approved contents for storage in the NUHOMS–61BT dry shielded canister. The environmental assessment and finding of no significant impact on which this determination is based are available for inspection at the NRC Public Document Room, 11555 Rockville Pike, Rockville, MD. Single copies of the environmental assessment E:\FR\FM\01FER1.SGM 01FER1 Federal Register / Vol. 72, No. 21 / Thursday, February 1, 2007 / Rules and Regulations and finding of no significant impact are available from Jayne M. McCausland, Office of Federal and State Materials and Environmental Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, telephone (301) 415–6219, e-mail jmm2@nrc.gov. Paperwork Reduction Act Statement This direct final rule does not contain a new or amended information collection requirement 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, Approval Number 3150–0132. rmajette on PROD1PC67 with RULES 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. 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, 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 part 72 that approved the Standardized NUHOMS System design by adding it to the list of NRC-approved cask designs in 10 CFR 72.214. On April 18, 2006, and as supplemented on June 21, 2006, the certificate holder, Transnuclear, Inc., submitted an application to the NRC to amend CoC No. 1004 to permit a part 72 licensee to use the FANP9 9x9–2 fuel assemblies in the NUHOMS–61BT dry shielded canister. The alternative to this action is to withhold approval of Amendment No. 9 and to require any part 72 licensee seeking to use Amendment No. 9 to request an exemption from the requirements of 10 CFR 72.212 and 72.214. Under this alternative, each interested 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. VerDate Aug<31>2005 15:01 Jan 31, 2007 Jkt 211001 Approval of the direct final rule is consistent with previous NRC actions. Further, the direct final rule will have no adverse effect on public health and safety. 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 thus, this action is recommended. 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 the licensing and operation of nuclear power plants, independent spent fuel storage facilities, and TN. The companies that own these plants 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). Backfit Analysis The NRC has determined that the backfit rule (10 CFR 72.62) does not apply to this direct final rule because this amendment does not involve any provisions that would impose backfits as defined in 10 CFR Chapter I. Therefore, a backfit analysis is not required. Congressional Review Act Under the Congressional Review Act of 1996, the NRC has determined that this action is not a major rule and has verified this determination with the Office of Information and Regulatory Affairs, Office of Management and Budget. List of Subjects in 10 CFR Part 72 Administrative practice and procedure, Criminal penalties, Manpower training programs, Nuclear materials, Occupational safety and health, Penalties, Radiation protection, Reporting and recordkeeping requirements, Security measures, Spent fuel, Whistleblowing. I 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. 552 and 553; the NRC is adopting the following amendments to 10 CFR part 72. PO 00000 Frm 00003 Fmt 4700 Sfmt 4700 4617 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: I 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 1004 is revised to read as follows: I § 72.214 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. E:\FR\FM\01FER1.SGM 01FER1 4618 Federal Register / Vol. 72, No. 21 / Thursday, February 1, 2007 / Rules and Regulations Amendment Number 8 Effective Date: December 5, 2005. Amendment Number 9 Effective Date: April 17, 2007. 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, –52B, –61BT, –32PT, –24PHB, and –24PTH. * * * * * Dated at Rockville, Maryland, this 19th day of January, 2007. For the Nuclear Regulatory Commission. Luis A. Reyes, Executive Director for Operations. [FR Doc. E7–1644 Filed 1–31–07; 8:45 am] BILLING CODE 7590–01–P DEPARTMENT OF TRANSPORTATION Regional Counsel, ACE–7, Attention: Rules Docket CE255, 901 Locust, Room 506, Kansas City, Missouri 64106; or delivered in duplicate to the Regional Counsel at the above address. Comments must be marked: CE255. Comments may be inspected in the Rules Docket weekdays, except Federal holidays, between 7:30 a.m. and 4 p.m. FOR FURTHER INFORMATION CONTACT: J. Lowell Foster, Federal Aviation Administration, Aircraft Certification Service, Small Airplane Directorate, ACE–111, 901 Locust, Room 301, Kansas City, Missouri, 816–329–4125, fax 816–329–4090. SUPPLEMENTARY INFORMATION: The FAA has determined that notice and opportunity for prior public comment hereon are impracticable because the substance of these special conditions has been subject to the public comment process in several prior instances with no substantive comments received. The FAA therefore finds that good cause exists for making these special conditions effective upon issuance. Federal Aviation Administration Comments Invited 14 CFR Part 23 Interested persons are invited to submit such written data, views, or arguments as they may desire. Communications should identify the regulatory docket or special condition number and be submitted in duplicate to the address specified above. All communications received on or before the closing date for comments will be considered by the Administrator. The special conditions may be changed in light of the comments received. All comments received will be available in the Rules Docket for examination by interested persons, both before and after the closing date for comments. A report summarizing each substantive public contact with FAA personnel concerning this rulemaking will be filed in the docket. Commenters wishing the FAA to acknowledge receipt of their comments submitted in response to this notice must include a self-addressed, stamped postcard on which the following statement is made: ‘‘Comments to CE255.’’ The postcard will be date stamped and returned to the commenter. [Docket No. CE255; Special Conditions No. 23–195–SC] Special Conditions: Aviation Technology Group (ATG), Inc., Javelin Model 100 Series Airplane; Flight Performance, Flight Characteristics, and Operating Limitations Federal Aviation Administration (FAA), DOT. ACTION: Final special conditions; request for comments. rmajette on PROD1PC67 with RULES AGENCY: SUMMARY: These special conditions are issued for the Aviation Technology Group (ATG), Inc., Javelin Model 100 Series airplane. This airplane will have a novel or unusual design feature(s) associated with engine location, certain performance, flight characteristics and operating limitations necessary for this type of airplane. The applicable airworthiness regulations do not contain adequate or appropriate safety standards for this design feature. These special conditions contain the additional safety standards that the Administrator considers necessary to establish a level of safety equivalent to airworthiness standards applicable to these airplanes. DATES: The effective date of these special conditions is January 24, 2007. Comments must be received on or before March 5, 2007. ADDRESSES: Comments on these special conditions may be mailed in duplicate to: Federal Aviation Administration, VerDate Aug<31>2005 15:01 Jan 31, 2007 Jkt 211001 Background On February 15, 2005, Aviation Technology Group (ATG); 8001 South InterPort Boulevard, Suite 310; Englewood, Colorado 80112–5951, applied for a type certificate for their new Model 100 Javelin airplane in accordance with the airworthiness standards in 14 CFR, part 23. The Javelin is a two-place, twin engine, PO 00000 Frm 00004 Fmt 4700 Sfmt 4700 turbofan-powered light jet airplane with a planned maximum operating altitude of 45,000 feet. Part 23 regulations in effect on the date of ATG’s application do not contain adequate or appropriate safety standards for a small, high performance jet airplane such as the Javelin. In accordance with Small Airplane Directorate policy, the safety standards for flight performance, flight characteristics and operational limitations that the Federal Aviation Administration (FAA) finds necessary to establish an acceptable level of safety for this type of airplane are presented in this special condition. Type Certification Basis Under the provisions of 14 CFR, part 21, § 21.17, ATG must show that the Model 100 meets the applicable provisions of part 23, as amended by Amendment 23–1 through 23–55 thereto. If the Administrator finds that the applicable airworthiness regulations (i.e., 14 CFR part 23) do not contain adequate or appropriate safety standards for the ATG Model 100 series because of a novel or unusual design feature, special conditions are prescribed under the provisions of § 21.16. Special conditions, as appropriate, as defined in § 11.19, are issued in accordance with § 11.38, and become part of the type certification basis in accordance with § 21.17(a)(2). Special conditions are initially applicable to the model for which they are issued. Should the type certificate for that model be amended later to include any other model that incorporates the same novel or unusual design feature, the special conditions would also apply to the other model under the provisions of § 21.101(a)(1). In addition to the applicable airworthiness regulations and special conditions, the Model 100 must comply with the part 23 fuel vent and exhaust emission requirements of 14 CFR, part 34 and the part 23 noise certification requirements of 14 CFR part 36; and the FAA must issue a finding of regulatory adequacy pursuant to § 611 of Public Law 92–574, the ‘‘Noise Control Act of 1972.’’ Novel or Unusual Design Features ATG intends to certificate the Javelin in both utility and acrobatic categories. The ATG Javelin Model 100 will incorporate the following novel or unusual design features: • Two-place, tandem configuration. • Maximum takeoff weight of approximately 6,900 pounds. • Design cruise speed of 500 knots calibrated airspeed. E:\FR\FM\01FER1.SGM 01FER1

Agencies

[Federal Register Volume 72, Number 21 (Thursday, February 1, 2007)]
[Rules and Regulations]
[Pages 4615-4618]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-1644]



========================================================================
Rules and Regulations
                                                Federal Register
________________________________________________________________________

This section of the FEDERAL REGISTER contains regulatory documents 
having general applicability and legal effect, most of which are keyed 
to and codified in the Code of Federal Regulations, which is published 
under 50 titles pursuant to 44 U.S.C. 1510.

The Code of Federal Regulations is sold by the Superintendent of Documents. 
Prices of new books are listed in the first FEDERAL REGISTER issue of each 
week.

========================================================================


Federal Register / Vol. 72, No. 21 / Thursday, February 1, 2007 / 
Rules and Regulations

[[Page 4615]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

RIN 3150-AI03


List of Approved Spent Fuel Storage Casks: Standardized 
NUHOMS[reg] System Revision 9

AGENCY: Nuclear Regulatory Commission.

ACTION: Direct final rule.

-----------------------------------------------------------------------

SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its 
regulations revising the Transnuclear, Inc., Standardized 
NUHOMS[reg] System listing within the ``List of Approved 
Spent Fuel Storage Casks'' to include Amendment No. 9 to Certificate of 
Compliance (CoC) Number 1004. Amendment No. 9 will modify the CoC by 
revising Technical Specifications 1.2.1 and 1.2.14 to add the 
Framatome-ANP, Version 9x9-2 fuel assemblies as approved contents for 
storage in the NUHOMS[reg]-61BT dry shielded canister, under 
the general license provisions of 10 CFR part 72.

DATES: The final rule is effective April 17, 2007, unless significant 
adverse comments are received by March 5, 2007. 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. If 
the rule is withdrawn, timely notice will be published in the Federal 
Register.

ADDRESSES: You may submit comments by any one of the following methods. 
Please include the following number (RIN 3150-AI03) in the subject line 
of your comments. Comments on rulemakings submitted in writing or in 
electronic form will be made available for public inspection. Because 
your comment will not be edited to remove any identifying or contact 
information, the NRC cautions you against including personal 
information such as social security numbers and birth dates in your 
submission.
    Mail comments to: Secretary, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, ATTN: Rulemakings and Adjudications Staff.
    E-mail comments to: SECY@nrc.gov. If you do not receive a reply e-
mail confirming that we have received your comments, contact us 
directly at (301) 415-1966. You may also submit comments via the NRC's 
rulemaking Web site at http://rulemaking.llnl.gov. Address questions 
about our rulemaking Web site to Carol Gallagher (301) 415-5905; e-mail 
cag@nrc.gov. Comments can also be submitted via the Federal eRulemaking 
Portal http://www.regulations.gov.
    Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland 
20852, between 7:30 a.m. and 4:15 p.m. Federal workdays [telephone 
(301) 415-1966].
    Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at 
(301) 415-1101.
    Publicly available documents related to this rulemaking may be 
viewed electronically on the public computers at the NRC's Public 
Document Room (PDR), O-1F21, One White Flint North, 11555 Rockville 
Pike, Rockville, Maryland. Selected documents, including comments, can 
be viewed and downloaded electronically via the NRC rulemaking Web site 
at http://ruleforum.llnl.gov.
    Publicly available documents created or received at the NRC after 
November 1, 1999, are available electronically at the NRC's Electronic 
Reading Room at http://www.nrc.gov/NRC/ADAMS/index.html. From this 
site, the public can gain entry into the NRC's Agencywide Document 
Access and Management System (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 PDR Reference staff at 1-800-397-4209, 301-415-4737, or 
by e-mail to pdr@nrc.gov. An electronic copy of the CoC No. 1004, the 
proposed Technical Specifications (TS), and the preliminary safety 
evaluation report (SER) for Amendment 9 can be found under ADAMS 
Accession Nos. ML062830065, ML062830067, and ML062830069.
    CoC No. 1004, the proposed TS, the preliminary SER for Amendment 
No. 9, and the environmental assessment, are available for inspection 
at the NRC PDR, 11555 Rockville Pike, Rockville, MD. Single copies of 
these documents may be obtained from Jayne M. McCausland, Office of 
Federal and State Materials and Environmental Management Programs, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone 
(301) 415-6219, e-mail jmm2@nrc.gov.

FOR FURTHER INFORMATION CONTACT: Jayne M. McCausland, Office of Federal 
and State Materials and Environmental Management Programs, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6219, e-mail jmm2@nrc.gov.

SUPPLEMENTARY INFORMATION:

Background

    Section 218(a) of the Nuclear Waste Policy Act of 1982, as amended 
(NWPA), requires that ``[t]he Secretary [of the Department of Energy 
(DOE)] 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 nuclear 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 ``[t]he Commission shall, by rule, establish 
procedures for the licensing of any technology approved by the 
Commission under Section 218(a) for use at the site of any civilian 
nuclear power reactor.''
    To implement this mandate, the NRC 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 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'' containing 
procedures and criteria for obtaining NRC approval of spent fuel 
storage cask designs. The NRC subsequently issued a final rule on

[[Page 4616]]

December 22, 1994 (59 FR 65898), that approved the Standardized 
NUHOMS[reg] System (NUHOMS[reg]-24P and -52B) 
cask designs and added them to the list of NRC-approved cask designs in 
10 CFR 72.214 as CoC No. 1004. Amendments 3, 5, and 6, respectively, 
added the -61BT, -32PT, -24PHB designs to the Standardized 
NUHOMS[reg] System.

Discussion

    On April 18, 2006, and as supplemented on June 21, 2006, the 
certificate holder (Transnuclear, Inc.) submitted an application to the 
NRC to amend CoC No. 1004 to permit a Part 72 licensee to store 
Framatome-ANP, Version 9x9-2 fuel assemblies (FANP9 9x9-2) in the 
NUHOMS[reg]-61BT dry shielded canister. No other changes to 
the Standardized NUHOMS[reg] System design were requested in 
this application. The NRC staff performed a detailed safety evaluation 
of the proposed CoC amendment request and found that an acceptable 
safety margin is maintained. In addition, the NRC staff has determined 
that there continues to be reasonable assurance that public health and 
safety and the environment will be adequately protected.
    This direct final rule revises the Standardized NUHOMS[supreg] 
System cask design listing in 10 CFR 72.214 by adding Amendment No. 9 
to CoC No. 1004. The amendment consists of changes to the TS that will 
allow for the addition of the FANP9 9x9-2 fuel assemblies as approved 
contents for storage in the NUHOMS[supreg]-61BT dry shielded canister. 
The particular TS which are changed are identified in the NRC staff's 
SER for Amendment No. 9.
    The amended Standardized NUHOMS[supreg] System, when used under the 
conditions specified in the CoC, the TS, and NRC regulations, will meet 
the requirements of Part 72; thus, adequate protection of public health 
and safety will continue to be ensured.

Discussion of Amendments by Section

Section 72.214 List of Approved Spent Fuel Storage Casks

    Certificate No. 1004 is revised by adding the effective date of 
Amendment No. 9.

Procedural Background

    This rule is limited to the changes contained in Amendment 9 to CoC 
No. 1004 and does not include other aspects of the Standardized 
NUHOMS[supreg] 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 April 17, 2007. However, if the NRC receives significant 
adverse comments by March 5, 2007, 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 elsewhere in this Federal Register. 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, 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.

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[supreg] System design listed in Sec.  72.214 
(List of NRC-approved spent fuel storage cask designs). This action 
does not constitute the establishment of a standard that contains 
generally applicable requirements.

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 Category ``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 (AEA), or the provisions of Title 10 of the Code of 
Federal Regulations. Although an Agreement State may not adopt program 
elements reserved to 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.

Plain Language

    The Presidential Memorandum, ``Plain Language in Government 
Writing,'' published June 10, 1998 (63 FR 31883), directed that the 
Government's documents be in clear and accessible language. The NRC 
requests comments on this direct final rule specifically with respect 
to the clarity and effectiveness of the language used. Comments should 
be sent to the address listed under the heading ADDRESSES above.

Finding of No Significant Environmental Impact: Availability

    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 prepared an environmental assessment and, on the basis of this 
environmental assessment, has made a finding of no significant impact. 
This rule will amend the CoC for the Standardized NUHOMS[supreg] System 
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. The amendment will modify the CoC by revising TS 1.2.1 and 
1.2.14 to add the FANP9 9x9-2 fuel assemblies as approved contents for 
storage in the NUHOMS[supreg]-61BT dry shielded canister. The 
environmental assessment and finding of no significant impact on which 
this determination is based are available for inspection at the NRC 
Public Document Room, 11555 Rockville Pike, Rockville, MD. Single 
copies of the environmental assessment

[[Page 4617]]

and finding of no significant impact are available from Jayne M. 
McCausland, Office of Federal and State Materials and Environmental 
Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, telephone (301) 415-6219, e-mail jmm2@nrc.gov.

Paperwork Reduction Act Statement

    This direct final rule does not contain a new or amended 
information collection requirement 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, 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.

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, 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 part 72 that approved the Standardized 
NUHOMS[supreg] System design by adding it to the list of NRC-approved 
cask designs in 10 CFR 72.214. On April 18, 2006, and as supplemented 
on June 21, 2006, the certificate holder, Transnuclear, Inc., submitted 
an application to the NRC to amend CoC No. 1004 to permit a part 72 
licensee to use the FANP9 9x9-2 fuel assemblies in the NUHOMS[supreg]-
61BT dry shielded canister.
    The alternative to this action is to withhold approval of Amendment 
No. 9 and to require any part 72 licensee seeking to use Amendment No. 
9 to request an exemption from the requirements of 10 CFR 72.212 and 
72.214. Under this alternative, each interested 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, the direct final rule will have no adverse effect on 
public health and safety. 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 
thus, this action is recommended.

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 the licensing and operation of nuclear power 
plants, independent spent fuel storage facilities, and TN. The 
companies that own these plants 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).

Backfit Analysis

    The NRC has determined that the backfit rule (10 CFR 72.62) does 
not apply to this direct final rule because this amendment does not 
involve any provisions that would impose backfits as defined in 10 CFR 
Chapter I. Therefore, a backfit analysis is not required.

Congressional Review Act

    Under the Congressional Review Act of 1996, the NRC has determined 
that this action is not a major rule and has verified this 
determination with the Office of Information and Regulatory Affairs, 
Office of Management and Budget.

List of Subjects in 10 CFR Part 72

    Administrative practice and procedure, Criminal penalties, Manpower 
training programs, Nuclear materials, Occupational safety and health, 
Penalties, Radiation protection, Reporting and recordkeeping 
requirements, Security measures, Spent fuel, Whistleblowing.


0
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. 552 and 553; the NRC is adopting 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

0
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).


0
2. In Sec.  72.214, Certificate of Compliance 1004 is revised to read 
as follows:


Sec.  72.214  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.

[[Page 4618]]

    Amendment Number 8 Effective Date: December 5, 2005.
    Amendment Number 9 Effective Date: April 17, 2007.
    SAR Submitted by: Transnuclear, Inc.
    SAR Title: Final Safety Analysis Report for the Standardized 
NUHOMS[supreg] Horizontal Modular Storage System for Irradiated Nuclear 
Fuel.
    Docket Number: 72-1004.
    Certificate Expiration Date: January 23, 2015.
    Model Number: NUHOMS[supreg]-24P, -52B, -61BT, -32PT, -24PHB, and -
24PTH.
* * * * *

    Dated at Rockville, Maryland, this 19th day of January, 2007.

    For the Nuclear Regulatory Commission.
Luis A. Reyes,
Executive Director for Operations.
[FR Doc. E7-1644 Filed 1-31-07; 8:45 am]
BILLING CODE 7590-01-P