List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 6, 26310-26312 [E9-12618]

Download as PDF 26310 Federal Register / Vol. 74, No. 104 / Tuesday, June 2, 2009 / Proposed Rules (iii) (A) Pumps and valves, in facilities whose construction permit was issued before November 22, 1999, which are classified as ASME Code Class 1 must be designed and be provided with access to enable the performance of inservice testing of the pumps and valves for assessing operational readiness set forth in the editions and addenda of Section XI of the ASME Boiler and Pressure Vessel Code incorporated by reference in paragraph (b) of this section (or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, Revision 16; or Regulatory Guide 1.192 that are incorporated by reference in paragraph (b) of this section) applied to the construction of the particular pump or valve or the Summer 1973 Addenda, whichever is later. * * * * * (iv)(A) Pumps and valves, in facilities whose construction permit was issued before November 22, 1999, which are classified as ASME Code Class 2 and Class 3 must be designed and be provided with access to enable the performance of inservice testing of the pumps and valves for assessing operational readiness set forth in the editions and addenda of Section XI of the ASME Boiler and Pressure Vessel Code incorporated by reference in paragraph (b) of this section (or the optional ASME Code Cases listed in NRC Regulatory Guide 1.147, Revision 16, that are incorporated by reference in paragraph (b) of this section) applied to the construction of the particular pump or valve or the Summer 1973 Addenda, whichever is later. * * * * * (4) * * * (ii) Inservice tests to verify operational readiness of pumps and valves, whose function is required for safety, conducted during successive 120-month intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section 12 months before the start of the 120-month interval (or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, Revision 16; or Regulatory Guide 1.192 that are incorporated by reference in paragraph (b) of this section), subject to the conditions listed in paragraph (b) of this section. * * * * * (g) * * * (2) For a boiling or pressurized watercooled nuclear power facility whose construction permit was issued on or after January 1, 1971, but before July 1, 1974, components (including supports) VerDate Nov<24>2008 16:00 Jun 01, 2009 Jkt 217001 which are classified as ASME Code Class 1 and Class 2 must be designed and be provided with access to enable the performance of inservice examination of such components (including supports) and must meet the preservice examination requirements set forth in editions and addenda of Section XI of the ASME Boiler and Pressure Vessel Code incorporated by reference in paragraph (b) of this section (or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, Revision 16, that are incorporated by reference in paragraph (b) of this section) in effect 6 months before the date of issuance of the construction permit. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of this Code which are incorporated by reference in paragraph (b) of this section (or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, Revision 16, that are incorporated by reference in paragraph (b) of this section), subject to the applicable limitations and modifications. (3) * * * (i) Components (including supports) which are classified as ASME Code Class 1 must be designed and be provided with access to enable the performance of inservice examination of these components and must meet the preservice examination requirements set forth in the editions and addenda of Section XI of the ASME Boiler and Pressure Vessel Code incorporated by reference in paragraph (b) of this section (or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, Revision 16, that are incorporated by reference in paragraph (b) of this section) applied to the construction of the particular component. (ii) Components which are classified as ASME Code Class 2 and Class 3 and supports for components which are classified as ASME Code Class 1, Class 2, and Class 3 must be designed and be provided with access to enable the performance of inservice examination of these components and must meet the preservice examination requirements set forth in the editions and addenda of Section XI of the ASME Boiler and Pressure Vessel Code incorporated by reference in paragraph (b) of this section (or the optional ASME Code Cases listed in NRC Regulatory Guide 1.147, Revision 16, that are incorporated by reference in paragraph (b) of this section) applied to the construction of the particular component. * * * * * (4) * * * (i) Inservice examination of components and system pressure tests PO 00000 Frm 00009 Fmt 4702 Sfmt 4702 conducted during the initial 120-month inspection interval must comply with the requirements in the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section on the date 12 months before the date of issuance of the operating license (or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, Revision 16, that are incorporated by reference in paragraph (b) of this section, subject to the conditions listed in paragraph (b) of this section. (ii) Inservice examination of components and system pressure tests conducted during successive 120-month inspection intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section 12 months before the start of the 120-month inspection interval (or the optional ASME Code cases listed in NRC Regulatory Guide 1.147, Revision 16, that are incorporated by reference in paragraph (b) of this section), subject to the conditions listed in paragraph (b) of this section. * * * * * Dated at Rockville, Maryland, this 12th day of May 2009. For the Nuclear Regulatory Commission R.W. Borchardt, Executive Director for Operations. [FR Doc. E9–12751 Filed 6–1–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION 10 CFR Part 72 RIN 3150–AI60 [NRC–2009–0132] List of Approved Spent Fuel Storage Casks: HI–STORM 100 Revision 6 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 HI–STORM 100 dry storage cask system listing within the ‘‘List of Approved Spent Fuel Storage Casks’’ to include Amendment No. 6 to Certificate of Compliance (CoC) Number 1014. Amendment No. 6 would modify the CoC to add instrument tube tie rods used for pressurized water reactor 15x15 and 17x17 fuel lattices, for both intact and damaged fuel assemblies, to the approved contents of the MPC–24, MPC–24E, MPC–24EF, MPC–32, and E:\FR\FM\02JNP1.SGM 02JNP1 Federal Register / Vol. 74, No. 104 / Tuesday, June 2, 2009 / Proposed Rules MPC–32F models; and to correct legacy editorial issues in Appendices A and B Technical Specifications. DATES: Comments on the proposed rule must be received on or before July 2, 2009. You may submit comments by any one of the following methods. Comments submitted in writing or in electronic form will be made available for public inspection. 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. Federal e-Rulemaking Portal: Go to https://www.regulations.gov and search for documents filed under Docket ID [NRC–2009–0132]. Address questions about NRC dockets to Carol Gallagher, 301–492–3668; e-mail Carol.Gallagher@nrc.gov. Mail comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, Attn: Rulemakings and Adjudications Staff. E-mail comments to: Rulemaking.Comments@nrc.gov. 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 a.m. and 4:15 p.m. Federal workdays. (Telephone 301–415– 1677.) Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at 301–415–1101. You can access publicly available documents related to this document using the following methods: NRC’s Public Document Room (PDR): The public may examine and have copied for a fee publicly available documents at the NRC’s PDR, Public File Area O–1F21, 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 https://www.nrc.gov/ reading-rm/adams.html. From this page, 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 pdr.resource@nrc.gov. An electronic copy of the proposed Certificate of ADDRESSES: VerDate Nov<24>2008 16:00 Jun 01, 2009 Jkt 217001 Compliance (CoC) No. 1014, the proposed technical specifications (TS), and the preliminary safety evaluation report (SER) can be found under ADAMS Package Number ML090290140. The proposed CoC No. 1014, the proposed TS, the preliminary SER, 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 Jayne.McCausland@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 Jayne.McCausland@nrc.gov. 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 No. 6 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 August 17, 2009. However, if the NRC receives significant adverse comments on the direct final rule by July 2, 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 PO 00000 Frm 00010 Fmt 4702 Sfmt 4702 26311 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, 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. E:\FR\FM\02JNP1.SGM 02JNP1 26312 Federal Register / Vol. 74, No. 104 / Tuesday, June 2, 2009 / Proposed Rules 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. SAR Submitted by: Holtec International. SAR Title: Final Safety Analysis Report for the HI–STORM 100 Cask System. Docket Number: 72–1014. Certificate Expiration Date: June 1, 2020. Model Number: HI–STORM 100. * * * * * Dated at Rockville, Maryland, this 7th day of May 2009. For the Nuclear Regulatory Commission. R.W. Borchardt, Executive Director for Operations. [FR Doc. E9–12618 Filed 6–1–09; 8:45 am] BILLING CODE 7590–01–P VerDate Nov<24>2008 16:00 Jun 01, 2009 Jkt 217001 DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 39 [Docket No. FAA–2009–0465; Directorate Identifier 2007–NM–244–AD] RIN 2120–AA64 Airworthiness Directives; Airbus Model A310–203, –204, –221, –222, –304, –322, –324, and –325 Airplanes AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of proposed rulemaking (NPRM). SUMMARY: We propose to adopt a new airworthiness directive (AD) for the products listed above that would supersede an existing AD. This proposed AD results from mandatory continuing airworthiness information (MCAI) originated by an aviation authority of another country to identify and correct an unsafe condition on an aviation product. The MCAI describes the unsafe condition as: ´ ´ DGAC [Direction Generale de l’Aviation Civile] France issued AD F–2005–078 [which corresponds to FAA AD 2006–02–06] to require the modification (Airbus modification 13023), defined in Airbus SB [service bulletin] A310–53–2124, to increase the service life of junctions of center box upper frame bases to upper fuselage arches. This structural modification falls within the scope of the work related to the extension of the service life of A310 aircraft and widespread fatigue damage evaluations. The threshold timescales for accomplishment of the tasks as defined in SB A310–53–2124 were refined and reduced. * * * * * * * * The unsafe condition is fatigue cracking of the frame foot run-outs, which could lead to rupture of the frame foot and cracking in adjacent frames and skin, and which could result in reduced structural integrity of the fuselage. The proposed AD would require actions that are intended to address the unsafe condition described in the MCAI. DATES: We must receive comments on this proposed AD by July 2, 2009. ADDRESSES: You may send comments by any of the following methods: • Federal eRulemaking Portal: Go to https://www.regulations.gov. Follow the instructions for submitting comments. • Fax: (202) 493–2251. • Mail: U.S. Department of Transportation, Docket Operations, M– 30, West Building Ground Floor, Room W12–140, 1200 New Jersey Avenue, SE., Washington, DC 20590. • Hand Delivery: U.S. Department of Transportation, Docket Operations, M– PO 00000 Frm 00011 Fmt 4702 Sfmt 4702 30, West Building Ground Floor, Room W12–40, 1200 New Jersey Avenue, SE., Washington, DC, between 9 a.m. and 5 p.m., Monday through Friday, except Federal holidays. For service information identified in this proposed AD, contact Airbus SAS— EAW (Airworthiness Office), 1 Rond Point Maurice Bellonte, 31707 Blagnac Cedex, France; telephone +33 5 61 93 36 96; fax +33 5 61 93 44 51; e-mail: account.airworth-eas@airbus.com; Internet https://www.airbus.com. You may review copies of the referenced service information at the FAA, Transport Airplane Directorate, 1601 Lind Avenue, SW., Renton, Washington. For information on the availability of this material at the FAA, call 425–227– 1221 or 425–227–1152. Examining the AD Docket You may examine the AD docket on the Internet at https:// www.regulations.gov; or in person at the Docket Operations office between 9 a.m. and 5 p.m., Monday through Friday, except Federal holidays. The AD docket contains this proposed AD, the regulatory evaluation, any comments received, and other information. The street address for the Docket Operations office (telephone (800) 647–5527) is in the ADDRESSES section. Comments will be available in the AD docket shortly after receipt. FOR FURTHER INFORMATION CONTACT: Tom Stafford, Aerospace Engineer, International Branch, ANM–116, Transport Airplane Directorate, FAA, 1601 Lind Avenue, SW., Renton, Washington 98055–4056; telephone (425) 227–1622; fax (425) 227–1149. SUPPLEMENTARY INFORMATION: Comments Invited We invite you to send any written relevant data, views, or arguments about this proposed AD. Send your comments to an address listed under the ADDRESSES section. Include ‘‘Docket No. FAA–2009–0465; Directorate Identifier 2007–NM–244–AD’’ at the beginning of your comments. We specifically invite comments on the overall regulatory, economic, environmental, and energy aspects of this proposed AD. We will consider all comments received by the closing date and may amend this proposed AD based on those comments. We will post all comments we receive, without change, to https:// www.regulations.gov, including any personal information you provide. We will also post a report summarizing each substantive verbal contact we receive about this proposed AD. E:\FR\FM\02JNP1.SGM 02JNP1

Agencies

[Federal Register Volume 74, Number 104 (Tuesday, June 2, 2009)]
[Proposed Rules]
[Pages 26310-26312]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-12618]


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

NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

RIN 3150-AI60
[NRC-2009-0132]


List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 
6

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 HI-STORM 100 dry storage cask system listing within the 
``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 
6 to Certificate of Compliance (CoC) Number 1014. Amendment No. 6 would 
modify the CoC to add instrument tube tie rods used for pressurized 
water reactor 15x15 and 17x17 fuel lattices, for both intact and 
damaged fuel assemblies, to the approved contents of the MPC-24, MPC-
24E, MPC-24EF, MPC-32, and

[[Page 26311]]

MPC-32F models; and to correct legacy editorial issues in Appendices A 
and B Technical Specifications.

DATES: Comments on the proposed rule must be received on or before July 
2, 2009.

ADDRESSES: You may submit comments by any one of the following methods. 
Comments submitted in writing or in electronic form will be made 
available for public inspection. 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.
    Federal e-Rulemaking Portal: Go to https://www.regulations.gov and 
search for documents filed under Docket ID [NRC-2009-0132]. Address 
questions about NRC dockets to Carol Gallagher, 301-492-3668; e-mail 
Carol.Gallagher@nrc.gov.
    Mail comments to: Secretary, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, Attn: Rulemakings and Adjudications Staff.
    E-mail comments to: Rulemaking.Comments@nrc.gov. 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 a.m. and 4:15 p.m. Federal workdays. (Telephone 
301-415-1677.)
    Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at 
301-415-1101.
    You can access publicly available documents related to this 
document using the following methods:
    NRC's Public Document Room (PDR): The public may examine and have 
copied for a fee publicly available documents at the NRC's PDR, Public 
File Area O-1F21, 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 https://www.nrc.gov/reading-rm/adams.html. From this page, 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 
pdr.resource@nrc.gov. An electronic copy of the proposed Certificate of 
Compliance (CoC) No. 1014, the proposed technical specifications (TS), 
and the preliminary safety evaluation report (SER) can be found under 
ADAMS Package Number ML090290140.
    The proposed CoC No. 1014, the proposed TS, the preliminary SER, 
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 Jayne.McCausland@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 Jayne.McCausland@nrc.gov.

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 No. 6 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 August 17, 
2009. However, if the NRC receives significant adverse comments on the 
direct final rule by July 2, 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.

[[Page 26312]]

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


Sec.  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.
    SAR Submitted by: Holtec International.
    SAR Title: Final Safety Analysis Report for the HI-STORM 100 Cask 
System.
    Docket Number: 72-1014.
    Certificate Expiration Date: June 1, 2020.
    Model Number: HI-STORM 100.
* * * * *

    Dated at Rockville, Maryland, this 7th day of May 2009.

    For the Nuclear Regulatory Commission.
R.W. Borchardt,
Executive Director for Operations.
[FR Doc. E9-12618 Filed 6-1-09; 8:45 am]
BILLING CODE 7590-01-P
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