[Federal Register Volume 72, Number 21 (Thursday, February 1, 2007)]
[Rules and Regulations]
[Pages 4615-4618]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E7-1644]
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Rules and Regulations
Federal Register
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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.
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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the rule is withdrawn, timely notice will be published in the Federal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: [email protected]. 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
[email protected]. 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 [email protected]. 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 [email protected].
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 [email protected].
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 [email protected].
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]
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