List of Approved Spent Fuel Storage Casks: NAC-MPC Revision 5, 26535-26538 [E7-9008]
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Federal Register / Vol. 72, No. 90 / Thursday, May 10, 2007 / Rules and Regulations
advanced knowledge in a field of
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provision of personal services by an
employee, including the rendering of
advice or consultation, which involves
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as defined in 5 CFR 2636.305(b)(1) or
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defined in 5 CFR 2636.305(b)(2).
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Note to § 7401.102(b): There is a special
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U.S.C. 203(d) and 205(e), respectively, for
certain representational activities otherwise
covered by the conflict of interest restrictions
on compensation and activities of employees
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in outside employment as defined in
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activities shall set forth, at a minimum:
(i) The name of the employer or
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(3) Upon a significant change in the
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(d) Standard for approval. Approval
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issuances examples of outside
employment that are permissible or
impermissible consistent with this part
and 5 CFR part 2635.
Dated: May 4, 2007.
Bentley M. Roberts, Jr.,
Clerk of the Board.
[FR Doc. E7–9035 Filed 5–9–07; 8:45 am]
BILLING CODE 7400–01–P
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 72
RIN 3150–AI13
List of Approved Spent Fuel Storage
Casks: NAC–MPC Revision 5
Nuclear Regulatory
Commission.
ACTION: Direct final rule.
AGENCY:
SUMMARY: The Nuclear Regulatory
Commission (NRC) is amending its
regulations revising the NAC
International, Inc., NAC-Multi-Purpose
Canister (MPC) system listing within the
‘‘List of Approved Spent Fuel Storage
Casks’’ to include Amendment No. 5 to
Certificate of Compliance (CoC) Number
1025. Amendment No. 5 will modify the
CoC by revising the Technical
Specifications (TS) to incorporate
changes to the reporting and monitoring
requirements to allow for visual
inspection of the air inlet and outlet
vents instead of thermal monitoring,
revising the TS to incorporate guidance
from NRC Interim Staff Guidance-22
and replace all references to backfilling
the cask with air to backfilling with
inert gas, revising the CoC description to
remove the requirement for tamperindicating devices on the Vertical
Concrete Casks, and including several
editorial changes to improve the clarity
of the documents associated with the
NAC–MPC system, under the general
provisions that govern licensing
requirements for the independent
storage of spent nuclear fuel, high level
radioactive waste, and reactor-related
greater than Class C waste.
DATES: The final rule is effective July 24,
2007, unless significant adverse
comments are received by June 11,
2007. A significant adverse comment is
a comment where the commenter
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26535
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–AI13) 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 https://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 https://
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 https://
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
https://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
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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. 1025, the revised TS, and the
preliminary safety evaluation report
(SER) for Amendment 5 can be found
under ADAMS Accession Nos.
ML063520431, ML063520434, and
ML063520440.
CoC No. 1025, the revised TS, the
preliminary SER for Amendment No. 5,
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:
cprice-sewell on PRODPC61 with RULES
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
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Storage Casks’’ containing procedures
and criteria for obtaining NRC approval
of spent fuel storage cask designs. The
NRC subsequently issued a final rule on
March 9, 2000 (65 FR 12444), that
approved the NAC–MPC cask design
and added it to the list of NRC-approved
cask designs in 10 CFR 72.214 as CoC
No. 1025.
Discussion
On July 17, 2006, and as
supplemented on September 13, 2006,
the certificate holder, NAC, submitted
an application to the NRC requesting
modifications to CoC No. 1025 by: (1)
Revising the TS to incorporate changes
to the reporting and monitoring
requirements to allow for visual
inspection of the air inlet and outlet
vents instead of thermal monitoring; (2)
revising the TS to incorporate guidance
from NRC Interim Staff Guidance (ISG)–
22 and replace all references to
backfilling the cask with air to
backfilling with inert gas; and (3)
revising the CoC description to remove
the requirement for tamper-indicating
devices on the Vertical Concrete Casks.
Also, the amendment includes several
editorial changes to improve the clarity
of the documents associated with the
NAC–MPC system. No other changes to
the NAC–MPC cask 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
NAC–MPC cask design listing in 10 CFR
72.214 by adding Amendment No. 5 to
CoC No. 1025. The amendment consists
of changes to the CoC by revising the TS
to incorporate changes to the reporting
and monitoring requirements to allow
for visual inspection of the air inlet and
outlet vents instead of thermal
monitoring, revising the TS to
incorporate guidance from NRC ISG–22
and replace all references to backfilling
the cask with air to backfilling with
inert gas, revising the CoC description to
remove the requirement for tamperindicating devices on the Vertical
Concrete Casks, and including several
editorial changes to improve the clarity
of the documents associated with the
NAC–MPC system. The particular TS
that are changed are identified in the
NRC staff’s SER for Amendment No. 5.
The amended NAC–MPC cask design,
when used under the conditions
specified in the CoC, the TS, and NRC
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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. 1025 is revised by
adding the effective date of Amendment
No. 5.
Procedural Background
This rule is limited to the changes
contained in Amendment 5 to CoC No.
1025 and does not include other aspects
of the NAC–MPC cask 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 July 24, 2007. However, if
the NRC receives significant adverse
comments by June 11, 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. For
example, a substantive response is
required when:
(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 rule, CoC, or TS.
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Federal Register / Vol. 72, No. 90 / Thursday, May 10, 2007 / Rules and Regulations
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 NAC–MPC cask
design listed in § 72.214 (List of NRCapproved 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.
cprice-sewell on PRODPC61 with RULES
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
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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 NAC–MPC cask design within
the list of approved spent fuel storage
casks that power reactor licensees can
use to store spent fuel at reactor sites
under a general license. The amendment
will incorporate changes to the
reporting and monitoring requirements
to allow for visual inspection of the air
inlet and outlet vents instead of thermal
monitoring, incorporate guidance from
NRC ISG–22 and replace all references
to backfilling the cask with air to
backfilling with inert gas, revise the CoC
description to remove the requirement
for tamper-indicating devices on the
Vertical Concrete Casks, and make
several editorial changes to improve the
clarity of the documents associated with
the NAC–MPC system. 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 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, 10 CFR
Part 72.
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
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26537
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 March 9, 2000 (65
FR 12444), the NRC issued an
amendment to part 72 that approved the
NAC–MPC cask design by adding it to
the list of NRC-approved cask designs in
10 CFR 72.214. On July 17, 2006, and
as supplemented on September 13,
2006, the certificate holder, NAC,
submitted an application to the NRC to
amend CoC No. 1025 to revise TS to
incorporate changes to the reporting and
monitoring requirements to allow for
visual inspection of the air inlet and
outlet vents instead of thermal
monitoring under the general license
provisions of 10 CFR part 72,
incorporate guidance from NRC ISG–22
and replace all references to backfilling
the cask with air to backfilling with
inert gas, revise the CoC description to
remove the requirement for tamperindicating devices on the Vertical
Concrete Casks, and include several
editorial changes to improve the clarity
of the documents associated with the
NAC–MPC system.
The alternative to this action is to
withhold approval of Amendment No. 5
and to require any part 72 licensee
seeking to use Amendment No. 5 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
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storage facilities, and NAC. 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.
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:
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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
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14:29 May 09, 2007
Jkt 211001
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 1025 is revised to read as
follows:
I
§ 72.214 List of approved spent fuel
storage casks.
*
*
*
*
*
Certificate Number: 1025.
Initial Certificate Effective Date: April
10, 2000.
Amendment Number 1 Effective Date:
November 13, 2001.
Amendment Number 2 Effective Date:
May 29, 2002.
Amendment Number 3 Effective Date:
October 1, 2003.
Amendment Number 4 Effective Date:
October 27, 2004.
Amendment Number 5 Effective Date:
July 24, 2007.
SAR Submitted by: NAC International,
Inc.
SAR Title: Final Safety Analysis Report
for the NAC Multi-Purpose Canister
System (NAC–MPC System).
Docket Number: 72–1025.
Certificate Expiration Date: April 10,
2020.
Model Number: NAC–MPC.
*
*
*
*
*
Dated at Rockville, Maryland, this 24th day
of April, 2007.
For the Nuclear Regulatory Commission.
Martin J. Virgilio,
Acting Executive Director for Operations.
[FR Doc. E7–9008 Filed 5–9–07; 8:45 am]
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DEPARTMENT OF TRANSPORTATION
Federal Aviation Administration
14 CFR Part 39
[Docket No. FAA–2007–27283; Directorate
Identifier 2007–NE–05–AD; Amendment 39–
15046; AD 2007–10–05]
RIN 2120–AA64
Airworthiness Directives; General
Electric Company (GE) GE90 Series
Turbofan Engines
Federal Aviation
Administration (FAA), Department of
Transportation (DOT).
ACTION: Final rule; request for
comments.
AGENCY:
SUMMARY: The FAA is adopting a new
airworthiness directive (AD) for GE
GE90–110B1, –113B, and –115B series
turbofan engines with certain Turbine
Center Frames (TCFs) installed. This AD
requires removing certain TCFs, listed
by part number (P/N) in this AD, from
service before exceeding 14,300 flight
cycles. This AD results from a report
that GE inadvertently omitted some TCF
P/Ns from the Airworthiness
Limitations Section (ALS) of the engine
manual. We are issuing this AD to
prevent structural failure of the TCF
with uncontained failure of low
pressure turbine (LPT) rotating parts.
Uncontained failure of the LPT rotating
parts could result in damage to the
airplane and possible loss of control of
the airplane.
DATES: This AD becomes effective June
14, 2007.
We must receive any comments on
this AD by July 9, 2007.
ADDRESSES: Use one of the following
addresses to comment on this AD:
• DOT Docket Web site: Go to
https://dms.dot.gov and follow the
instructions for sending your comments
electronically.
• Government-wide rulemaking Web
site: Go to https://www.regulations.gov
and follow the instructions for sending
your comments electronically.
• Mail: Docket Management Facility;
U.S. Department of Transportation, 400
Seventh Street, SW., Nassif Building,
Room PL–401, Washington, DC 20590–
0001.
• Fax: (202) 493–2251.
• Hand Delivery: Room PL–401 on
the plaza level of the Nassif Building,
400 Seventh Street, SW., Washington,
DC, between 9 a.m. and 5 p.m., Monday
through Friday, except Federal holidays.
FOR FURTHER INFORMATION CONTACT:
Antonio Cancelliere, Aerospace
Engineer, Engine Certification Office,
E:\FR\FM\10MYR1.SGM
10MYR1
Agencies
[Federal Register Volume 72, Number 90 (Thursday, May 10, 2007)]
[Rules and Regulations]
[Pages 26535-26538]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-9008]
=======================================================================
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NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
RIN 3150-AI13
List of Approved Spent Fuel Storage Casks: NAC-MPC Revision 5
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
-----------------------------------------------------------------------
SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its
regulations revising the NAC International, Inc., NAC-Multi-Purpose
Canister (MPC) system listing within the ``List of Approved Spent Fuel
Storage Casks'' to include Amendment No. 5 to Certificate of Compliance
(CoC) Number 1025. Amendment No. 5 will modify the CoC by revising the
Technical Specifications (TS) to incorporate changes to the reporting
and monitoring requirements to allow for visual inspection of the air
inlet and outlet vents instead of thermal monitoring, revising the TS
to incorporate guidance from NRC Interim Staff Guidance-22 and replace
all references to backfilling the cask with air to backfilling with
inert gas, revising the CoC description to remove the requirement for
tamper-indicating devices on the Vertical Concrete Casks, and including
several editorial changes to improve the clarity of the documents
associated with the NAC-MPC system, under the general provisions that
govern licensing requirements for the independent storage of spent
nuclear fuel, high level radioactive waste, and reactor-related greater
than Class C waste.
DATES: The final rule is effective July 24, 2007, unless significant
adverse comments are received by June 11, 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-AI13) 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 https://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 https://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 https://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 https://www.nrc.gov/NRC/ADAMS/. 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
[[Page 26536]]
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. 1025, the revised TS, and the preliminary safety evaluation
report (SER) for Amendment 5 can be found under ADAMS Accession Nos.
ML063520431, ML063520434, and ML063520440.
CoC No. 1025, the revised TS, the preliminary SER for Amendment No.
5, 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 March
9, 2000 (65 FR 12444), that approved the NAC-MPC cask design and added
it to the list of NRC-approved cask designs in 10 CFR 72.214 as CoC No.
1025.
Discussion
On July 17, 2006, and as supplemented on September 13, 2006, the
certificate holder, NAC, submitted an application to the NRC requesting
modifications to CoC No. 1025 by: (1) Revising the TS to incorporate
changes to the reporting and monitoring requirements to allow for
visual inspection of the air inlet and outlet vents instead of thermal
monitoring; (2) revising the TS to incorporate guidance from NRC
Interim Staff Guidance (ISG)-22 and replace all references to
backfilling the cask with air to backfilling with inert gas; and (3)
revising the CoC description to remove the requirement for tamper-
indicating devices on the Vertical Concrete Casks. Also, the amendment
includes several editorial changes to improve the clarity of the
documents associated with the NAC-MPC system. No other changes to the
NAC-MPC cask 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 NAC-MPC cask design listing in
10 CFR 72.214 by adding Amendment No. 5 to CoC No. 1025. The amendment
consists of changes to the CoC by revising the TS to incorporate
changes to the reporting and monitoring requirements to allow for
visual inspection of the air inlet and outlet vents instead of thermal
monitoring, revising the TS to incorporate guidance from NRC ISG-22 and
replace all references to backfilling the cask with air to backfilling
with inert gas, revising the CoC description to remove the requirement
for tamper-indicating devices on the Vertical Concrete Casks, and
including several editorial changes to improve the clarity of the
documents associated with the NAC-MPC system. The particular TS that
are changed are identified in the NRC staff's SER for Amendment No. 5.
The amended NAC-MPC cask design, 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. 1025 is revised by adding the effective date of
Amendment No. 5.
Procedural Background
This rule is limited to the changes contained in Amendment 5 to CoC
No. 1025 and does not include other aspects of the NAC-MPC cask 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 July 24, 2007. However,
if the NRC receives significant adverse comments by June 11, 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. For example, a substantive response is
required when:
(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 rule, CoC, or TS.
[[Page 26537]]
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 NAC-MPC cask 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 NAC-MPC cask design within the
list of approved spent fuel storage casks that power reactor licensees
can use to store spent fuel at reactor sites under a general license.
The amendment will incorporate changes to the reporting and monitoring
requirements to allow for visual inspection of the air inlet and outlet
vents instead of thermal monitoring, incorporate guidance from NRC ISG-
22 and replace all references to backfilling the cask with air to
backfilling with inert gas, revise the CoC description to remove the
requirement for tamper-indicating devices on the Vertical Concrete
Casks, and make several editorial changes to improve the clarity of the
documents associated with the NAC-MPC system. 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 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, 10 CFR Part 72.
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 March 9, 2000 (65 FR 12444), the NRC
issued an amendment to part 72 that approved the NAC-MPC cask design by
adding it to the list of NRC-approved cask designs in 10 CFR 72.214. On
July 17, 2006, and as supplemented on September 13, 2006, the
certificate holder, NAC, submitted an application to the NRC to amend
CoC No. 1025 to revise TS to incorporate changes to the reporting and
monitoring requirements to allow for visual inspection of the air inlet
and outlet vents instead of thermal monitoring under the general
license provisions of 10 CFR part 72, incorporate guidance from NRC
ISG-22 and replace all references to backfilling the cask with air to
backfilling with inert gas, revise the CoC description to remove the
requirement for tamper-indicating devices on the Vertical Concrete
Casks, and include several editorial changes to improve the clarity of
the documents associated with the NAC-MPC system.
The alternative to this action is to withhold approval of Amendment
No. 5 and to require any part 72 licensee seeking to use Amendment No.
5 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
[[Page 26538]]
storage facilities, and NAC. 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 1025 is revised to read
as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1025.
Initial Certificate Effective Date: April 10, 2000.
Amendment Number 1 Effective Date: November 13, 2001.
Amendment Number 2 Effective Date: May 29, 2002.
Amendment Number 3 Effective Date: October 1, 2003.
Amendment Number 4 Effective Date: October 27, 2004.
Amendment Number 5 Effective Date: July 24, 2007.
SAR Submitted by: NAC International, Inc.
SAR Title: Final Safety Analysis Report for the NAC Multi-Purpose
Canister System (NAC-MPC System).
Docket Number: 72-1025.
Certificate Expiration Date: April 10, 2020.
Model Number: NAC-MPC.
* * * * *
Dated at Rockville, Maryland, this 24th day of April, 2007.
For the Nuclear Regulatory Commission.
Martin J. Virgilio,
Acting Executive Director for Operations.
[FR Doc. E7-9008 Filed 5-9-07; 8:45 am]
BILLING CODE 7590-01-P