List of Approved Spent Fuel Storage Casks: HI-STORM 100, Revision 8, 9515-9518 [2012-3678]
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9515
Rules and Regulations
Federal Register
Vol. 77, No. 33
Friday, February 17, 2012
This section of the FEDERAL REGISTER
contains regulatory documents having general
applicability and legal effect, most of which
are keyed to and codified in the Code of
Federal Regulations, which is published under
50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by
the Superintendent of Documents. Prices of
new books are listed in the first FEDERAL
REGISTER issue of each week.
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 72
[NRC–2011–0221]
RIN 3150–AJ05
List of Approved Spent Fuel Storage
Casks: HI–STORM 100, Revision 8
Nuclear Regulatory
Commission.
ACTION: Direct final rule.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC or the Commission)
is amending its spent fuel storage
regulations by revising the Holtec
International HI–STORM 100 dry cask
storage system listing within the ‘‘List of
Approved Spent Fuel Storage Casks’’ to
include Amendment No. 8 to Certificate
of Compliance (CoC) No. 1014.
Amendment No. 8 adds a new
multipurpose canister (MPC)–68M to
the approved models currently included
in CoC No. 1014 with two new boiling
water reactor fuel assembly/array
classes, and a new pressurized water
reactor fuel assembly/class to CoC No.
1014 for loading into the MPC–32. In
addition, the amendment makes several
other changes as described under the
‘‘Discussion’’ heading in the
SUPPLEMENTARY INFORMATION section of
this document.
DATES: The final rule is effective May 2,
2012, unless significant adverse
comments are received by March 19,
2012. 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rule is withdrawn, timely notice will be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.
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SUMMARY:
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You can access publicly
available documents related to this
document using the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for documents filed under Docket ID
NRC–2011–0221. Address questions
about NRC dockets to Carol Gallagher,
telephone: 301–492–3668; email:
Carol.Gallagher@nrc.gov.
• NRC’s Public Document Room
(PDR): The public may examine and
have copied, for a fee, publicly available
documents at the NRC’s PDR, Room O–
1F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland
20852.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): Publicly available documents
created or received at the NRC are
available online in the NRC Library 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 email to
pdr.resource@nrc.gov. An electronic
copy of the proposed CoC, Technical
Specifications (TSs), and preliminary
safety evaluation report (SER) can be
found under ADAMS Package
Accession Number ML112160574.
FOR FURTHER INFORMATION CONTACT:
Gregory Trussell, Office of Federal and
State Materials and Environmental
Management Programs, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–415–
6445, email: Gregory.Trussell@nrc.gov.
SUPPLEMENTARY INFORMATION:
ADDRESSES:
Background
Section 218(a) of the Nuclear Waste
Policy Act (NWPA) of 1982, as
amended, requires that ‘‘the Secretary
[of the Department of Energy] shall
establish a demonstration program, in
cooperation with the private sector, for
the dry storage of spent nuclear fuel at
civilian nuclear power reactor sites,
with the objective of establishing one or
more technologies that the [U.S. 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
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for additional site-specific approvals by
the Commission.’’ Section 133 of the
NWPA states, in part, that [the
Commission] shall, by rule, establish
procedures for the licensing of any
technology approved by the
Commission under Section 219(a) for
use at the site of any civilian nuclear
power reactor.’’
To implement this mandate, the
Commission approved dry storage of
spent nuclear fuel in NRC-approved
casks under a general license by
publishing a final rule in Title 10 of the
Code of Federal Regulations (10 CFR)
Part 72, which added a new Subpart K
within 10 CFR Part 72, entitled ‘‘General
License for Storage of Spent Fuel at
Power Reactor Sites’’ (55 FR 29181; July
18, 1990). This rule also established a
new Subpart L within 10 CFR Part 72,
entitled ‘‘Approval of Spent Fuel
Storage Casks,’’ which contains
procedures and criteria for obtaining
NRC approval of spent fuel storage cask
designs. The NRC subsequently issued a
final rule on May 1, 2000 (65 FR 25241),
that approved the Holtec International
cask design and added it to the list of
NRC-approved cask designs in 10 CFR
72.214 as CoC No. 1014.
Discussion
On November 28, 2009, and as
supplemented on November 4 and
December 14, 2010, and February 25
and July 8, 2011, Holtec International,
the holder of CoC No. 1014, submitted
a certificate amendment request to the
NRC requesting an amendment to CoC
No. 1014. Specifically, Holtec
International requested changes to add a
new MPC–68M to the approved models
currently included in CoC No. 1014
with two new boiling water reactor fuel
assembly/array classes, and a new
pressurized water reactor fuel assembly/
class to CoC No. 1014 for loading into
the MPC–32. In addition, the
amendment would change 1) Condition
5 of CoC No. 1014 to add ‘‘if applicable’’
after the reference to Section 3.5 of
Appendix B, ‘‘Cask Transfer Facility
(CTF)’’ to clarify that the CTF is an
optional facility; 2) Appendix A, TS 1.1,
to modify the CTF definition to clarify
that it could be used in lieu of 10 CFR
Part 50 controlled structures for cask
transfer evolutions; and 3) Table 3–1,
MPC Cavity Drying Limits, to include
the previously approved, but omitted
table to eliminate inconsistencies
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Federal Register / Vol. 77, No. 33 / Friday, February 17, 2012 / Rules and Regulations
between Table 3–1 and TS 3.1.1,
Limiting Condition for Operation.
As documented in the SER, 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 will be adequately protected.
This direct final rule revises the HI–
STORM 100 listing in 10 CFR 72.214 by
adding Amendment No. 8 to CoC No.
1014. The amendment consists of the
changes previously described, as set
forth in the revised CoC and TSs. The
revised TSs are identified in the SER.
The amended HI–STORM 100 cask
design, when used under the conditions
specified in the CoC, the TSs, and the
NRC’s regulations, will meet the
requirements of 10 CFR Part 72; thus,
adequate protection of public health and
safety will continue to be ensured.
When this direct final rule becomes
effective, persons who hold a general
license under 10 CFR 72.210 may load
spent nuclear fuel into HI–STORM 100
casks that meet the criteria of
Amendment No. 8 to CoC No. 1014
under 10 CFR 72.212.
Discussion of Amendments by Section
Section 72.214 List of approved spent
fuel storage casks
The CoC No. 1014 is revised by
adding the effective date of Amendment
Number 8.
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Procedural Background
This rule is limited to the changes
contained in Amendment No. 8 to CoC
No. 1014 and does not include other
aspects of the HI–STORM 100 dry
storage cask system. 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 May 2, 2012.
However, if the NRC receives significant
adverse comments on this direct final
rule by March 19, 2012, 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 issue of the Federal
Register. Absent significant
modifications to the proposed revisions
requiring republication, the NRC will
not initiate a second comment period on
this action.
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A significant adverse comment is a
comment where the commenter
explains why the rule would be
inappropriate, including challenges to
the rule’s underlying premise or
approach, or would be ineffective or
unacceptable without a change. A
comment is adverse and significant if:
(1) The comment opposes the rule and
provides a reason sufficient to require a
substantive response in a notice-andcomment process. For example, a
substantive response is required when:
(a) The comment causes the NRC staff
to reevaluate (or reconsider) its position
or conduct additional analysis;
(b) The comment raises an issue
serious enough to warrant a substantive
response to clarify or complete the
record; or
(c) The comment raises a relevant
issue that was not previously addressed
or considered by the NRC staff.
(2) The comment proposes a change
or an addition to the rule, and it is
apparent that the rule would be
ineffective or unacceptable without
incorporation of the change or addition.
(3) The comment causes the NRC staff
to make a change (other than editorial)
to the rule, CoC, or TSs.
For detailed instructions on filing
comments, please see the companion
proposed rule published elsewhere in
this issue of the Federal Register.
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 Holtec International
HI–STORM 100 System cask design
listed in § 72.214 (List of Approved
Spent Fuel Storage Casks). 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, or the provisions of
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10 CFR. Although an Agreement State
may not adopt program elements
reserved to the NRC, it may wish to
inform its licensees of certain
requirements via a mechanism that is
consistent with the particular State’s
administrative procedure laws but does
not confer regulatory authority on the
State.
Plain Writing
The Plain Writing Act of 2010 (Pub.
L. 111–274) requires Federal agencies to
write documents in a clear, concise,
well-organized manner that also follows
other best practices appropriate to the
subject or field and the intended
audience. The NRC has attempted to use
plain language in promulgating this rule
consistent with the Federal Plain
Writing Act guidelines.
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 amends the CoC for
the Holtec International HI–STORM 100
System 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. Amendment No. 8 adds
a new multipurpose canister (MPC)—
68M to the approved models currently
included in CoC No. 1014 with two new
boiling water reactor fuel assembly/
array classes, and a new pressurized
water reactor fuel assembly/class to CoC
No. 1014 for loading into the MPC–32.
In addition, the amendment changes: (1)
Condition 5 of CoC No. 1014 to add ‘‘if
applicable’’ after the reference to
Section 3.5 of Appendix B, ‘‘Cask
Transfer Facility (CTF)’’ to clarify that
the CTF is an optional facility; (2)
Appendix A, TS 1.1, to modify the CTF
definition to clarify that it could be used
in lieu of 10 CFR part 50 controlled
structures for cask transfer evolutions;
and (3) Table 3–1, MPC Cavity Drying
Limits, to include the previously
approved, but omitted, table to
eliminate inconsistencies between Table
3–1 and TS 3.1.1, Limiting Condition for
Operation.
The environmental assessment and
finding of no significant impact on
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which this determination is based are
available for inspection at the NRC PDR,
Room O–1F21, One White Flint North,
11555 Rockville Pike, Rockville,
Maryland 20852. Single copies of the
environmental assessment and finding
of no significant impact are available
from Gregory Trussell, Office of Federal
and State Materials and Environmental
Management Programs, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–415–
6445, email: Gregory.Trussell@nrc.gov.
Paperwork Reduction Act Statement
This rule does not contain any
information collection requirements
and, therefore, is not subject to the
Paperwork Reduction Act of 1995 (44
U.S.C. 3501 et seq.). Existing
requirements were approved by the
Office of Management and Budget
(OMB), Approval Number 3150–0132.
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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, the spent
fuel is stored under the conditions
specified in the cask’s CoC, and the
conditions of the general license are
met. A list of NRC-approved cask
designs is contained in 10 CFR 72.214.
On May 1, 2000 (65 FR 25241), the NRC
issued an amendment to 10 CFR part 72
that approved the HI–STORM 100 cask
design by adding it to the list of NRCapproved cask designs in 10 CFR
72.214.
On November 28, 2009, and as
supplemented on November 4 and
December 14, 2010, and February 25
and July 8, 2011, Holtec International,
the holder of CoC No. 1014, submitted
a certificate amendment request to the
NRC requesting an amendment to CoC
No. 1014. Specifically, Holtec
International requested changes to add a
new multipurpose canister (MPC)–68M
to the approved models currently
included in CoC No. 1014 with two new
boiling water reactor fuel assembly/
array classes, and a new pressurized
water reactor fuel assembly/class to CoC
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No. 1014 for loading into the MPC–32.
In addition, the amendment would
change: (1) Condition 5 of CoC No. 1014
to add ‘‘if applicable’’ after the reference
to Section 3.5 of Appendix B, ‘‘Cask
Transfer Facility (CTF)’’ to clarify that
the CTF is an optional facility; (2)
Appendix A, TS 1.1, to modify the CTF
definition to clarify that it could be used
in lieu of 10 CFR part 50 controlled
structures for cask transfer evolutions;
and (3) Table 3–1, MPC Cavity Drying
Limits, to include the previously
approved, but omitted table to eliminate
inconsistencies between Table 3–1 and
TS 3.1.1, Limiting Condition for
Operation.
The alternative to this action is to
withhold approval of Amendment No. 8
and to require any 10 CFR part 72
general licensee seeking to load spent
nuclear fuel into HI–STORM 100 casks
under the changes described in
Amendment No. 8 to request an
exemption from the requirements of 10
CFR 72.212 and 72.214. Under this
alternative, each interested 10 CFR part
72 licensee would have to prepare, and
the NRC would have to review, a
separate exemption request, thereby
increasing the administrative burden
upon the NRC and the costs to each
licensee.
Approval of the direct final rule is
consistent with previous NRC actions.
Further, as documented in the SER and
the environmental assessment, the
direct final rule will have no adverse
effect on public health and safety or the
environment. This direct final rule has
no significant identifiable impact or
benefit on other Government agencies.
Based on this regulatory analysis, the
NRC concludes that the requirements of
the direct final rule are commensurate
with the NRC’s responsibilities for
public health and safety and the
common defense and security. No other
available alternative is believed to be as
satisfactory, and 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
nuclear power plant licensees and
Holtec International. These entities do
not fall within the scope of the
definition of ‘‘small entities’’ set forth in
the Regulatory Flexibility Act or the size
standards established by the NRC (10
CFR 2.810).
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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, OMB.
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.
For the reasons set out in the
preamble and under the authority of the
Atomic Energy Act of 1954, as amended;
the Energy Reorganization Act of 1974,
as amended; the Nuclear Waste Policy
Act of 1982, as amended; and 5 U.S.C.
552 and 553; the NRC is adopting the
following amendments to 10 CFR part
72.
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.
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);
Energy Policy Act of 2005, Pub. L. No. 109–
58, 119 Stat. 549 (2005).
Section 72.44(g) also issued under secs.
142(b) and 148(c), (d), Pub. L. 100–203, 101
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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:
■
*
*
*
*
*
Certificate No.: 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.
Amendment Number 7 Effective Date:
December 28, 2009.
Amendment Number 8 Effective Date:
May 2, 2012.
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: May 31,
2020.
Model Number: HI–STORM 100.
*
*
*
*
*
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Dated at Rockville, Maryland, this 25th day
of January, 2012.
For the Nuclear Regulatory Commission.
R.W. Borchardt,
Executive Director for Operations.
BILLING CODE 7590–01–P
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Federal Aviation Administration
14 CFR Part 39
[Docket No. FAA–2011–0725; Directorate
Identifier 2011–NM–065–AD; Amendment
39–16943; AD 2012–03–02]
RIN 2120–AA64
Airworthiness Directives; The Boeing
Company Airplanes
Federal Aviation
Administration (FAA), DOT.
ACTION: Final rule.
AGENCY:
We are adopting a new
airworthiness directive (AD) for certain
The Boeing Company Model 767–200,
–300, and –300F series airplanes. This
AD was prompted by reports of loss of
avionics cooling due to an unserviceable
relay installed on a panel as part of the
cabin air conditioning and temperature
control system (CACTCS). This AD
requires doing certain wiring changes,
installing a new relay and necessary
wiring in the CACTCS, and performing
an operational test of the cooling pack
system. We are issuing this AD to
prevent loss of electrical equipment bay
cooling and the overheating of flight
deck instruments, which would result
in the eventual loss of primary flight
displays, an unusually high pilot
workload, and depressurization of the
cabin.
DATES: This AD is effective March 23,
2012.
The Director of the Federal Register
approved the incorporation by reference
of certain publications listed in the AD
as of March 23, 2012.
ADDRESSES: For service information
identified in this AD, contact Boeing
Commercial Airplanes, Attention: Data
& Services Management, P.O. Box 3707,
MC 2H–65, Seattle, Washington 98124–
2207; telephone 206–544–5000,
extension 1; fax 206–766–5680; email:
me.boecom@boeing.com; Internet
https://www.myboeingfleet.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.
SUMMARY:
§ 72.214 List of approved spent fuel
storage casks.
[FR Doc. 2012–3678 Filed 2–16–12; 8:45 am]
DEPARTMENT OF TRANSPORTATION
Examining the AD Docket
You may examine the AD docket on
the Internet at https://
www.regulations.gov; or in person at the
Docket Management Facility between
9 a.m. and 5 p.m., Monday through
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Friday, except Federal holidays. The AD
docket contains this AD, the regulatory
evaluation, any comments received, and
other information. The address for the
Docket Office (phone: 800–647–5527) is
Document Management Facility, U.S.
Department of Transportation, Docket
Operations, M–30, West Building
Ground Floor, Room W12–140, 1200
New Jersey Avenue SE., Washington,
DC 20590.
FOR FURTHER INFORMATION CONTACT: Ana
Martinez Hueto, Aerospace Engineer,
Cabin Safety and Environmental
Systems Branch, ANM–150S, FAA,
Seattle Aircraft Certification Office,
1601 Lind Avenue SW., Renton, WA
98057–3356; phone: 425–917–6592; fax:
425–917–6590; email:
ana.m.hueto@faa.gov.
SUPPLEMENTARY INFORMATION:
Discussion
We issued a notice of proposed
rulemaking (NPRM) to amend 14 CFR
part 39 to include an AD that would
apply to the specified products. That
NPRM published in the Federal
Register on August 24, 2011 (76 FR
52899). That NPRM proposed to require
doing certain wiring changes, installing
a new relay and necessary wiring in the
CACTCS, and performing an operational
test of the cooling pack system.
Comments
We gave the public the opportunity to
participate in developing this AD. We
have considered the comments received.
Boeing supports the NPRM (76 FR
52899, August 24, 2011). American
Airlines stated that it is not affected by
the NPRM.
Conclusion
We reviewed the relevant data,
considered the comments received, and
determined that air safety and the
public interest require adopting the AD
as proposed except for minor editorial
changes. We have determined that these
minor changes:
• Are consistent with the intent that
was proposed in the NPRM (76 FR
52899, August 24, 2011) for correcting
the unsafe condition; and
• Do not add any additional burden
upon the public than was already
proposed in the NPRM (76 FR 52899,
August 24, 2011).
Costs of Compliance
We estimate that this AD affects 35
airplanes of U.S. registry.
We estimate the following costs to
comply with this AD:
E:\FR\FM\17FER1.SGM
17FER1
Agencies
[Federal Register Volume 77, Number 33 (Friday, February 17, 2012)]
[Rules and Regulations]
[Pages 9515-9518]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-3678]
========================================================================
Rules and Regulations
Federal Register
________________________________________________________________________
This section of the FEDERAL REGISTER contains regulatory documents
having general applicability and legal effect, most of which are keyed
to and codified in the Code of Federal Regulations, which is published
under 50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by the Superintendent of Documents.
Prices of new books are listed in the first FEDERAL REGISTER issue of each
week.
========================================================================
Federal Register / Vol. 77, No. 33 / Friday, February 17, 2012 /
Rules and Regulations
[[Page 9515]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2011-0221]
RIN 3150-AJ05
List of Approved Spent Fuel Storage Casks: HI-STORM 100, Revision
8
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the Commission)
is amending its spent fuel storage regulations by revising the Holtec
International HI-STORM 100 dry cask storage system listing within the
``List of Approved Spent Fuel Storage Casks'' to include Amendment No.
8 to Certificate of Compliance (CoC) No. 1014. Amendment No. 8 adds a
new multipurpose canister (MPC)-68M to the approved models currently
included in CoC No. 1014 with two new boiling water reactor fuel
assembly/array classes, and a new pressurized water reactor fuel
assembly/class to CoC No. 1014 for loading into the MPC-32. In
addition, the amendment makes several other changes as described under
the ``Discussion'' heading in the SUPPLEMENTARY INFORMATION section of
this document.
DATES: The final rule is effective May 2, 2012, unless significant
adverse comments are received by March 19, 2012. 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 can access publicly available documents related to this
document using the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for documents filed under Docket ID NRC-
2011-0221. Address questions about NRC dockets to Carol Gallagher,
telephone: 301-492-3668; email: Carol.Gallagher@nrc.gov.
NRC's Public Document Room (PDR): The public may examine
and have copied, for a fee, publicly available documents at the NRC's
PDR, Room O-1F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland 20852.
NRC's Agencywide Documents Access and Management System
(ADAMS): Publicly available documents created or received at the NRC
are available online in the NRC Library 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 email to pdr.resource@nrc.gov. An
electronic copy of the proposed CoC, Technical Specifications (TSs),
and preliminary safety evaluation report (SER) can be found under ADAMS
Package Accession Number ML112160574.
FOR FURTHER INFORMATION CONTACT: Gregory Trussell, Office of Federal
and State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone: 301-415-
6445, email: Gregory.Trussell@nrc.gov.
SUPPLEMENTARY INFORMATION:
Background
Section 218(a) of the Nuclear Waste Policy Act (NWPA) of 1982, as
amended, requires that ``the Secretary [of the Department of Energy]
shall establish a demonstration program, in cooperation with the
private sector, for the dry storage of spent nuclear fuel at civilian
nuclear power reactor sites, with the objective of establishing one or
more technologies that the [U.S. 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 [the Commission] shall, by rule, establish
procedures for the licensing of any technology approved by the
Commission under Section 219(a) for use at the site of any civilian
nuclear power reactor.''
To implement this mandate, the Commission approved dry storage of
spent nuclear fuel in NRC-approved casks under a general license by
publishing a final rule in Title 10 of the Code of Federal Regulations
(10 CFR) Part 72, which added a new Subpart K within 10 CFR Part 72,
entitled ``General License for Storage of Spent Fuel at Power Reactor
Sites'' (55 FR 29181; July 18, 1990). This rule also established a new
Subpart L within 10 CFR Part 72, entitled ``Approval of Spent Fuel
Storage Casks,'' which contains procedures and criteria for obtaining
NRC approval of spent fuel storage cask designs. The NRC subsequently
issued a final rule on May 1, 2000 (65 FR 25241), that approved the
Holtec International cask design and added it to the list of NRC-
approved cask designs in 10 CFR 72.214 as CoC No. 1014.
Discussion
On November 28, 2009, and as supplemented on November 4 and
December 14, 2010, and February 25 and July 8, 2011, Holtec
International, the holder of CoC No. 1014, submitted a certificate
amendment request to the NRC requesting an amendment to CoC No. 1014.
Specifically, Holtec International requested changes to add a new MPC-
68M to the approved models currently included in CoC No. 1014 with two
new boiling water reactor fuel assembly/array classes, and a new
pressurized water reactor fuel assembly/class to CoC No. 1014 for
loading into the MPC-32. In addition, the amendment would change 1)
Condition 5 of CoC No. 1014 to add ``if applicable'' after the
reference to Section 3.5 of Appendix B, ``Cask Transfer Facility
(CTF)'' to clarify that the CTF is an optional facility; 2) Appendix A,
TS 1.1, to modify the CTF definition to clarify that it could be used
in lieu of 10 CFR Part 50 controlled structures for cask transfer
evolutions; and 3) Table 3-1, MPC Cavity Drying Limits, to include the
previously approved, but omitted table to eliminate inconsistencies
[[Page 9516]]
between Table 3-1 and TS 3.1.1, Limiting Condition for Operation.
As documented in the SER, 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 will be adequately protected.
This direct final rule revises the HI-STORM 100 listing in 10 CFR
72.214 by adding Amendment No. 8 to CoC No. 1014. The amendment
consists of the changes previously described, as set forth in the
revised CoC and TSs. The revised TSs are identified in the SER.
The amended HI-STORM 100 cask design, when used under the
conditions specified in the CoC, the TSs, and the NRC's regulations,
will meet the requirements of 10 CFR Part 72; thus, adequate protection
of public health and safety will continue to be ensured. When this
direct final rule becomes effective, persons who hold a general license
under 10 CFR 72.210 may load spent nuclear fuel into HI-STORM 100 casks
that meet the criteria of Amendment No. 8 to CoC No. 1014 under 10 CFR
72.212.
Discussion of Amendments by Section
Section 72.214 List of approved spent fuel storage casks
The CoC No. 1014 is revised by adding the effective date of
Amendment Number 8.
Procedural Background
This rule is limited to the changes contained in Amendment No. 8 to
CoC No. 1014 and does not include other aspects of the HI-STORM 100 dry
storage cask system. 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 May 2, 2012. However, if the NRC receives significant
adverse comments on this direct final rule by March 19, 2012, 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
issue of the Federal Register. Absent significant modifications to the
proposed revisions requiring republication, the NRC will not initiate a
second comment period on this action.
A significant adverse comment is a comment where the commenter
explains why the rule would be inappropriate, including challenges to
the rule's underlying premise or approach, or would be ineffective or
unacceptable without a change. A comment is adverse and significant if:
(1) The comment opposes the rule and provides a reason sufficient
to require a substantive response in a notice-and-comment process. For
example, a substantive response is required when:
(a) The comment causes the NRC staff to reevaluate (or reconsider)
its position or conduct additional analysis;
(b) The comment raises an issue serious enough to warrant a
substantive response to clarify or complete the record; or
(c) The comment raises a relevant issue that was not previously
addressed or considered by the NRC staff.
(2) The comment proposes a change or an addition to the rule, and
it is apparent that the rule would be ineffective or unacceptable
without incorporation of the change or addition.
(3) The comment causes the NRC staff to make a change (other than
editorial) to the rule, CoC, or TSs.
For detailed instructions on filing comments, please see the
companion proposed rule published elsewhere in this issue of the
Federal Register.
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 Holtec International HI-STORM 100 System cask design listed in
Sec. 72.214 (List of Approved Spent Fuel Storage Casks). 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, or the provisions of 10 CFR. Although an Agreement
State may not adopt program elements reserved to the NRC, it may wish
to inform its licensees of certain requirements via a mechanism that is
consistent with the particular State's administrative procedure laws
but does not confer regulatory authority on the State.
Plain Writing
The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal
agencies to write documents in a clear, concise, well-organized manner
that also follows other best practices appropriate to the subject or
field and the intended audience. The NRC has attempted to use plain
language in promulgating this rule consistent with the Federal Plain
Writing Act guidelines.
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 amends the CoC for the Holtec International HI-STORM 100
System 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. Amendment No. 8 adds a new multipurpose
canister (MPC)--68M to the approved models currently included in CoC
No. 1014 with two new boiling water reactor fuel assembly/array
classes, and a new pressurized water reactor fuel assembly/class to CoC
No. 1014 for loading into the MPC-32. In addition, the amendment
changes: (1) Condition 5 of CoC No. 1014 to add ``if applicable'' after
the reference to Section 3.5 of Appendix B, ``Cask Transfer Facility
(CTF)'' to clarify that the CTF is an optional facility; (2) Appendix
A, TS 1.1, to modify the CTF definition to clarify that it could be
used in lieu of 10 CFR part 50 controlled structures for cask transfer
evolutions; and (3) Table 3-1, MPC Cavity Drying Limits, to include the
previously approved, but omitted, table to eliminate inconsistencies
between Table 3-1 and TS 3.1.1, Limiting Condition for Operation.
The environmental assessment and finding of no significant impact
on
[[Page 9517]]
which this determination is based are available for inspection at the
NRC PDR, Room O-1F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland 20852. Single copies of the environmental
assessment and finding of no significant impact are available from
Gregory Trussell, Office of Federal and State Materials and
Environmental Management Programs, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, telephone: 301-415-6445, email:
Gregory.Trussell@nrc.gov.
Paperwork Reduction Act Statement
This rule does not contain any information collection requirements
and, therefore, is not subject to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et seq.). Existing requirements were approved by the
Office of Management and Budget (OMB), Approval Number 3150-0132.
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to
respond to a request for information or an information collection
requirement unless the requesting document displays a currently valid
OMB control number.
Regulatory Analysis
On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10
CFR part 72 to provide for the storage of spent nuclear fuel under a
general license in cask designs approved by the NRC. Any nuclear power
reactor licensee can use NRC-approved cask designs to store spent
nuclear fuel if it notifies the NRC in advance, the spent fuel is
stored under the conditions specified in the cask's CoC, and the
conditions of the general license are met. A list of NRC-approved cask
designs is contained in 10 CFR 72.214. On May 1, 2000 (65 FR 25241),
the NRC issued an amendment to 10 CFR part 72 that approved the HI-
STORM 100 cask design by adding it to the list of NRC-approved cask
designs in 10 CFR 72.214.
On November 28, 2009, and as supplemented on November 4 and
December 14, 2010, and February 25 and July 8, 2011, Holtec
International, the holder of CoC No. 1014, submitted a certificate
amendment request to the NRC requesting an amendment to CoC No. 1014.
Specifically, Holtec International requested changes to add a new
multipurpose canister (MPC)-68M to the approved models currently
included in CoC No. 1014 with two new boiling water reactor fuel
assembly/array classes, and a new pressurized water reactor fuel
assembly/class to CoC No. 1014 for loading into the MPC-32. In
addition, the amendment would change: (1) Condition 5 of CoC No. 1014
to add ``if applicable'' after the reference to Section 3.5 of Appendix
B, ``Cask Transfer Facility (CTF)'' to clarify that the CTF is an
optional facility; (2) Appendix A, TS 1.1, to modify the CTF definition
to clarify that it could be used in lieu of 10 CFR part 50 controlled
structures for cask transfer evolutions; and (3) Table 3-1, MPC Cavity
Drying Limits, to include the previously approved, but omitted table to
eliminate inconsistencies between Table 3-1 and TS 3.1.1, Limiting
Condition for Operation.
The alternative to this action is to withhold approval of Amendment
No. 8 and to require any 10 CFR part 72 general licensee seeking to
load spent nuclear fuel into HI-STORM 100 casks under the changes
described in Amendment No. 8 to request an exemption from the
requirements of 10 CFR 72.212 and 72.214. Under this alternative, each
interested 10 CFR part 72 licensee would have to prepare, and the NRC
would have to review, a separate exemption request, thereby increasing
the administrative burden upon the NRC and the costs to each licensee.
Approval of the direct final rule is consistent with previous NRC
actions. Further, as documented in the SER and the environmental
assessment, the direct final rule will have no adverse effect on public
health and safety or the environment. This direct final rule has no
significant identifiable impact or benefit on other Government
agencies. Based on this regulatory analysis, the NRC concludes that the
requirements of the direct final rule are commensurate with the NRC's
responsibilities for public health and safety and the common defense
and security. No other available alternative is believed to be as
satisfactory, and 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 nuclear power plant licensees and Holtec
International. These entities do not fall within the scope of the
definition of ``small entities'' set forth in the Regulatory
Flexibility Act or the size standards established by the NRC (10 CFR
2.810).
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,
OMB.
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.
For the reasons set out in the preamble and under the authority of
the Atomic Energy Act of 1954, as amended; the Energy Reorganization
Act of 1974, as amended; the Nuclear Waste Policy Act of 1982, as
amended; and 5 U.S.C. 552 and 553; the NRC is adopting the following
amendments to 10 CFR part 72.
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); Energy Policy Act of 2005, Pub. L. No. 109-58, 119 Stat.
549 (2005).
Section 72.44(g) also issued under secs. 142(b) and 148(c), (d),
Pub. L. 100-203, 101
[[Page 9518]]
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 1014 is revised to read
as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate No.: 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.
Amendment Number 7 Effective Date: December 28, 2009.
Amendment Number 8 Effective Date: May 2, 2012.
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: May 31, 2020.
Model Number: HI-STORM 100.
* * * * *
Dated at Rockville, Maryland, this 25th day of January, 2012.
For the Nuclear Regulatory Commission.
R.W. Borchardt,
Executive Director for Operations.
[FR Doc. 2012-3678 Filed 2-16-12; 8:45 am]
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