[Federal Register Volume 80, Number 53 (Thursday, March 19, 2015)]
[Rules and Regulations]
[Pages 14291-14295]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-06367]
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Rules and Regulations
Federal Register
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Federal Register / Vol. 80, No. 53 / Thursday, March 19, 2015 / Rules
and Regulations
[[Page 14291]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2014-0275]
RIN 3150-AJ52
List of Approved Spent Fuel Storage Casks: Holtec HI-STORM Flood/
Wind System; Certificate of Compliance No. 1032, Amendment No. 1,
Revision 1
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its
spent fuel storage regulations by revising the Holtec International,
Inc. (Holtec), HI-STORM Flood/Wind (FW) System listing within the
``List of approved spent fuel storage casks'' to add Amendment No. 1,
Revision 1, to Certificate of Compliance (CoC) No. 1032. Amendment No.
1, Revision 1, allows these casks to accept 14X14B fuel assemblies with
minor changes in the internal diameter of the fuel cladding, diameter
of the fuel pellet, and spacing between the fuel pins. The amendment
also updates testing requirements for the fabrication of Metamic HT
neutron-absorbing structural material.
DATES: The direct final rule is effective June 2, 2015, unless
significant adverse comments are received by April 20, 2015. If the
direct final rule is withdrawn as a result of such comments, timely
notice of the withdrawal will be published in the Federal Register.
Comments received after this date will be considered if it is practical
to do so, but the Commission is able to ensure consideration only for
comments received on or before this date. Comments received on this
direct final rule will also be considered to be comments on a companion
proposed rule published in the Proposed Rules section of this issue of
the Federal Register.
ADDRESSES: You may submit comments by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0275. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Email comments to: [email protected]. If you do
not receive an automatic email reply confirming receipt, then contact
us at 301-415-1677.
Fax comments to: Secretary, U.S. Nuclear Regulatory
Commission at 301-415-1101.
Mail comments to: Secretary, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, ATTN: Rulemakings and
Adjudications Staff.
Hand deliver comments to: 11555 Rockville Pike, Rockville,
Maryland 20852, between 7:30 a.m. and 4:15 p.m. (Eastern Time) Federal
workdays; telephone: 301-415-1677.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Robert D. MacDougall, Office of
Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory
Commission, Washington DC 20555-0001; telephone: 301-415-5175, email:
[email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
II. Procedural Background
III. Background
IV. Discussion of Changes
V. Voluntary Consensus Standards
VI. Agreement State Compatibility
VII. Plain Writing
VIII. Environmental Assessment and Finding of No Significant
Environmental Impact
IX. Paperwork Reduction Act Statement
X. Regulatory Flexibility Certification
XI. Regulatory Analysis
XII. Backfitting and Issue Finality
XIII. Congressional Review Act
XIV. Availability of Documents
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2014-0275 when contacting the NRC
about the availability of information for this action. You may obtain
publicly-available information related to this action by any of the
following methods:
Federal rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0275.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to [email protected]. For
the convenience of the reader, instructions about obtaining materials
referenced in this document are provided in the ``Availability of
Documents'' section.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2014-0275 in the subject line of your
comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission.
[[Page 14292]]
Your request should state that the NRC does not routinely edit comment
submissions to remove such information before making the comment
submissions available to the public or entering the comment into ADAMS.
II. Procedural Background
This direct final rule is limited to adding Amendment No. 1,
Revision 1, which will supersede Amendment No. 1 (effective December
17, 2014), to CoC No. 1032 to the ``List of approved spent fuel storage
casks,'' and does not include other aspects of the Holtec HI-STORM FW
System design. Amendment No. 1 continues to be effective but is now
being modified with respect to certain specified provisions, as
outlined in Amendment No. 1, Revision 1, and in Section IV of this
document, which apply to all general licensees using the casks for
Independent Spent Fuel Storage Installations (ISFSIs). Therefore,
Amendment No. 1, Revision 1, supersedes the previously issued Amendment
No. 1 (effective December 17, 2014). In requesting this revision,
Holtec indicated that no ISFSI licensee has placed such a cask into
service under CoC No. 1032, Amendment No. 1.
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. The amendment to
the rule will become effective on June 2, 2015. However, if the NRC
receives significant adverse comments on this direct final rule by
April 20, 2015, 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 in
the Proposed Rule section of 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 Technical Specifications (TSs).
For detailed instructions on filing comments, please see the
ADDRESSES section of this document.
III. 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 [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 219(a) [sic: 218(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 which added a new subpart K in part 72 of Title
10 of the Code of Federal Regulations (10 CFR) 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 in 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
October 3, 2014 (79 FR 59623), that approved the HI-STORM FW System
design amendment and added it to the list of NRC-approved cask designs
in 10 CFR 72.214 as CoC No. 1032, Amendment No. 1.
IV. Discussion of Changes
On July 31, 2013, Holtec submitted a revision request for the
Holtec HI-STORM FW System CoC No. 1032, Amendment No. 1. Holtec
supplemented its request on November 5, 2013. As a revision, the CoC
will supersede the previous version of the CoC and its TSs, effective
December 17, 2014, in their entirety. Amendment No. 1, Revision 1,
revises the authorized contents of the cask in Appendix B to the TSs to
include 14X14B fuel assemblies with minor changes in the internal
diameter of the fuel cladding, diameter of the fuel pellet, and fuel
rod pitch (distance from fuel pin centerlines). The amendment also
updates testing requirements for the fabrication of Metamic HT neutron-
absorbing aluminum alloy structural material used to secure the spent
fuel inside the cask. These changes to Appendix B of the TSs are
identified with revision bars in the margin of the document.
Specifically, Amendment No. 1, Revision 1, changes the fuel
cladding internal diameter, the fuel pellet diameter, and the fuel rod
pitch (distance from fuel pin centerlines) of the fuel assembly class
14X14B. These changes in spacing between the fuel pins would result in
a volumetric increase of 0.6 percent of the fuel and a reduction of
0.13 percent of the original flow area. Because this reduced flow area
is still larger than the 17X17 assembly flow area used as the bounding
scenario, the flow resistance factor is still less restrictive than the
bounding scenario, and the passive decay heat removal of the proposed
14X14B assembly is still conservative.
Amendment No. 1, Revision 1, also removes fabrication testing
requirements for the thermal expansion coefficient and thermal
conductivity of Metamic HT neutron-absorbing structural material, as
these properties have little variability in this aluminum alloy when
fabricated according to the manufacturer's manual.
As documented in the safety evaluation report (SER), the NRC staff
performed a detailed safety evaluation of the proposed CoC Amendment
No. 1, Revision 1 request. There are no significant changes to cask
design requirements in the proposed Revision 1 to the CoC Amendment No.
1. Considering the specific design requirements for each accident
condition, the design of the cask would prevent loss of containment,
shielding, and criticality control. If there is no loss of containment,
shielding, or criticality control, the environmental impacts
[[Page 14293]]
would be insignificant. Amendment No. 1, Revision 1 does not reflect a
significant change in design or fabrication of the cask. In addition,
any resulting occupational exposure or offsite dose rates from the
implementation of Amendment No. 1, Revision 1, would remain well within
10 CFR part 20 radiation protection limits. Therefore, the proposed CoC
changes will not result in any radiological or non-radiological
environmental impacts that significantly differ from the environmental
impacts evaluated in the environmental assessment supporting the
October 3, 2014 (79 FR 59623), final rule that approved the HI-STORM FW
System design Amendment 1. There will be no significant change in the
types or amounts of any effluent released, no significant increase in
individual or cumulative radiation exposure, and no significant
increase in the potential for or consequences from radiological
accidents.
This direct final rule revises the Holtec HI-STORM FW System
listing in 10 CFR 72.214 by superseding Amendment 1 to CoC No. 1032
(effective December 17, 2014) with Amendment No. 1, Revision 1. The
revision consists of the changes previously described, as set forth in
the revised CoC and TSs. Appendix A and the revised Appendix B of the
TSs are identified in the SER and are also available in ADAMS.
The amended Holtec HI-STORM FW System 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; therefore, 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
Holtec HI-STORM FW Systems that meet the criteria of Amendment No. 1,
Revision 1, to CoC No. 1032 under 10 CFR 72.212.
V. Voluntary Consensus Standards
The National Technology Transfer and Advancement Act of 1995 (Pub.
L. 104-113) requires that Federal agencies use technical standards
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
HI-STORM FW System 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.
VI. 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.
VII. Plain Writing
The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal
agencies to write documents in a clear, concise, and well-organized
manner. The NRC has written this document to be consistent with the
Plain Writing Act as well as the Presidential Memorandum, ``Plain
Language in Government Writing,'' published June 10, 1998 (63 FR
31883).
VIII. Environmental Assessment and Finding of No Significant
Environmental Impact
A. The Action
This direct final rule amends 10 CFR 72.214 by revising the CoC for
the Holtec HI-STORM FW System design listing within the ``List of
approved spent fuel storage casks'' to add Amendment No. 1, Revision 1,
to CoC No. 1032. Under the National Environmental Policy Act of 1969,
as amended, and the NRC's regulations in subpart A of 10 CFR part 51,
``Environmental Protection Regulations for Domestic Licensing and
Related Regulatory Functions,'' 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 made a finding of no
significant impact on the basis of this environmental assessment.
B. The Need for the Action
This direct final rule revises the CoC for the Holtec HI-STORM FW
System within the list of approved systems that can be used for dry
storage of additional fuel assembly designs now in reactor spent fuel
storage pools.
C. Environmental Impacts of the Action
On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10
CFR part 72 to provide for the storage of spent fuel under a general
license in cask designs approved by the NRC. The potential
environmental impact of using NRC-approved storage casks was initially
analyzed in the environmental assessment for the 1990 final rule. The
environmental assessment for this Amendment No. 1, Revision 1, of CoC
1032 tiers off of the environmental assessment for the July 18, 1990,
final rule. Tiering on past environmental assessments is a standard
process under the National Environmental Policy Act.
Holtec HI-STORM FW Systems are designed to mitigate the effects of
design basis accidents that could occur during storage. Design basis
accidents account for human-induced events and the most severe natural
phenomena reported for the site and surrounding area. Postulated
accidents analyzed for an ISFSI, the type of facility at which a holder
of a power reactor operating license would store spent fuel in casks in
accordance with 10 CFR part 72, include tornado winds and tornado-
generated missiles, a design basis earthquake, a design basis flood, an
accidental cask drop, lightning effects, fire, explosions, and other
incidents.
Considering the specific design requirements for each accident
condition, the design of the cask would prevent loss of confinement,
shielding, and criticality control. If there is no loss of confinement,
shielding, or criticality control, the environmental impacts would be
insignificant. This amendment does not reflect a significant change in
design or fabrication of the cask. There are no significant changes to
cask design requirements in the proposed CoC amendment. In addition,
because there are no significant design or process changes, any
resulting occupational exposure or offsite dose rates from the
implementation of Amendment No. 1, Revision 1, would remain well within
10 CFR part 20 radiation protection limits. Therefore, the proposed CoC
changes will not result in any radiological or non-radiological
environmental impacts that significantly differ from the environmental
impacts evaluated in the environmental assessment supporting the July
18, 1990, final rule. There will be no significant change in the types
or amounts of any effluents released, no significant increase in
individual or cumulative radiation exposure, and no significant
[[Page 14294]]
increase in the potential for or consequences from radiological
accidents. The staff has documented its safety findings in the SER.
D. Alternative to the Action
The alternative to this action is to deny approval of Amendment No.
1, Revision 1, and end this direct final rule. Consequently, any 10 CFR
part 72 general licensee that seeks to load spent nuclear fuel into the
Holtec HI-STORM FW System in accordance with the changes described in
proposed Amendment No. 1, Revision 1, would have to request an
exemption from the requirements of 10 CFR 72.212 and 72.214. Under this
alternative, interested licensees would have to prepare, and the NRC
would have to review, each separate exemption request, thereby
increasing the administrative burden upon the NRC and the costs to each
licensee. Therefore, the environmental impacts of the alternative to
the action would be the same or more than the impacts of the action.
E. Alternative Use of Resources
Approval of Amendment No. 1, Revision 1, to CoC No. 1032 would
result in no irreversible commitments of resources.
F. Agencies and Persons Contacted
No agencies or persons outside the NRC were contacted in connection
with the preparation of this environmental assessment.
G. Finding of No Significant Impact
The environmental impacts of the action have been reviewed under
the requirements in 10 CFR part 51. Based on the foregoing
environmental assessment, the NRC concludes that this direct final rule
entitled, ``Holtec HI-STORM Flood/Wind System; Certificate of
Compliance No. 1032, Amendment No. 1, Revision 1,'' will not have a
significant effect on the human environment. Therefore, the NRC has
determined that an environmental impact statement is not necessary for
this direct final rule.
IX. Paperwork Reduction Act Statement
This rule does not contain any information collection requirements,
and is therefore not subject to the Paperwork Reduction Act of 1995 (44
U.S.C. 3501 et seq.).
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
Office of Management and Budget control number.
X. 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, Inc. 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).
XI. 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 March 28, 2011 (76 FR 17019),
the NRC issued an amendment to 10 CFR part 72 that approved the Holtec
HI-STORM FW System design by adding it to the list of NRC-approved cask
designs in 10 CFR 72.214.
On July 31, 2013, and as supplemented on November 5, 2013, Holtec
submitted an application to amend the HI-STORM FW System as described
in Section IV, ``Discussion of Changes,'' of this document.
The alternative to this action is to withhold approval of Amendment
No. 1, Revision 1, and to require any 10 CFR part 72 general licensee
seeking to load spent nuclear fuel into a Holtec HI-STORM FW System
under the changes described in Amendment No. 1, Revision 1, 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 therefore, this action is recommended.
XII. Backfitting and Issue Finality
This direct final rule revises the CoC No. 1032 for the Holtec HI-
STORM FW System, as currently listed in 10 CFR 72.214, ``List of
approved spent fuel storage casks.'' Amendment No. 1, Revision 1,
revises authorized contents of the cask to include 14X14B fuel
assemblies with minor changes in the internal diameter of the fuel
cladding, diameter of the fuel pellet, and spacing between the fuel
pins. The revision also updates testing requirements for the
fabrication of Metamic HT neutron-absorbing aluminum alloy structural
material used to secure the spent fuel inside the cask.
Although Holtec has manufactured some casks under the existing CoC
1032, Amendment No. 1 that is being revised by this direct final rule,
Holtec, as the vendor, is not subject to backfitting protection under
10 CFR 72.62. Moreover, Holtec requested the change and has requested
to apply it to the existing casks manufactured under Amendment No. 1.
Therefore, even if the vendor were deemed to be an entity protected
from backfitting, this request represents a voluntary change and is not
backfitting.
Additionally, because Holtec has not delivered any cask certified
under CoC No. 1032, Amendment No. 1, no ISFSI licensee has placed such
a cask into service. Therefore, the changes in Amendment 1, Revision 1
which are approved in this direct final rule do not fall within the
definition of backfitting under 10 CFR 72.62 or 10 CFR 50.109(a)(1), or
otherwise represent an inconsistency with the issue finality provisions
applicable to combined licenses in 10 CFR part 52.
Finally, the changes in CoC No. 1032, Amendment 1, Revision 1 do
not apply to casks manufactured to the initial CoC 1032, and therefore,
have no effect on current ISFSI licensees using these casks. While any
current CoC user may comply with the new requirements in Amendment No.
1, Revision 1, this would be a voluntary decision on the part of the
user. For these reasons, NRC approval of CoC No. 1032, Amendment
[[Page 14295]]
No. 1, Revision 1, does not constitute backfitting under 10 CFR 72.62
or 10 CFR 50.109(a)(1), or otherwise represent an inconsistency with
the issue finality provisions in 10 CFR part 52 for users of the Holtec
HI-STORM FW System manufactured to the initial CoC No. 1032.
For the reasons set forth above, the NRC has not prepared a backfit
analysis or additional documentation addressing the issue finality
criteria in 10 CFR part 52.
XIII. Congressional Review Act
This action is not a major rule as defined in the Congressional
Review Act (5 U.S.C. 801-808).
XIV. Availability of Documents
The documents identified in the following table are available to
interested persons through one or more of the following methods, as
indicated below.
------------------------------------------------------------------------
ADAMS Accession No./Web link/
Document Federal Register citation
------------------------------------------------------------------------
CoC No. 1032, Amendment No. 1, Revision ML14276A621
1.
CoC No. 1032, Amendment No. 1, Revision ML14276A618
1, Appendix A to the Technical
Specifications.
CoC No. 1032, Amendment No. 1, Revision ML14276A617
1, Appendix B of the Technical
Specifications.
CoC No. 1032, Amendment No. 1, Revision ML14276A620
1, Preliminary SER.
Holtec International HI-STORM Flood/Wind ML13214A023
Multipurpose Canister Storage System,
License Amendment Request 1032-2, July
31, 2013.
Submittal of Response to First Request ML13311A103
for Additional Information for License
Amendment Request No. 2 to the Holtec
International HI[dash]STORM Flood/Wind
Multi-Purpose Canister Storage System,
November 5, 2013.
------------------------------------------------------------------------
The NRC may post materials related to this document, including
public comments, on the Federal rulemaking Web site at http://www.regulations.gov under Docket ID NRC-2014-0275. The Federal
rulemaking Web site allows you to receive alerts when changes or
additions occur in a docket folder. To subscribe: (1) Navigate to the
docket folder (NRC-2014-0275); (2) click the ``Sign up for Email
Alerts'' link; and (3) enter your email address and select how
frequently you would like to receive emails (daily, weekly, or
monthly).
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: Atomic Energy Act secs. 51, 53, 57, 62, 63, 65, 69,
81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42 U.S.C.
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2239, 2273, 2282, 2021); Energy Reorganization Act
secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851);
National Environmental Policy Act sec. 102 (42 U.S.C. 4332); Nuclear
Waste Policy Act secs. 131, 132, 133, 135, 137, 141 148 (42 U.S.C.
10151, 10152, 10153, 10155, 10157, 10161, 10168); Government
Paperwork Elimination Act sec. 1704 (44 U.S.C. 3504 note); Energy
Policy Act of 2005, Pub. L. 109-58, 119 Stat. 788 (2005).
Section 72.44(g) also issued under Nuclear Waste Policy Act
secs. 142(b) and 148(c), (d) (42 U.S.C. 10162(b), 10168(c), (d)).
Section 72.46 also issued under Atomic Energy Act sec. 189 (42
U.S.C. 2239); Nuclear Waste Policy Act sec. 134 (42 U.S.C. 10154).
Section 72.96(d) also issued under Nuclear Waste Policy Act sec.
145(g) (42 U.S.C. 10165(g)).
Subpart J also issued under Nuclear Waste Policy Act secs.
117(a), 141(h) (42 U.S.C. 10137(a), 10161(h)).
Subpart K also issued under Nuclear Waste Policy Act sec. 218(a)
(42 U.S.C. 10198).
0
2. In Sec. 72.214, Certificate of Compliance No. 1032 is revised to
read as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1032.
Initial Certificate Effective Date: June 13, 2011.
Amendment Number 1 Effective Date: December 17, 2014, superseded by
Amendment Number 1, Revision 1, on June 2, 2015.
Amendment Number 1, Revision 1, Effective Date: June 2, 2015.
SAR Submitted by: Holtec International, Inc.
SAR Title: Final Safety Analysis Report for the Holtec HI-STORM FW
System.
Docket Number: 72-1032.
Certificate Expiration Date: June 12, 2031.
Model Number: HI-STORM FW MPC-37, MPC-89.
* * * * *
Dated at Rockville, Maryland, this 9th day of March, 2015.
For the Nuclear Regulatory Commission.
Mark A. Satorius,
Executive Director for Operations.
[FR Doc. 2015-06367 Filed 3-18-15; 8:45 am]
BILLING CODE 7590-01-P