List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System; Certificate of Compliance No. 1014, Amendment No. 10, 13265-13271 [2016-05711]
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Federal Register / Vol. 81, No. 49 / Monday, March 14, 2016 / Rules and Regulations
Subpart A—General Provisions:
1. Are the definitions (in 10 CFR 37.5,
‘‘Definitions’’) clear, unambiguous, and
consistent with their usage in other
parts of the regulations?
2. Is the rule clear as to when a
licensee can use physical barriers to
render aggregated sources below the
category 2 aggregated quantity?
Subpart B—Background Investigations
and Access Control Program:
3. Are the requirements of subpart B
clear for use in determining individuals
to be trustworthy and reliable?
4. While the regulations provide the
type of information that must be
gathered before making a
Trustworthiness and Reliability (T&R)
determination, NUREG–2155 provides
additional guidance on determining
whether someone is T&R. Is the
information in Annex A to NUREG–
2155 adequate in helping a Reviewing
Official make a T&R determination?
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Subpart C—Physical Protection
Requirements During Use:
5. Do the requirements of subpart C
clearly define what is needed to support
the physical protection of licensed
category 1 and category 2 quantities of
radioactive material during use?
6. Which requirements in 10 CFR
37.45, ‘‘LLEA [local law enforcement
agency] coordination,’’ have you found
to be instrumental in ensuring an
adequate LLEA response, should an
LLEA response be needed? Is there other
information you think should be
required to be shared with an LLEA?
7. Isolation of category 1 and category
2 quantities of radioactive material by
the use of continuous physical barriers
that allow access to the security zone
only through established access control
points is required in 10 CFR 37.37,
‘‘Security zones.’’ Is the rule clear as to
what qualifies as an adequate physical
barrier?
8. Do the requirements in 10 CFR
37.57, ‘‘Reporting of events,’’ clearly
define a licensee’s responsibility to
notify the LLEA and the NRC’s
Operations Center?
Subpart D—Physical Protection in
Transit:
9. Do the requirements of subpart D
clearly define what is needed to support
the physical protection of licensed
category 1 and category 2 quantities of
radioactive material in transit?
10. Are the requirements in 10 CFR
37.81, ‘‘Reporting of events,’’ clear in
defining the licensee’s responsibility to
notify LLEA and the NRC’s Operations
Center within 1 hour when a
determination is made that a shipment
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of a category 1 quantity of radioactive
material is lost or missing?
Implementation Guidance Documents:
Please specify the sections of
NUREG–2155 and NUREG–2166 in your
responses to the extent practicable.
11. How have you utilized NUREG–
2155 to implement the 10 CFR part 37
regulatory requirements in order to
protect your licensed category 1 and
category 2 quantities of radioactive
material? If utilized, are there certain
areas of NUREG–2155 that you have
found to be particularly useful? Are
there areas of NUREG–2155 that you
think could be clarified or
supplemented to make it a more useful
tool?
12. How have you utilized NUREG–
2166 to implement the 10 CFR part 37
regulatory requirements in order to
protect your licensed category 1 and
category 2 quantities of radioactive
material? If utilized, are there certain
areas of NUREG–2166 that you have
found to be particularly useful?
Are there areas of NUREG–2166 that
you think could be clarified or
supplemented to make it a more useful
tool?
IV. Public Comments Process
The NRC is committed to keeping the
public informed and values public
involvement in its assessment effort.
Responses to this solicitation will be
considered by NRC in preparing a report
to the Committees on Appropriations of
the House of Representatives and the
Senate, pursuant to Public Law 113–
235, Section 403. The NRC, however,
does not intend to provide specific
responses to comments or other
information submitted in response to
this request.
V. Public Meetings
The NRC plans to hold a series of
licensee-specific webinars, and one inperson meeting, during the public
comment period for this action. The
public meetings will provide forums for
the NRC staff to discuss the issues and
questions with members of the public.
The information received will be used
by NRC to develop a report to the
Committees on Appropriations of the
House of Representatives and the
Senate. The NRC does not intend to
provide detailed responses to
information or other comments
submitted during the public meetings.
Each public meeting will be noticed on
the NRC’s public meeting Web site at
least 10 calendar days before the
meeting. Members of the public should
monitor the NRC’s public meeting Web
site for additional information about the
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public meetings at https://www.nrc.gov/
public-involve/public-meetings/
index.cfm. The NRC will post the
notices for the public meetings and may
post additional material related to this
action to the Federal rulemaking Web
site at www.regulations.gov under
Docket ID NRC–2015–0109. 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–
2015–0109); (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).
Dated at Rockville, Maryland, this 1st day
of March, 2016.
For the Nuclear Regulatory Commission.
Daniel S. Collins,
Director, Division of Material Safety, State,
Tribal and Rulemaking Programs, Office of
Nuclear Material Safety and Safeguards.
[FR Doc. 2016–05260 Filed 3–11–16; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 72
[NRC–2015–0270]
RIN 3150–AJ71
List of Approved Spent Fuel Storage
Casks: Holtec International HI–STORM
100 Cask System; Certificate of
Compliance No. 1014, Amendment No.
10
Nuclear Regulatory
Commission.
ACTION: Direct final rule.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is amending its
spent fuel storage regulations by
revising the Holtec International (Holtec
or applicant) HI–STORM 100 Cask
System listing within the ‘‘List of
approved spent fuel storage casks’’ to
include Amendment No. 10 to
Certificate of Compliance (CoC) No.
1014. Amendment No. 10 adds new fuel
classes to the contents approved for the
loading of 16×16-pin fuel assemblies
into a HI–STORM 100 Cask System;
allows a minor increase in manganese in
an alloy material for the system’s
overpack and transfer cask; clarifies the
minimum water displacement required
of a dummy fuel rod (i.e., a rod not
filled with uranium pellets); and
clarifies the design pressures needed for
normal operation of forced helium
drying systems. Additionally,
Amendment No. 10 revises Condition
SUMMARY:
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Federal Register / Vol. 81, No. 49 / Monday, March 14, 2016 / Rules and Regulations
No. 9 of CoC No. 1014 to provide clearer
direction on the measurement of air
velocity and modeling of heat
distribution through the storage system.
Each of these changes is described in
Section IV, ‘‘Discussion of Changes,’’ in
the SUPPLEMENTARY INFORMATION section
of this document.
DATES: The direct final rule is effective
May 31, 2016, unless significant adverse
comments are received by April 13,
2016. 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
https://www.regulations.gov and search
for Docket ID NRC–2015–0270. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Email comments to:
Rulemaking.Comments@nrc.gov. 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,
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Washington DC 20555–0001; telephone:
301–415–5175; email:
Robert.MacDougall@nrc.gov.
SUPPLEMENTARY INFORMATION:
Table of Contents
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–2015–
0270 when contacting the NRC about
the availability of information for this
action. You may obtain publiclyavailable information related to this
action by any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2015–0270.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://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 pdr.resource@nrc.gov. 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–2015–
0270 in 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 https://
www.regulations.gov as well as enter the
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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, then 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.
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 rule is limited to the changes
contained in Amendment No. 10 to CoC
No. 1014 and does not include other
aspects of the Holtec HI–STORM 100
Cask System design. The NRC is using
the ‘‘direct final rule procedure’’ to
issue this amendment because it
represents a limited and routine change
to an existing CoC that is expected to be
noncontroversial. Adequate protection
of public health and safety continues to
be ensured. The amendment to the rule
will become effective on May 31, 2016.
However, if the NRC receives significant
adverse comments on this direct final
rule by April 13, 2016, 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-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.
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(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 companion
proposed rule published in the
Proposed Rule section of this issue of
the Federal Register.
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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 ‘‘[the
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 May
1, 2000 (65 FR 25241) that approved the
Holtec HI–STORM 100 Cask System
design and added it to the list of NRCapproved cask designs in 10 CFR 72.214
as CoC No. 1014.
IV. Discussion of Changes
On January 5, 2015, Holtec submitted
a request to the NRC to amend CoC No.
1014. Amendment No. 10 (1) adds new
fuel classes to the contents approved for
the loading of 16X16-pin fuel
assemblies into a HI–STORM 100 Cask
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System; (2) allows a minor increase in
manganese in an alloy material for the
system’s overpack and transfer cask; (3)
clarifies the minimum water
displacement required of a dummy fuel
rod (i.e., a rod not filled with uranium
pellets); and (4) clarifies the design
pressures expected for normal operation
of forced helium drying systems.
Additionally, Amendment No. 10
revises Condition No. 9 of CoC No. 1014
to provide clearer direction on the
measurement of air velocity and
modeling of heat distribution through
the storage system. These changes are
further discussed in this section, and
the changes to the affected TS
Appendices are identified with revision
bars in the margin of each document.
1. Addition of New 16X16B and 16X16C
Fuel Classes to the Contents Approved
for Storage in a HI–STORM 100 Cask
System
The contents, enrichment, weight,
and dimensions of the new 16X16 fuel
assembly classes are all bounded by
previously approved 16X16 classes. The
NRC staff determined that the
applicant’s analysis of the adequacy of
the HI–STORM 100 package’s shielding
for the new fuel classes supports the
conclusion that this shielding
evaluation is also bounded by the
previously evaluated classes of 16X16
fuel. From its criticality evaluations in
the safety evaluation report (SER), the
NRC staff also determined that the
calculated maximum neutron fluences
of the 16X16B and 16X16C fuel classes
are statistically similar to the alreadyapproved 16X16A fuel class, and both
are well bounded by the design basis
fuel. The staff therefore has reasonable
assurance that the new fuel classes are
consistent with the appropriate
standards for shielding, criticality, and
other required safety analyses, and that
the package design and contents satisfy
the radiation protection and criticality
safety requirements in 10 CFR 72.14,
72.124, 72.106, and 72.236.
2. Addition to American Society of
Mechanical Engineers (ASME) Boiler
and Pressure Vessel Code Alternative
Table To Allow a Newer Alloy Material
In its request for this amendment,
Holtec proposed an additional
exemption to the ASME Boiler and
Pressure Vessel Code Alternative Table
to allow the use of more recent Code
versions of material SA–516/516A
Grade 70, an alloy like the one used in
the overpack and transfer cask of the
HI–STORM 100 Cask System. All SA–
516 material used in the HI–STORM 100
Cask System is required to meet the
material composition described in
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ASME Boiler and Pressure Vessel Code
Section II, 2007 edition. This edition
allows for a different manganese content
from the 1995 edition, but does not
change the structural or thermal
properties of the material. The
applicant’s request proposed no change
in mechanical properties and no
alteration in the form, fit, or function of
these system components resulting from
the minor change in composition of the
alloy. The NRC staff therefore finds the
requested exemption acceptable for the
affected structures, systems, and
components of CoC No. 1014.
3. Editorial Clarifications
3.a. Clarification of Minimum
Displacement of Dummy Fuel Rods
When reactor operators become aware
of a damaged or malfunctioning fuel pin
in a fuel assembly, they may remove the
assembly from the reactor core, replace
the problem pin with a dummy fuel rod
containing no uranium, and return the
assembly to the reactor core to recover
the assembly’s remaining energy value.
An assembly with a dummy rod may or
may not be considered ‘‘intact’’ for
handling purposes when it is finally
removed from the reactor core. In
Appendix A of the TSs, the definition
of ‘‘Intact Fuel Assemblies’’ now
clarifies the description of ‘‘dummy fuel
rod’’ to specify that it must displace at
least the same amount of water as would
a fuel rod in the active fuel region of the
assembly, because criticality safety
analyses are based on displacement of
water in that location. Specifically, the
definition states that ‘‘[f]uel assemblies
without fuel rods in fuel rod locations
shall not be classified as INTACT FUEL
ASSEMBLIES unless dummy fuel rods
are used to displace an amount of water
greater than or equal to that displaced
by the fuel rod(s) in the active region [of
the fuel assembly].’’ Intact fuel
assemblies are by definition those that
can be handled by normal means. In
effect, this clarification of the minimum
volume of a dummy rod provides that
a fuel assembly with any such rods may
not be handled by normal means unless
these rods displace an equal or greater
volume of water than rods containing
fuel in the region of the assembly where
there is nuclear material. The greater
volume of fresh (unborated) water
displaced by the dummy rod results in
correspondingly less water available to
moderate neutrons to a speed that could
sustain a nuclear reaction, and
consequently, the greater displacement
will reduce reactivity in an accident
involving flooding with fresh water.
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3.b. Clarification of Helium Pressure
Limits for Drying and Backfilling of
Multi-Purpose Canisters (MPCs) in
Underground Installations
As indicated in Table 3–1 of
Appendix A–100U for HI–STORM 100
Cask Systems intended for deployment
in underground spent fuel storage
installations, use of a closed-loop forced
helium dehydration (FHD) system is an
alternative to vacuum drying for an
MPC containing moderate burnup fuel,
and FHD is mandatory for drying MPCs
with one or more high burnup fuel
assemblies or a higher heat load. Section
3.6.2.2 of Appendix B–100U for HI–
STORM Cask Systems was revised to
clarify that the design pressure limit for
normal operation of the FHD system is
for drying only and not for backfilling
the MPC with helium at lower pressures
for long-term storage.
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4. Revised Condition No. 9 of CoC No.
1014
The NRC staff revised Condition No.
9, ‘‘Special Requirements for First
Systems in Place,’’ to provide a more
appropriate location to perform air
velocity measurements to gauge the
cooling effect of air convection in the
dry cask storage system. The previous
language in the CoC required the
measurements at the annular gap
between the canister and the overpack.
This location is difficult to access, and
the measured data proved to be
unreliable because air velocities can
vary chaotically, especially at a location
close to the top of the canister. The
revised Condition No. 9 directs the user
to make the measurements at the inlet
vents, where the user can obtain the
total mass flow rate of the air and
perform a meaningful comparison with
predicted results.
The NRC staff also revised Condition
No. 9 to specify that measurements of
the Supplemental Cooling System be
used to validate the analytical methods
described in the applicant’s final safety
analysis report (FSAR) for the cask. The
cask user will therefore need to develop
a thermal model of this cask using the
analytical methods described in the
FSAR. This will avoid unnecessary
approximations in the thermal model
that could add uncertainty in the
predicted results. The revised language
more precisely specifies the parameters
to be measured and the analysis
necessary to satisfy the Condition.
5. Conclusions
As documented in the SER for
Amendment No. 10, the NRC staff
performed a detailed safety evaluation
of the proposed CoC amendment
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request. There are no significant
changes to cask design requirements in
the proposed CoC amendment.
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
would be insignificant. This amendment
does not reflect a significant change in
design or fabrication of the cask. In
addition, any resulting changes in
occupational exposure or offsite dose
from the implementation of Amendment
No. 10 would remain well within 10
CFR part 20 limits.
Therefore, based on these findings of
the SER and those of the environmental
assessment below, the NRC staff
concludes that the proposed CoC
changes will not result in any
radiological or non-radiological
environmental impacts that differ
significantly from the environmental
impacts evaluated in the environmental
assessment (EA) supporting the May 1,
2000, final rule approving CoC No.
1014. There will be no significant
change in the types or amounts of any
effluent released, no significant increase
in individual or cumulative radiation
exposures, and no significant increase
in the potential for or consequences of
radiological accidents.
This direct final rule revises the
Holtec HI–STORM 100 Cask System
listing in 10 CFR 72.214 by adding
Amendment No. 10 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 Holtec HI–STORM 100
Cask 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 HI–
STORM 100 Cask Systems that meet the
criteria of Amendment No. 10 to CoC
No. 1014 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 any
such standard is inconsistent with
applicable law or otherwise impractical.
In this direct final rule, the NRC will
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revise the Holtec HI–STORM 100 Cask
System design listed in 10 CFR 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, and a Category
‘‘NRC’’ does not confer regulatory
authority on the State, the State may
wish to inform its licensees of certain
requirements by means consistent with
the particular State’s administrative
procedure laws.
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
The action is to amend 10 CFR 72.214
to revise the Holtec HI–STORM 100
Cask System listing within the ‘‘List of
approved spent fuel storage casks’’ to
include Amendment No. 10 to CoC No.
1014. Under the National
Environmental Policy Act of 1969, as
amended (NEPA), 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 (EIS) is not required. The NRC
has made a finding of no significant
impact on the basis of this EA.
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B. The Need for the Action
This direct final rule is needed to
allow users of HI–STORM 100 Cask
Systems under Amendment No. 10 to
load for dry storage under a general
license additional classes of fuel
assemblies that would otherwise have to
remain in spent fuel storage pools. This
direct final rule amends the CoC for the
Holtec HI–STORM 100 Cask System
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.
Specifically, Amendment No. 10 (1)
adds new fuel classes to the contents
approved for the loading of 16X16-pin
fuel assemblies into a HI–STORM 100
Cask System; (2) allows a minor
increase in manganese in an alloy
material for the system’s overpack and
transfer cask; (3) clarifies the minimum
water displacement required of a
dummy fuel rod (i.e., a rod not filled
with uranium pellets); and (4) clarifies
the design pressures expected for
normal operation of forced helium
drying systems. Additionally,
Amendment No. 10 revises Condition
No. 9 of CoC No. 1014 to provide clearer
direction on the measurement of air
velocity and modeling of heat
distribution through the storage system.
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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 EA for the 1990
final rule. The EA for Amendment No.
10 tiers off of the EA for the July 18,
1990, final rule. Tiering on past EAs is
a standard process under NEPA by
which impact analyses in a previous EA
can be cited by a subsequent EA as
bounding the expected impacts of a new
proposed action within the scope of the
previous EA.
The Holtec HI–STORM 100 Cask
System is 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 Independent Spent Fuel
Storage Installation, 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 tornadogenerated missiles, a design basis
earthquake, a design basis flood, an
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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 proposed
CoC amendment does not reflect a
significant change in cask design or
fabrication requirements. Because there
are no significant design or production
process changes, any resulting
occupational exposure or offsite dose
rates from the implementation of
Amendment No. 10 would remain well
within all applicable 10 CFR part 20
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 EA supporting the July
18, 1990, final rule. There will be no
significant change in the types or
amounts of any effluent released, no
significant increase in individual or
cumulative radiation exposures, and no
significant increase in the potential for
or consequences of radiological
accidents. The NRC staff documented
these safety findings in the SER.
D. Alternative to the Action
The alternative to this action is to
deny approval of Amendment No. 10
and withdraw the direct final rule.
Consequently, any 10 CFR part 72
general licensee that seeks to load spent
nuclear fuel into the Holtec HI–STORM
100 Cask System in accordance with the
changes described in proposed
Amendment No. 10 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. The
environmental impacts of this
alternative would therefore be the same
as or greater than the preferred action.
E. Alternative Use of Resources
Approval of Amendment No. 10 to
CoC No. 1014 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 EA.
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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 EA, the NRC concludes
that this direct final rule entitled, ‘‘List
of Approved Spent Fuel Storage Casks:
Holtec International HI–STORM 100
Cask System; Certificate of Compliance
No. 1014, Amendment No. 10,’’ will not
have a significant effect on the human
environment. Therefore, the NRC has
determined that an EIS for this direct
final rule is not necessary.
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. 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 May 1, 2000 (65 FR 25241), the NRC
issued an amendment to 10 CFR part 72
that approved the Holtec HI–STORM
100 Cask System design by adding it to
the list of NRC-approved cask designs in
10 CFR 72.214.
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On January 5, 2015, Holtec submitted
an application to amend the HI–STORM
100 Cask System CoC as described in
Section IV, ‘‘Discussion of Changes,’’ of
this document.
The alternative to this action is to
withhold approval of Amendment No.
10 and require any 10 CFR part 72
general licensee seeking to load spent
nuclear fuel into the Holtec HI–STORM
100 Cask System under the changes
described in Amendment No. 10 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 EA, 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 on or benefit to 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
The NRC has determined that the
backfit rule (10 CFR 72.62) does not
apply to this direct final rule. Therefore,
a backfit analysis is not required. This
direct final rule revises CoC No. 1014
for the Holtec HI–STORM 100 Cask
System, as currently listed in 10 CFR
72.214, ‘‘List of approved spent fuel
storage casks.’’ The revision consists of
Amendment No. 10, which (1) adds new
fuel classes to the contents approved for
the loading of 16X16-pin fuel
assemblies into a HI–STORM 100 Cask
System; (2) allows a minor increase in
manganese in an alloy material for the
system’s overpack and transfer cask; (3)
clarifies the minimum water
displacement required of a dummy fuel
rod (i.e., a rod not filled with uranium
pellets); and (4) clarifies the design
pressures expected for normal operation
of forced helium drying systems.
Additionally, Amendment No. 10
revises Condition No. 9 of CoC No. 1014
to provide clearer direction on the
measurement of air velocity and
modeling of heat distribution through
the storage system.
Amendment No. 10 to CoC No. 1014
for the Holtec HI–STORM 100 Cask
System was initiated by Holtec, and was
not submitted in response to new NRC
requirements or an NRC request for
amendment. Amendment No. 10 applies
only to new casks fabricated and used
under Amendment No. 10. These
changes do not affect existing users of
the Holtec HI–STORM 100 Cask System;
the current Amendment No. 9 and
earlier amendments continue to be
effective for existing users. While
current CoC users may comply with the
new requirements in Amendment No.
10, this would be a voluntary decision
on the part of current users. For these
reasons, Amendment No. 10 to CoC No.
1014 does not constitute backfitting
under 10 CFR 72.62, 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. Accordingly,
no backfit analysis or additional
documentation addressing the issue
finality criteria in 10 CFR part 52 has
been prepared by the NRC staff.
XIII. Congressional Review Act
The Office of Management and Budget
has not found this to be a major rule as
defined in the Congressional Review
Act.
XIV. Availability of Documents
The documents identified in the
following table are available to
interested persons as indicated.
ADAMS Accession
No.
Document
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Holtec International HI–STORM 100 Cask System—License Amendment Request (1014–10)
Proposed CoC No. 1014, Amendment No. 10 ...........................................................................
Appendix A for Proposed CoC No. 1014, Amendment No. 10 .................................................
Appendix B for Proposed CoC No. 1014, Amendment No. 10 .................................................
Appendix A—100U for Proposed CoC No. 1014, Amendment No. 10 .....................................
Appendix B—100U for Proposed CoC No. 1014, Amendment No. 10 .....................................
Preliminary SER for Proposed CoC No. 1014, Amendment No. 10 .........................................
The NRC may post materials related
to this document, including public
comments, on the Federal Rulemaking
Web site at https://www.regulations.gov
under Docket ID NRC–2015–0270. 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–2015–0270); (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
training programs, Nuclear energy,
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.
Administrative practice and
procedure, Criminal penalties,
Hazardous waste, Indians,
Intergovernmental relations, Manpower
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ML15007A435.
ML15331A307.
ML15331A310.
ML15331A311.
ML15331A312.
ML15331A313.
ML15331A309.
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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: Atomic Energy Act of 1954,
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, 2210e, 2232, 2233, 2234,
2236, 2237, 2238, 2273, 2282, 2021); Energy
Reorganization Act of 1974, secs. 201, 202,
206, 211 (42 U.S.C. 5841, 5842, 5846, 5851);
National Environmental Policy Act of 1969
(42 U.S.C. 4332); Nuclear Waste Policy Act
of 1982, secs. 117(a), 132, 133, 134, 135, 137,
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Federal Register / Vol. 81, No. 49 / Monday, March 14, 2016 / Rules and Regulations
141, 145(g), 148, 218(a) (42 U.S.C. 10137(a),
10152, 10153, 10154, 10155, 10157, 10161,
10165(g), 10168, 10198(a)) 44 U.S.C. 3504
note.
DEPARTMENT OF TRANSPORTATION
Federal Aviation Administration
14 CFR Part 39
2. In § 72.214, Certificate of
Compliance 1014 is revised to read as
follows:
■
[Docket No. FAA–2016–4222; Directorate
Identifier 2016–NM–017–AD; Amendment
39–18433; AD 2016–06–02]
§ 72.214 List of approved spent fuel
storage casks.
RIN 2120–AA64
*
Airworthiness Directives; The Boeing
Company Airplanes
*
*
*
*
Certificate Number: 1014.
Initial Certificate Effective Date: May
31, 2000.
Amendment Number 1 Effective Date:
July 15, 2002.
Amendment Number 2 Effective Date:
June 7, 2005.
Amendment Number 3 Effective Date:
May 29, 2007.
Amendment Number 4 Effective Date:
January 8, 2008.
Amendment Number 5 Effective Date:
July 14, 2008.
Amendment Number 6 Effective Date:
August 17, 2009.
Amendment Number 7 Effective Date:
December 28, 2009.
Amendment Number 8 Effective Date:
May 2, 2012, as corrected on November
16, 2012 (ADAMS Accession No.
ML12213A170).
Amendment Number 9 Effective Date:
March 11, 2014.
Amendment Number 10 Effective
Date: May 31, 2016.
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 2nd day
of March, 2016.
For the Nuclear Regulatory Commission.
Victor M. McCree,
Executive Director of Operations.
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[FR Doc. 2016–05711 Filed 3–11–16; 8:45 am]
BILLING CODE 7590–01–P
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Federal Aviation
Administration (FAA), DOT.
ACTION: Final rule; request for
comments.
AGENCY:
We are adopting a new
airworthiness directive (AD) for all The
Boeing Company Model 737–300, –400,
and –500 series airplanes. This AD
requires repetitive inspections for
cracking in the horizontal and vertical
flanges of the rear spar upper chord of
the horizontal stabilizer, and related
investigative and corrective actions if
necessary. This AD was prompted by a
report of cracking in the center section
of the horizontal stabilizer. We are
issuing this AD to detect and correct
cracking of the rear spar center section
of the horizontal stabilizer that could
lead to departure of the horizontal
stabilizer from the airplane.
DATES: This AD is effective March 29,
2016.
The Director of the Federal Register
approved the incorporation by reference
of a certain publication listed in this AD
as of March 29, 2016.
We must receive comments on this
AD by April 28, 2016.
ADDRESSES: You may send comments,
using the procedures found in 14 CFR
11.43 and 11.45, by any of the following
methods:
• Federal eRulemaking Portal: Go to
https://www.regulations.gov. Follow the
instructions for submitting comments.
• Fax: 202–493–2251.
• Mail: U.S. Department of
Transportation, Docket Operations, M–
30, West Building Ground Floor, Room
W12–140, 1200 New Jersey Avenue SE.,
Washington, DC 20590.
• Hand Delivery: U.S. Department of
Transportation, Docket Operations, M–
30, West Building Ground Floor, Room
W12–140, 1200 New Jersey Avenue SE.,
Washington, DC 20590, between 9 a.m.
and 5 p.m., Monday through Friday,
except Federal holidays.
For service information identified in
this final rule, contact Boeing
Commercial Airplanes, Attention: Data
& Services Management, P.O. Box 3707,
MC 2H–65, Seattle, WA 98124–2207;
SUMMARY:
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13271
telephone 206–544–5000, extension 1;
fax 206–766–5680; Internet https://
www.myboeingfleet.com. You may view
this referenced service information at
the FAA, Transport Airplane
Directorate, 1601 Lind Avenue SW.,
Renton, WA. For information on the
availability of this material at the FAA,
call 425–227–1221. It is also available
on the Internet at https://
www.regulations.gov by searching for
and locating Docket No. FAA–2016–
4222.
Examining the AD Docket
You may examine the AD docket on
the Internet at https://
www.regulations.gov by searching for
and locating Docket No. FAA–2016–
4222; or in person at the Docket
Management Facility between 9 a.m.
and 5 p.m., Monday through Friday,
except Federal holidays. The AD docket
contains this AD, the regulatory
evaluation, any comments received, and
other information. The street address for
the Docket Office (phone: 800–647–
5527) is in the ADDRESSES section.
Comments will be available in the AD
docket shortly after receipt.
FOR FURTHER INFORMATION CONTACT:
Payman Soltani, Aerospace Engineer,
Airframe Branch, ANM–120L, FAA, Los
Angeles Aircraft Certification Office
(ACO), 3960 Paramount Boulevard,
Lakewood, CA 90712–4137; phone:
562–627–5313; fax: 562–627–5210;
email: Payman.Soltani@faa.gov.
SUPPLEMENTARY INFORMATION:
Discussion
We have received a report of cracking
in the center section of the horizontal
stabilizer. A review of empennage
loading of the Model 737–300, –400,
and –500 series airplanes identified
several loading discrepancies that
included landing rollout (LRO) buffet
condition within the ground-air-ground
(GAG) operational loads. These loading
discrepancies impact the operating
stress level on the rear spar upper chord
of the horizontal stabilizer center
section, which can lead to cracking. We
have determined that the inspection
threshold for detecting the cracking
needs to be lower than the existing
required compliance threshold of 66,000
total flight cycles. This horizontal
stabilizer center section cracking, if not
corrected, could result in departure of
the horizontal stabilizer from the
airplane.
Related Rulemaking
On April 8, 2008, we issued AD 2008–
09–13, Amendment 39–15494 (73 FR
24164, May 2, 2008), for all Boeing
Model 737–300, –400, and –500 series
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]]>Agencies
[Federal Register Volume 81, Number 49 (Monday, March 14, 2016)]
[Rules and Regulations]
[Pages 13265-13271]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-05711]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2015-0270]
RIN 3150-AJ71
List of Approved Spent Fuel Storage Casks: Holtec International
HI-STORM 100 Cask System; Certificate of Compliance No. 1014, Amendment
No. 10
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its
spent fuel storage regulations by revising the Holtec International
(Holtec or applicant) HI-STORM 100 Cask System listing within the
``List of approved spent fuel storage casks'' to include Amendment No.
10 to Certificate of Compliance (CoC) No. 1014. Amendment No. 10 adds
new fuel classes to the contents approved for the loading of 16x16-pin
fuel assemblies into a HI-STORM 100 Cask System; allows a minor
increase in manganese in an alloy material for the system's overpack
and transfer cask; clarifies the minimum water displacement required of
a dummy fuel rod (i.e., a rod not filled with uranium pellets); and
clarifies the design pressures needed for normal operation of forced
helium drying systems. Additionally, Amendment No. 10 revises Condition
[[Page 13266]]
No. 9 of CoC No. 1014 to provide clearer direction on the measurement
of air velocity and modeling of heat distribution through the storage
system. Each of these changes is described in Section IV, ``Discussion
of Changes,'' in the SUPPLEMENTARY INFORMATION section of this
document.
DATES: The direct final rule is effective May 31, 2016, unless
significant adverse comments are received by April 13, 2016. 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 https://www.regulations.gov and search for Docket ID NRC-2015-0270. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Email comments to: Rulemaking.Comments@nrc.gov. 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:
Robert.MacDougall@nrc.gov.
SUPPLEMENTARY INFORMATION:
Table of Contents
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-2015-0270 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 https://www.regulations.gov and search for Docket ID NRC-2015-0270.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at https://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 pdr.resource@nrc.gov. 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-2015-0270 in 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 https://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, then 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. 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 rule is limited to the changes contained in Amendment No. 10
to CoC No. 1014 and does not include other aspects of the Holtec HI-
STORM 100 Cask System design. The NRC is using the ``direct final rule
procedure'' to issue this amendment because it represents a limited and
routine change to an existing CoC that is expected to be
noncontroversial. Adequate protection of public health and safety
continues to be ensured. The amendment to the rule will become
effective on May 31, 2016. However, if the NRC receives significant
adverse comments on this direct final rule by April 13, 2016, 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.
[[Page 13267]]
(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
companion proposed rule published in the Proposed Rule section of this
issue of the Federal Register.
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 ``[the 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
May 1, 2000 (65 FR 25241) that approved the Holtec HI-STORM 100 Cask
System design and added it to the list of NRC-approved cask designs in
10 CFR 72.214 as CoC No. 1014.
IV. Discussion of Changes
On January 5, 2015, Holtec submitted a request to the NRC to amend
CoC No. 1014. Amendment No. 10 (1) adds new fuel classes to the
contents approved for the loading of 16X16-pin fuel assemblies into a
HI-STORM 100 Cask System; (2) allows a minor increase in manganese in
an alloy material for the system's overpack and transfer cask; (3)
clarifies the minimum water displacement required of a dummy fuel rod
(i.e., a rod not filled with uranium pellets); and (4) clarifies the
design pressures expected for normal operation of forced helium drying
systems. Additionally, Amendment No. 10 revises Condition No. 9 of CoC
No. 1014 to provide clearer direction on the measurement of air
velocity and modeling of heat distribution through the storage system.
These changes are further discussed in this section, and the changes to
the affected TS Appendices are identified with revision bars in the
margin of each document.
1. Addition of New 16X16B and 16X16C Fuel Classes to the Contents
Approved for Storage in a HI-STORM 100 Cask System
The contents, enrichment, weight, and dimensions of the new 16X16
fuel assembly classes are all bounded by previously approved 16X16
classes. The NRC staff determined that the applicant's analysis of the
adequacy of the HI-STORM 100 package's shielding for the new fuel
classes supports the conclusion that this shielding evaluation is also
bounded by the previously evaluated classes of 16X16 fuel. From its
criticality evaluations in the safety evaluation report (SER), the NRC
staff also determined that the calculated maximum neutron fluences of
the 16X16B and 16X16C fuel classes are statistically similar to the
already-approved 16X16A fuel class, and both are well bounded by the
design basis fuel. The staff therefore has reasonable assurance that
the new fuel classes are consistent with the appropriate standards for
shielding, criticality, and other required safety analyses, and that
the package design and contents satisfy the radiation protection and
criticality safety requirements in 10 CFR 72.14, 72.124, 72.106, and
72.236.
2. Addition to American Society of Mechanical Engineers (ASME) Boiler
and Pressure Vessel Code Alternative Table To Allow a Newer Alloy
Material
In its request for this amendment, Holtec proposed an additional
exemption to the ASME Boiler and Pressure Vessel Code Alternative Table
to allow the use of more recent Code versions of material SA-516/516A
Grade 70, an alloy like the one used in the overpack and transfer cask
of the HI-STORM 100 Cask System. All SA-516 material used in the HI-
STORM 100 Cask System is required to meet the material composition
described in ASME Boiler and Pressure Vessel Code Section II, 2007
edition. This edition allows for a different manganese content from the
1995 edition, but does not change the structural or thermal properties
of the material. The applicant's request proposed no change in
mechanical properties and no alteration in the form, fit, or function
of these system components resulting from the minor change in
composition of the alloy. The NRC staff therefore finds the requested
exemption acceptable for the affected structures, systems, and
components of CoC No. 1014.
3. Editorial Clarifications
3.a. Clarification of Minimum Displacement of Dummy Fuel Rods
When reactor operators become aware of a damaged or malfunctioning
fuel pin in a fuel assembly, they may remove the assembly from the
reactor core, replace the problem pin with a dummy fuel rod containing
no uranium, and return the assembly to the reactor core to recover the
assembly's remaining energy value. An assembly with a dummy rod may or
may not be considered ``intact'' for handling purposes when it is
finally removed from the reactor core. In Appendix A of the TSs, the
definition of ``Intact Fuel Assemblies'' now clarifies the description
of ``dummy fuel rod'' to specify that it must displace at least the
same amount of water as would a fuel rod in the active fuel region of
the assembly, because criticality safety analyses are based on
displacement of water in that location. Specifically, the definition
states that ``[f]uel assemblies without fuel rods in fuel rod locations
shall not be classified as INTACT FUEL ASSEMBLIES unless dummy fuel
rods are used to displace an amount of water greater than or equal to
that displaced by the fuel rod(s) in the active region [of the fuel
assembly].'' Intact fuel assemblies are by definition those that can be
handled by normal means. In effect, this clarification of the minimum
volume of a dummy rod provides that a fuel assembly with any such rods
may not be handled by normal means unless these rods displace an equal
or greater volume of water than rods containing fuel in the region of
the assembly where there is nuclear material. The greater volume of
fresh (unborated) water displaced by the dummy rod results in
correspondingly less water available to moderate neutrons to a speed
that could sustain a nuclear reaction, and consequently, the greater
displacement will reduce reactivity in an accident involving flooding
with fresh water.
[[Page 13268]]
3.b. Clarification of Helium Pressure Limits for Drying and Backfilling
of Multi-Purpose Canisters (MPCs) in Underground Installations
As indicated in Table 3-1 of Appendix A-100U for HI-STORM 100 Cask
Systems intended for deployment in underground spent fuel storage
installations, use of a closed-loop forced helium dehydration (FHD)
system is an alternative to vacuum drying for an MPC containing
moderate burnup fuel, and FHD is mandatory for drying MPCs with one or
more high burnup fuel assemblies or a higher heat load. Section 3.6.2.2
of Appendix B-100U for HI-STORM Cask Systems was revised to clarify
that the design pressure limit for normal operation of the FHD system
is for drying only and not for backfilling the MPC with helium at lower
pressures for long-term storage.
4. Revised Condition No. 9 of CoC No. 1014
The NRC staff revised Condition No. 9, ``Special Requirements for
First Systems in Place,'' to provide a more appropriate location to
perform air velocity measurements to gauge the cooling effect of air
convection in the dry cask storage system. The previous language in the
CoC required the measurements at the annular gap between the canister
and the overpack. This location is difficult to access, and the
measured data proved to be unreliable because air velocities can vary
chaotically, especially at a location close to the top of the canister.
The revised Condition No. 9 directs the user to make the measurements
at the inlet vents, where the user can obtain the total mass flow rate
of the air and perform a meaningful comparison with predicted results.
The NRC staff also revised Condition No. 9 to specify that
measurements of the Supplemental Cooling System be used to validate the
analytical methods described in the applicant's final safety analysis
report (FSAR) for the cask. The cask user will therefore need to
develop a thermal model of this cask using the analytical methods
described in the FSAR. This will avoid unnecessary approximations in
the thermal model that could add uncertainty in the predicted results.
The revised language more precisely specifies the parameters to be
measured and the analysis necessary to satisfy the Condition.
5. Conclusions
As documented in the SER for Amendment No. 10, the NRC staff
performed a detailed safety evaluation of the proposed CoC amendment
request. There are no significant changes to cask design requirements
in the proposed CoC amendment. 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 would be insignificant. This amendment does not
reflect a significant change in design or fabrication of the cask. In
addition, any resulting changes in occupational exposure or offsite
dose from the implementation of Amendment No. 10 would remain well
within 10 CFR part 20 limits.
Therefore, based on these findings of the SER and those of the
environmental assessment below, the NRC staff concludes that the
proposed CoC changes will not result in any radiological or non-
radiological environmental impacts that differ significantly from the
environmental impacts evaluated in the environmental assessment (EA)
supporting the May 1, 2000, final rule approving CoC No. 1014. There
will be no significant change in the types or amounts of any effluent
released, no significant increase in individual or cumulative radiation
exposures, and no significant increase in the potential for or
consequences of radiological accidents.
This direct final rule revises the Holtec HI-STORM 100 Cask System
listing in 10 CFR 72.214 by adding Amendment No. 10 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 Holtec HI-STORM 100 Cask 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 HI-STORM 100 Cask Systems that meet the criteria of Amendment No.
10 to CoC No. 1014 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 any such standard is inconsistent with applicable law or
otherwise impractical. In this direct final rule, the NRC will revise
the Holtec HI-STORM 100 Cask System design listed in 10 CFR 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, and a
Category ``NRC'' does not confer regulatory authority on the State, the
State may wish to inform its licensees of certain requirements by means
consistent with the particular State's administrative procedure laws.
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
The action is to amend 10 CFR 72.214 to revise the Holtec HI-STORM
100 Cask System listing within the ``List of approved spent fuel
storage casks'' to include Amendment No. 10 to CoC No. 1014. Under the
National Environmental Policy Act of 1969, as amended (NEPA), 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
(EIS) is not required. The NRC has made a finding of no significant
impact on the basis of this EA.
[[Page 13269]]
B. The Need for the Action
This direct final rule is needed to allow users of HI-STORM 100
Cask Systems under Amendment No. 10 to load for dry storage under a
general license additional classes of fuel assemblies that would
otherwise have to remain in spent fuel storage pools. This direct final
rule amends the CoC for the Holtec HI-STORM 100 Cask System 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.
Specifically, Amendment No. 10 (1) adds new fuel classes to the
contents approved for the loading of 16X16-pin fuel assemblies into a
HI-STORM 100 Cask System; (2) allows a minor increase in manganese in
an alloy material for the system's overpack and transfer cask; (3)
clarifies the minimum water displacement required of a dummy fuel rod
(i.e., a rod not filled with uranium pellets); and (4) clarifies the
design pressures expected for normal operation of forced helium drying
systems. Additionally, Amendment No. 10 revises Condition No. 9 of CoC
No. 1014 to provide clearer direction on the measurement of air
velocity and modeling of heat distribution through the storage system.
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 EA for the 1990 final rule. The EA for Amendment No. 10
tiers off of the EA for the July 18, 1990, final rule. Tiering on past
EAs is a standard process under NEPA by which impact analyses in a
previous EA can be cited by a subsequent EA as bounding the expected
impacts of a new proposed action within the scope of the previous EA.
The Holtec HI-STORM 100 Cask System is 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 Independent Spent Fuel Storage
Installation, 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 proposed CoC amendment does not reflect a
significant change in cask design or fabrication requirements. Because
there are no significant design or production process changes, any
resulting occupational exposure or offsite dose rates from the
implementation of Amendment No. 10 would remain well within all
applicable 10 CFR part 20 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 EA supporting the July 18, 1990, final rule. There
will be no significant change in the types or amounts of any effluent
released, no significant increase in individual or cumulative radiation
exposures, and no significant increase in the potential for or
consequences of radiological accidents. The NRC staff documented these
safety findings in the SER.
D. Alternative to the Action
The alternative to this action is to deny approval of Amendment No.
10 and withdraw the direct final rule. Consequently, any 10 CFR part 72
general licensee that seeks to load spent nuclear fuel into the Holtec
HI-STORM 100 Cask System in accordance with the changes described in
proposed Amendment No. 10 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. The
environmental impacts of this alternative would therefore be the same
as or greater than the preferred action.
E. Alternative Use of Resources
Approval of Amendment No. 10 to CoC No. 1014 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 EA.
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 EA, the NRC
concludes that this direct final rule entitled, ``List of Approved
Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask
System; Certificate of Compliance No. 1014, Amendment No. 10,'' will
not have a significant effect on the human environment. Therefore, the
NRC has determined that an EIS for this direct final rule is not
necessary.
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. 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 May 1, 2000 (65 FR 25241),
the NRC issued an amendment to 10 CFR part 72 that approved the Holtec
HI-STORM 100 Cask System design by adding it to the list of NRC-
approved cask designs in 10 CFR 72.214.
[[Page 13270]]
On January 5, 2015, Holtec submitted an application to amend the
HI-STORM 100 Cask System CoC as described in Section IV, ``Discussion
of Changes,'' of this document.
The alternative to this action is to withhold approval of Amendment
No. 10 and require any 10 CFR part 72 general licensee seeking to load
spent nuclear fuel into the Holtec HI-STORM 100 Cask System under the
changes described in Amendment No. 10 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 EA, 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 on or benefit to 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
The NRC has determined that the backfit rule (10 CFR 72.62) does
not apply to this direct final rule. Therefore, a backfit analysis is
not required. This direct final rule revises CoC No. 1014 for the
Holtec HI-STORM 100 Cask System, as currently listed in 10 CFR 72.214,
``List of approved spent fuel storage casks.'' The revision consists of
Amendment No. 10, which (1) adds new fuel classes to the contents
approved for the loading of 16X16-pin fuel assemblies into a HI-STORM
100 Cask System; (2) allows a minor increase in manganese in an alloy
material for the system's overpack and transfer cask; (3) clarifies the
minimum water displacement required of a dummy fuel rod (i.e., a rod
not filled with uranium pellets); and (4) clarifies the design
pressures expected for normal operation of forced helium drying
systems. Additionally, Amendment No. 10 revises Condition No. 9 of CoC
No. 1014 to provide clearer direction on the measurement of air
velocity and modeling of heat distribution through the storage system.
Amendment No. 10 to CoC No. 1014 for the Holtec HI-STORM 100 Cask
System was initiated by Holtec, and was not submitted in response to
new NRC requirements or an NRC request for amendment. Amendment No. 10
applies only to new casks fabricated and used under Amendment No. 10.
These changes do not affect existing users of the Holtec HI-STORM 100
Cask System; the current Amendment No. 9 and earlier amendments
continue to be effective for existing users. While current CoC users
may comply with the new requirements in Amendment No. 10, this would be
a voluntary decision on the part of current users. For these reasons,
Amendment No. 10 to CoC No. 1014 does not constitute backfitting under
10 CFR 72.62, 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. Accordingly, no backfit analysis or
additional documentation addressing the issue finality criteria in 10
CFR part 52 has been prepared by the NRC staff.
XIII. Congressional Review Act
The Office of Management and Budget has not found this to be a
major rule as defined in the Congressional Review Act.
XIV. Availability of Documents
The documents identified in the following table are available to
interested persons as indicated.
------------------------------------------------------------------------
Document ADAMS Accession No.
------------------------------------------------------------------------
Holtec International HI-STORM 100 Cask ML15007A435.
System--License Amendment Request (1014-
10).
Proposed CoC No. 1014, Amendment No. 10... ML15331A307.
Appendix A for Proposed CoC No. 1014, ML15331A310.
Amendment No. 10.
Appendix B for Proposed CoC No. 1014, ML15331A311.
Amendment No. 10.
Appendix A--100U for Proposed CoC No. ML15331A312.
1014, Amendment No. 10.
Appendix B--100U for Proposed CoC No. ML15331A313.
1014, Amendment No. 10.
Preliminary SER for Proposed CoC No. 1014, ML15331A309.
Amendment No. 10.
------------------------------------------------------------------------
The NRC may post materials related to this document, including
public comments, on the Federal Rulemaking Web site at https://www.regulations.gov under Docket ID NRC-2015-0270. 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-2015-0270); (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,
Hazardous waste, Indians, Intergovernmental relations, Manpower
training programs, Nuclear energy, 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 of 1954, 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, 2210e,
2232, 2233, 2234, 2236, 2237, 2238, 2273, 2282, 2021); Energy
Reorganization Act of 1974, secs. 201, 202, 206, 211 (42 U.S.C.
5841, 5842, 5846, 5851); National Environmental Policy Act of 1969
(42 U.S.C. 4332); Nuclear Waste Policy Act of 1982, secs. 117(a),
132, 133, 134, 135, 137,
[[Page 13271]]
141, 145(g), 148, 218(a) (42 U.S.C. 10137(a), 10152, 10153, 10154,
10155, 10157, 10161, 10165(g), 10168, 10198(a)) 44 U.S.C. 3504 note.
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 Number: 1014.
Initial Certificate Effective Date: May 31, 2000.
Amendment Number 1 Effective Date: July 15, 2002.
Amendment Number 2 Effective Date: June 7, 2005.
Amendment Number 3 Effective Date: May 29, 2007.
Amendment Number 4 Effective Date: January 8, 2008.
Amendment Number 5 Effective Date: July 14, 2008.
Amendment Number 6 Effective Date: August 17, 2009.
Amendment Number 7 Effective Date: December 28, 2009.
Amendment Number 8 Effective Date: May 2, 2012, as corrected on
November 16, 2012 (ADAMS Accession No. ML12213A170).
Amendment Number 9 Effective Date: March 11, 2014.
Amendment Number 10 Effective Date: May 31, 2016.
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 2nd day of March, 2016.
For the Nuclear Regulatory Commission.
Victor M. McCree,
Executive Director of Operations.
[FR Doc. 2016-05711 Filed 3-11-16; 8:45 am]
BILLING CODE 7590-01-P
