[Federal Register Volume 83, Number 204 (Monday, October 22, 2018)]
[Rules and Regulations]
[Pages 53159-53163]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-22912]
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Rules and Regulations
Federal Register
________________________________________________________________________
This section of the FEDERAL REGISTER contains regulatory documents
having general applicability and legal effect, most of which are keyed
to and codified in the Code of Federal Regulations, which is published
under 50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by the Superintendent of Documents.
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Federal Register / Vol. 83, No. 204 / Monday, October 22, 2018 /
Rules and Regulations
[[Page 53159]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2018-0075]
RIN 3150-AK12
List of Approved Spent Fuel Storage Casks: NAC International NAC-
UMS[supreg] Universal Storage System, Certificate of Compliance; No.
1015, Amendment No. 6
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 NAC International NAC-
UMS[supreg] listing within the ``List of approved spent fuel storage
casks'' to include Amendment No. 6 to Certificate of Compliance (CoC)
No. 1015. Amendment No. 6 revises the CoC's technical specifications
(TSs) to: Remove a redundant requirement for inspection of the concrete
cask and canister; revise a limiting condition of operation (LCO) for
heat removal to clarify that ``LCO not met'' means that the concrete
heat removal system is inoperable; remove an inspection requirement
that is already covered by LCO surveillance requirements for off-
normal, accident, or natural phenomenon events; and clarify that
``immediate'' restoration of a concrete cask's heat removal
capabilities means ``within the design-basis time limit'' in Section
11.2.13 of the Final Safety Analysis Report (FSAR), ``or within the
time limit for a less than design-basis heat load case, as evaluated.''
Amendment No. 6 also clarifies that an LCO for loaded cask surface dose
rates applies prior to storage conditions, when dose rates will be
highest.
DATES: This direct final rule is effective January 7, 2019, unless
significant adverse comments are received by November 21, 2018. If this
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 NRC 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:
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0075. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions contact
the individuals 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: Bernard H. White, Office of Nuclear
Material Safety and Safeguards; telephone: 301-415-6577; email:
[email protected] or Robert D. MacDougall, Office of Nuclear
Material Safety and Safeguards; telephone: 301-415-5175; email:
[email protected]. Both are staff of the U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Obtaining Information and Submitting Comments
II. Rulemaking Procedure
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-2018-0075 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 Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0075.
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-2018-0075 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 http:/
/
[[Page 53160]]
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. Rulemaking Procedure
This direct final rule is limited to the changes contained in
Amendment No. 6 to CoC No. 1015 and does not include other aspects of
the NAC-UMS[supreg] Universal Storage 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 January 7, 2019. However, if the NRC receives
significant adverse comments on this direct final rule by November 21,
2018, 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
Rules 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 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.
(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 to make a change (other than
editorial) to the rule, CoC, or TSs.
For detailed instructions on filing comments, please see the
companion proposed rule published in the Proposed Rules 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 [U.S. Nuclear Regulatory] Commission may, by
rule, approve for use at the sites of civilian nuclear power reactors
without, to the maximum extent practicable, the need for additional
site-specific approvals by the Commission.'' Section 133 of the NWPA
states, in part, that ``[the Commission] shall, by rule, establish
procedures for the licensing of any technology approved by the
Commission under Section 219(a) [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 that 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 19, 2000 (65 FR 62581), that approved the NAC-UMS[supreg]
Universal Storage System design and added it to the list of NRC-
approved cask designs provided in Sec. 72.214 as CoC No. 1015.
IV. Discussion of Changes
On May 23, 2017, NAC International submitted a request to the NRC
to amend CoC No. 1015. NAC International supplemented its request on
January 16, 2018. Amendment No. 6 revises the CoC's TSs to: (1) Remove
a redundant requirement for inspection of the concrete cask and
canister; (2) revise an LCO for heat removal to clarify that ``LCO not
met'' means that the concrete heat removal system is inoperable; (3)
remove an inspection requirement that is already covered by LCO
surveillance requirements for off-normal, accident, or natural
phenomenon events; (4) clarify that ``immediate'' restoration of a
concrete cask's heat removal capabilities means ``within the design-
basis time limit'' in Section 11.2.13 of the FSAR, ``or within the time
limit for a less than design-basis heat load case, as evaluated''; and
(5) clarify that an LCO for loaded cask surface dose rates applies
prior to storage conditions, when dose rates will be highest.
As documented in the preliminary safety evaluation report (PSER),
the NRC performed a safety review 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 in the
event of an accident. This amendment 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. 6 would remain well within the 10 CFR part 20 limits.
There will be no significant change in the types or amounts of any
effluent released, no significant increase in the individual or
cumulative radiation exposure, and no significant increase in the
potential for, or consequences from, radiological accidents.
This direct final rule revises the NAC-UMS[supreg] System listing
in Sec. 72.214 by adding Amendment No. 6 to CoC No. 1015. The
amendment consists of the changes previously described, as set forth in
the revised CoC and TSs. The revised TSs are identified and evaluated
in the PSER.
The amended NAC-UMS[supreg] cask design, when used under the
conditions specified in the CoC, the TSs, and the NRC's regulations,
will meet the requirements of 10 CFR part 72; 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 Sec. 72.210 may, consistent with the license
conditions under Sec. 72.212, load spent nuclear fuel into those NAC-
UMS[supreg] Universal Storage System casks that meet the
[[Page 53161]]
criteria of Amendment No. 6 to CoC No. 1015.
V. Voluntary Consensus Standards
The National Technology Transfer and Advancement Act of 1995 (Pub.
L. 104-113) requires that Federal agencies use technical standards that
are developed or adopted by voluntary consensus standards bodies unless
the use of such a standard is inconsistent with applicable law or
otherwise impractical. In this direct final rule, the NRC will revise
the NAC-UMS[supreg] Universal Storage System design listed in Sec.
72.214. 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 the
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 Sec. 72.214 to revise the NAC International
NAC-UMS[supreg] Universal Storage System listing of casks that power
reactor licensees can use for dry storage of spent fuel at reactor
sites under a general license. This direct final rule amends the
listing to add Amendment No. 6 to CoC No. 1015. Specifically, Amendment
No. 6 revises the CoC's TSs to: (1) Remove a redundant requirement for
inspection of the concrete cask and canister; (2) revise an LCO for
heat removal to clarify that ``LCO not met'' means that the concrete
heat removal system is inoperable; (3) remove an inspection requirement
that is already covered by LCO surveillance requirements for off-
normal, accident, or natural phenomenon events; (4) clarify that
``immediate'' restoration of a concrete cask's heat removal
capabilities means ``within the design-basis time limit'' in Section
11.2.13 of the FSAR, ``or within the time limit for a less than design-
basis heat load case, as evaluated''; and (5) clarify that an LCO for
loaded cask surface dose rates applies prior to storage conditions,
when dose rates will be highest.
B. The Need for the Action
This direct final rule amends the CoC for the NAC-UMS[supreg]
Universal Storage 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. 6
clarifies and removes redundancies in requirements for the use of the
NAC-UMS[supreg] Universal Storage System. The amendment facilitates the
dry cask storage of spent fuel that might otherwise have to be stored
in the affected power reactors' 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 (EA) for the 1990 final rule.
The EA for this Amendment No. 6 tiers off of the EA for the July 18,
1990, final rule. Tiering off past EAs is a standard process under the
National Environmental Policy Act of 1969, as amended (NEPA).
NAC-UMS[supreg] Universal Storage 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 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 events.
Considering the specific design requirements for each accident
condition, the design of the cask would prevent loss of confinement,
shielding, and criticality control in the event of an accident. If
there is no loss of confinement, shielding, or criticality control, the
environmental impacts resulting from an accident would be
insignificant. This amendment does not reflect a significant change in
design or fabrication of the cask. Because there are no significant
design or process changes, any resulting occupational exposure or
offsite dose rates from the implementation of Amendment No. 6 would
remain well within 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 documented its
safety findings in a PSER.
D. Alternative to the Action
The alternative to this action is to deny approval of Amendment No.
6 and end the direct final rule. Consequently, any 10 CFR part 72
general licensee that seeks to load spent nuclear fuel into NAC
International NAC-UMS[supreg] Universal Storage Systems in accordance
with the changes described in proposed Amendment No. 6 would have to
request an exemption from the requirements of Sec. Sec. 72.212 and
72.214. Under this alternative, interested licensees 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. Therefore, the environmental impacts of the
alternative action would be the same as, or more likely greater than,
the preferred action.
E. Alternative Use of Resources
Approval of Amendment No. 6 to CoC No. 1015 would result in no
irreversible commitment of resources.
F. Agencies and Persons Contacted
No agencies or persons outside the NRC were contacted in connection
with the preparation of this EA.
[[Page 53162]]
G. Finding of No Significant Impact
The environmental impacts of the action have been reviewed under
the requirements in NEPA, and the NRC's regulations in subpart A of 10
CFR part 51, ``Environmental Protection Regulations for Domestic
Licensing and Related Regulatory Functions.'' Based on the foregoing
EA, the NRC concludes that this direct final rule entitled, ``List of
Approved Spent Fuel Storage Casks: NAC International NAC-UMS[supreg]
Universal Storage System, Certificate of Compliance No. 1015, Amendment
No. 6'' 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 direct final rule does not contain any new or amended
collections of information subject to the Paperwork Reduction Act of
1995 (44 U.S.C. 3501 et seq.). Existing collections of information were
approved by the Office of Management and Budget (OMB), approval number
3150-0132.
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to
respond to a request for information or an information collection
requirement unless the requesting document displays a currently valid
OMB control number.
X. Regulatory Flexibility Certification
Under the Regulatory Flexibility Act of 1980 (5 U.S.C. 605(b)), the
NRC certifies that this direct final 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
NAC International. These entities do not fall within the scope of the
definition of small entities set forth in the Regulatory Flexibility
Act or the size standards established by the NRC (Sec. 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 Sec. 72.214. On October 19, 2000 (65 FR
62581), the NRC issued an amendment to 10 CFR part 72 that approved the
NAC-UMS[supreg] Universal Storage System design by adding it to the
list of NRC-approved cask designs in Sec. 72.214.
On May 23, 2017, and as supplemented on January 16, 2018, NAC
International submitted an application to amend the NAC-UMS[supreg]
Universal Storage System as described in Section IV, ``Discussion of
Changes,'' of this document.
The alternative to this action is to withhold approval of Amendment
No. 6 and to require any 10 CFR part 72 general licensee seeking to
load spent nuclear fuel into NAC International NAC-UMS[supreg]
Universal Storage Systems under the changes described in Amendment No.
6 to request an exemption from the requirements of Sec. Sec. 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 this direct final rule is consistent with previous NRC
actions. Further, as documented in the PSER and EA, this 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 this
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 actions in this direct final rule
do not require a backfit analysis because they either do not fall
within the definition of backfitting under Sec. 72.62 or Sec.
50.109(a)(1), or they do not impact any general licensees currently
using these systems. Additionally, the actions in this direct final
rule do not impact issue finality provisions applicable to combined
licenses under 10 CFR part 52.
This direct final rule revises CoC No. 1015 for the NAC
International NAC-UMS[supreg] Universal Storage System, as currently
listed in Sec. 72.214. The revision consists of Amendment No. 6, which
revises the CoC's TSs to: (1) Remove a redundant requirement for
inspection of the concrete cask and canister; (2) revise an LCO for
heat removal to clarify that ``LCO not met'' means that the concrete
heat removal system is inoperable; (3) remove an inspection requirement
that is already covered by LCO surveillance requirements for off-
normal, accident, or natural phenomenon events; (4) clarify that
``immediate'' restoration of a concrete cask's heat removal
capabilities means ``within the design-basis time limit'' in Section
11.2.13 of the FSAR, ``or within the time limit for a less than design-
basis heat load case, as evaluated''; and (5) clarify that an LCO for
loaded cask surface dose rates applies prior to storage conditions,
when dose rates will be highest.
Amendment No. 6 to CoC No. 1015 for the NAC International NAC-
UMS[supreg] Universal Storage System was initiated by NAC International
and was not submitted in response to new NRC requirements, or an NRC
request for amendment. Amendment No. 6 applies only to new casks
fabricated and used under Amendment No. 6. These changes do not affect
existing users of the NAC International NAC-UMS[supreg] Universal
Storage System, and the current Amendment No. 5 continues to be
effective for existing users. While current CoC users may comply with
the new requirements in Amendment No. 6, this would be a voluntary
decision on the part of current users.
For these reasons, Amendment No. 6 to CoC No. 1015 does not
constitute backfitting under Sec. 72.62 or Sec. 50.109(a)(1), or
otherwise represent an inconsistency with the issue finality provisions
applicable to combined licenses in 10 CFR part 52. Accordingly, the NRC
has not prepared a backfit analysis for this rulemaking.
XIII. Congressional Review Act
This direct final rule is not a rule as defined in the
Congressional Review Act.
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.
[[Page 53163]]
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ADAMS accession No./web link/
Document Federal Register citation
------------------------------------------------------------------------
Request to Amend Certificate of ML17145A380
Compliance No. 1015 for the NAC-
UMS[supreg] Cask System, dated May
23, 2017.
Revision of Request to Amend ML18018A893
Certificate of Compliance No. 1015
for the NAC-UMS[supreg] Cask System,
dated January 16, 2018.
Revision 11 to NAC-UMS[supreg] Final ML16341B102
Safety Analysis Report for the UMS
Universal Storage System.
Proposed CoC No. 1015, Amendment No. 6 ML18088A174
Proposed Technical Specifications, ML18088A176
Appendix A.
Proposed Technical Specifications, ML18088A178
Appendix B.
Preliminary Safety Evaluation Report.. ML18088A181
------------------------------------------------------------------------
The NRC may post materials related to this document, including
public comments, on the Federal Rulemaking website at http://www.regulations.gov under Docket ID NRC-2018-0075. The Federal
Rulemaking website allows you to receive alerts when changes or
additions occur in a docket folder. To subscribe: (1) Navigate to the
docket folder (NRC-2018-0075); (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, Hazardous waste, Indians,
Intergovernmental relations, Nuclear energy, Penalties, Radiation
protection, Reporting and recordkeeping requirements, Security
measures, 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, 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 1015 is revised to read
as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1015.
Initial Certificate Effective Date: November 20, 2000.
Amendment Number 1 Effective Date: February 20, 2001.
Amendment Number 2 Effective Date: December 31, 2001.
Amendment Number 3 Effective Date: March 31, 2004.
Amendment Number 4 Effective Date: October 11, 2005.
Amendment Number 5 Effective Date: January 12, 2009.
Amendment Number 6 Effective Date: January 7, 2019.
SAR Submitted by: NAC International, Inc.
SAR Title: Final Safety Analysis Report for the NAC-UMS Universal
Storage System.
Docket Number: 72-1015.
Certificate Expiration Date: November 20, 2020.
Model Number: NAC-UMS.
* * * * *
Dated at Rockville, Maryland, this 9th day of October 2018.
For the Nuclear Regulatory Commission.
Margaret M. Doane,
Executive Director for Operations.
[FR Doc. 2018-22912 Filed 10-19-18; 8:45 am]
BILLING CODE 7590-01-P