List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Multipurpose Canister Cask System, Certificate of Compliance No. 1014, Amendment No. 14, 67827-67828 [2019-26691]
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Rules and Regulations
Federal Register
Vol. 84, No. 239
Thursday, December 12, 2019
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.
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 72
[NRC–2019–0160]
RIN 3150–AK36
List of Approved Spent Fuel Storage
Casks: Holtec International HI–STORM
100 Multipurpose Canister Cask
System, Certificate of Compliance No.
1014, Amendment No. 14
Nuclear Regulatory
Commission.
ACTION: Direct final rule; confirmation of
effective date.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is confirming the
effective date of December 17, 2019, for
the direct final rule that was published
in the Federal Register on October 3,
2019. This direct final rule amended the
NRC’s spent fuel storage regulations by
revising the Holtec International HI–
STORM 100 Multipurpose Canister Cask
System listing within the ‘‘List of
approved spent fuel storage casks’’ to
include Amendment No. 14 to
Certificate of Compliance No. 1014.
Amendment No. 14 revised the
technical specifications to add new heat
loading patterns, reduce the minimum
cooling time, allow use of a damaged
fuel isolator for storing damaged fuel,
and modify the description of vents in
the overpack. Amendment No. 14 also
made other administrative changes to
the technical specifications.
DATES: The effective date of December
17, 2019, for the direct final rule
published on October 3, 2019 (84 FR
52747), is confirmed.
ADDRESSES: Please refer to Docket ID
NRC–2019–0160 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:
khammond on DSKJM1Z7X2PROD with RULES
SUMMARY:
VerDate Sep<11>2014
16:05 Dec 11, 2019
Jkt 250001
• Federal Rulemaking website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2019–0160. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• 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
‘‘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. The proposed amendment to
the certificate, the proposed changes to
the technical specifications, and the
preliminary safety evaluation report are
available in ADAMS under Accession
No. ML19120A076. The final
amendment to the certificate, the final
changes to the technical specifications,
and the final safety evaluation report
also can be viewed in ADAMS under
Accession No. ML19295C567.
• 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.
FOR FURTHER INFORMATION CONTACT: YenJu Chen, Office of Nuclear Material
Safety and Safeguards; telephone: 301–
415–1018; email: Yen-Ju.Chen@nrc.gov
or Torre Taylor, Office of Nuclear
Material Safety and Safeguards;
telephone: 301–415–7900; email:
Torre.Taylor@nrc.gov. Both are staff of
the U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
SUPPLEMENTARY INFORMATION: On
October 3, 2019 (84 FR 52747), the NRC
published a direct final rule amending
its regulations in part 72 of title 10 of
the Code of Federal Regulations (10
CFR) by revising the ‘‘List of approved
spent fuel storage casks’’ to include
Amendment No. 14 to Certificate of
Compliance No. 1014 for the Holtec
International HI–STORM 100
Multipurpose Canister Cask System (HI–
STORM 100 Cask System). Amendment
No. 14 revised the technical
PO 00000
Frm 00001
Fmt 4700
Sfmt 4700
specifications to add new heat loading
patterns, reduce the minimum cooling
time, allow use of a damaged fuel
isolator for storing damaged fuel, and
modify the description of vents in the
overpack. Amendment No. 14 also made
other administrative changes to the
technical specifications.
In the direct final rule, the NRC stated
that if no significant adverse comments
were received, the direct final rule
would become effective on December
17, 2019. The NRC received one
comment (ADAMS Accession No.
ML19309E185). The commenter asked
whether the NRC independently
verified that the amended certificate
will continue to protect public health,
safety, and the environment and
whether the HI–STORM 100 Cask
System, as approved on May 1, 2000,
continues to meet all requirements in 10
CFR 72.214 as outlined in Certificate of
Compliance No. 1014. The NRC
evaluated the comment against the
criteria for withdrawing the direct final
rule as described in the proposed rule
(84 FR 52815; October 3, 2019) and
determined it was not significant and
adverse. Specifically, the commenter
did not provide new information that
would cause the NRC to reevaluate its
position in the preliminary safety
evaluation report (ADAMS Accession
No. ML19120A064). The commenter did
not provide information that would
cause the NRC to conduct additional
analyses nor did the commenter raise a
serious issue that warrants an NRC
response to complete the record. The
commenter also did not raise any issues
that have not been previously
addressed. In addition, the commenter
did not propose a change, without
which the rule would be ineffective or
unacceptable.
The NRC’s safety evaluation report
provides the NRC’s review and
assessment of Holtec’s proposed
changes and the independent
calculations that the NRC performed to
verify Holtec’s analyses. The final safety
analysis report provided by Holtec, and
reviewed by the NRC, evaluates generic
site characteristics. Any general licensee
proposing to use Amendment No. 14 to
the HI–STORM 100 Cask System will
have to ensure, as required by 10 CFR
72.212(b)(6), that its site characteristics
are enveloped by the cask design bases
evaluated for Amendment No. 14. The
NRC confirmed that Holtec’s evaluation
E:\FR\FM\12DER1.SGM
12DER1
67828
Federal Register / Vol. 84, No. 239 / Thursday, December 12, 2019 / Rules and Regulations
of Amendment No. 14 shows that the
use of the damaged fuel isolators and
new heat loads will not impair the
ability of the storage cask to maintain
confinement and subcriticality.
Additionally, the off-site dose rates will
meet the dose requirements in 10 CFR
72.236(d).
As discussed in the environmental
assessment for the direct final rule,
Amendment No. 14 does not reflect a
significant change in design or
fabrication of the cask; therefore, any
resulting occupational exposure or
offsite dose rates would remain well
within the 10 CFR part 20 annual limits
for public and occupational radiological
doses. Additionally, Amendment No. 14
will not result in any radiological or
non-radiological environmental impacts
that significantly differ from the
environmental impacts evaluated in the
environmental assessment supporting
the final rule, ‘‘Storage of Spent Fuel in
NRC-Approved Storage Casks at Power
Reactor Sites’’ (55 FR 29181; July 18,
1990). There will be no significant
change in the types of, or significant
revisions in the amounts of, any effluent
released; no significant increase in the
individual or cumulative radiation
exposures; and no significant increase
in the potential for, or consequences of,
radiological accidents. Therefore, this
direct final rule will become effective as
scheduled.
Dated at Rockville, Maryland, this 6th day
of December 2019.
For the Nuclear Regulatory Commission.
Pamela J. Shepherd-Vladimir,
Acting Chief, Regulatory Analysis and
Rulemaking Support Branch, Division of
Rulemaking, Environmental and Financial
Support, Office of Nuclear Material Safety
and Safeguards.
[FR Doc. 2019–26691 Filed 12–11–19; 8:45 am]
BILLING CODE 7590–01–P
DEPARTMENT OF TRANSPORTATION
Federal Aviation Administration
14 CFR Part 25
khammond on DSKJM1Z7X2PROD with RULES
[Docket No. FAA–2019–0851; Special
Conditions No. 25–763–SC]
Special Conditions: VT DRB Aviation
Consultants, Airbus Model A330–300
Airplanes; Dynamic Test Requirements
for Single-Occupant, Oblique (SideFacing) Seats With or Without Airbag
Devices or 3-Point Restraints
Federal Aviation
Administration (FAA), DOT.
ACTION: Final special conditions; request
for comments.
AGENCY:
VerDate Sep<11>2014
16:05 Dec 11, 2019
Jkt 250001
These special conditions are
issued for the Airbus Model A330–300
airplane. This airplane, as modified by
VT DRB Aviation Consultants (VT DRB),
will have novel or unusual design
features when compared to the state of
technology envisioned in the
airworthiness standards for transportcategory airplanes. This design feature
is single-occupant, oblique (side-facing)
seats with airbag devices or 3-point
restraints. The applicable airworthiness
regulations do not contain adequate or
appropriate safety standards for this
design feature. These special conditions
contain the additional safety standards
that the Administrator considers
necessary to establish a level of safety
equivalent to that established by the
existing airworthiness standards.
DATES: This action is effective on VT
DRB on December 12, 2019. Send
comments on or before January 27,
2020.
SUMMARY:
Send comments identified
by Docket No. FAA–2019–0851 using
any of the following methods:
• Federal eRegulations Portal: Go to
https://www.regulations.gov/ and follow
the online instructions for sending your
comments electronically.
• Mail: Send comments to Docket
Operations, M–30, U.S. Department of
Transportation (DOT), 1200 New Jersey
Avenue SE, Room W12–140, West
Building Ground Floor, Washington, DC
20590–0001.
• Hand Delivery or Courier: Take
comments to Docket Operations in
Room W12–140 of the West Building
Ground Floor at 1200 New Jersey
Avenue SE, Washington, DC, between 9
a.m. and 5 p.m., Monday through
Friday, except Federal holidays.
• Fax: Fax comments to Docket
Operations at 202–493–2251.
Privacy: The FAA will post all
comments it receives, without change,
to https://www.regulations.gov/,
including any personal information the
commenter provides. Using the search
function of the docket website, anyone
can find and read the electronic form of
all comments received into any FAA
docket, including the name of the
individual sending the comment (or
signing the comment for an association,
business, labor union, etc.). DOT’s
complete Privacy Act Statement can be
found in the Federal Register published
on April 11, 2000 (65 FR 19477–19478).
Docket: Background documents or
comments received may be read at
https://www.regulations.gov/ at any time.
Follow the online instructions for
accessing the docket or go to Docket
Operations in Room W12–140 of the
West Building Ground Floor at 1200
ADDRESSES:
PO 00000
Frm 00002
Fmt 4700
Sfmt 4700
New Jersey Avenue SE, Washington,
DC, between 9 a.m. and 5 p.m., Monday
through Friday, except Federal holidays.
FOR FURTHER INFORMATION CONTACT:
Alan Sinclair, Airframe and Cabin
Safety Section, AIR–675, Transport
Standards Branch, Policy and
Innovation Division, Aircraft
Certification Service, Federal Aviation
Administration, 2200 South 216th
Street, Des Moines, Washington 98198;
telephone and fax 206–231–3215; email
alan.sinclair@faa.gov.
SUPPLEMENTARY INFORMATION: The FAA
has determined that notice of, and
opportunity for prior public comment
on, these special conditions is
impracticable because these procedures
would significantly delay issuance of
the design approval and thus delivery of
the affected airplanes.
In addition, the substance of these
special conditions has been published
in the Federal Register for public
comment in several prior instances with
no substantive comments received.
Therefore, the FAA has determined that
prior public notice and comment are
unnecessary, and finds that, for the
same reason, good cause exists for
adopting these special conditions upon
publication in the Federal Register.
Comments Invited
The FAA invites interested people to
take part in this rulemaking by sending
written comments, data, or views. The
most helpful comments reference a
specific portion of the special
conditions, explain the reason for any
recommended change, and include
supporting data.
The FAA will consider all comments
received by the closing date for
comments. The FAA may change these
special conditions based on the
comments received.
Background
On October 12, 2018, VT DRB applied
for a supplemental type certificate for
oblique (side-facing) single-occupant
seats equipped with airbag devices or 3point restraints in Airbus Model A330–
300 airplanes. The Airbus Model A330–
300 airplane is a twin-engine, transportcategory airplane with a maximum
takeoff weight of 533,518 pounds and
seating for 297 passengers.
Type Certification Basis
Under the provisions of title 14, Code
of Federal Regulations (14 CFR) 21.101,
VT DRB must show that the Airbus
Model A330–300 airplane, as changed,
continues to meet the applicable
provisions of the regulations listed in
Type Certificate No. A46NM or the
applicable regulations in effect on the
E:\FR\FM\12DER1.SGM
12DER1
Agencies
[Federal Register Volume 84, Number 239 (Thursday, December 12, 2019)]
[Rules and Regulations]
[Pages 67827-67828]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-26691]
========================================================================
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.
========================================================================
Federal Register / Vol. 84, No. 239 / Thursday, December 12, 2019 /
Rules and Regulations
[[Page 67827]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2019-0160]
RIN 3150-AK36
List of Approved Spent Fuel Storage Casks: Holtec International
HI-STORM 100 Multipurpose Canister Cask System, Certificate of
Compliance No. 1014, Amendment No. 14
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule; confirmation of effective date.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is confirming the
effective date of December 17, 2019, for the direct final rule that was
published in the Federal Register on October 3, 2019. This direct final
rule amended the NRC's spent fuel storage regulations by revising the
Holtec International HI-STORM 100 Multipurpose Canister Cask System
listing within the ``List of approved spent fuel storage casks'' to
include Amendment No. 14 to Certificate of Compliance No. 1014.
Amendment No. 14 revised the technical specifications to add new heat
loading patterns, reduce the minimum cooling time, allow use of a
damaged fuel isolator for storing damaged fuel, and modify the
description of vents in the overpack. Amendment No. 14 also made other
administrative changes to the technical specifications.
DATES: The effective date of December 17, 2019, for the direct final
rule published on October 3, 2019 (84 FR 52747), is confirmed.
ADDRESSES: Please refer to Docket ID NRC-2019-0160 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 https://www.regulations.gov and search for Docket ID NRC-2019-0160. 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.
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 ``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]. The proposed amendment to the
certificate, the proposed changes to the technical specifications, and
the preliminary safety evaluation report are available in ADAMS under
Accession No. ML19120A076. The final amendment to the certificate, the
final changes to the technical specifications, and the final safety
evaluation report also can be viewed in ADAMS under Accession No.
ML19295C567.
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.
FOR FURTHER INFORMATION CONTACT: Yen-Ju Chen, Office of Nuclear
Material Safety and Safeguards; telephone: 301-415-1018; email: [email protected] or Torre Taylor, Office of Nuclear Material Safety and
Safeguards; telephone: 301-415-7900; email: [email protected]. Both
are staff of the U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
SUPPLEMENTARY INFORMATION: On October 3, 2019 (84 FR 52747), the NRC
published a direct final rule amending its regulations in part 72 of
title 10 of the Code of Federal Regulations (10 CFR) by revising the
``List of approved spent fuel storage casks'' to include Amendment No.
14 to Certificate of Compliance No. 1014 for the Holtec International
HI-STORM 100 Multipurpose Canister Cask System (HI-STORM 100 Cask
System). Amendment No. 14 revised the technical specifications to add
new heat loading patterns, reduce the minimum cooling time, allow use
of a damaged fuel isolator for storing damaged fuel, and modify the
description of vents in the overpack. Amendment No. 14 also made other
administrative changes to the technical specifications.
In the direct final rule, the NRC stated that if no significant
adverse comments were received, the direct final rule would become
effective on December 17, 2019. The NRC received one comment (ADAMS
Accession No. ML19309E185). The commenter asked whether the NRC
independently verified that the amended certificate will continue to
protect public health, safety, and the environment and whether the HI-
STORM 100 Cask System, as approved on May 1, 2000, continues to meet
all requirements in 10 CFR 72.214 as outlined in Certificate of
Compliance No. 1014. The NRC evaluated the comment against the criteria
for withdrawing the direct final rule as described in the proposed rule
(84 FR 52815; October 3, 2019) and determined it was not significant
and adverse. Specifically, the commenter did not provide new
information that would cause the NRC to reevaluate its position in the
preliminary safety evaluation report (ADAMS Accession No. ML19120A064).
The commenter did not provide information that would cause the NRC to
conduct additional analyses nor did the commenter raise a serious issue
that warrants an NRC response to complete the record. The commenter
also did not raise any issues that have not been previously addressed.
In addition, the commenter did not propose a change, without which the
rule would be ineffective or unacceptable.
The NRC's safety evaluation report provides the NRC's review and
assessment of Holtec's proposed changes and the independent
calculations that the NRC performed to verify Holtec's analyses. The
final safety analysis report provided by Holtec, and reviewed by the
NRC, evaluates generic site characteristics. Any general licensee
proposing to use Amendment No. 14 to the HI-STORM 100 Cask System will
have to ensure, as required by 10 CFR 72.212(b)(6), that its site
characteristics are enveloped by the cask design bases evaluated for
Amendment No. 14. The NRC confirmed that Holtec's evaluation
[[Page 67828]]
of Amendment No. 14 shows that the use of the damaged fuel isolators
and new heat loads will not impair the ability of the storage cask to
maintain confinement and subcriticality. Additionally, the off-site
dose rates will meet the dose requirements in 10 CFR 72.236(d).
As discussed in the environmental assessment for the direct final
rule, Amendment No. 14 does not reflect a significant change in design
or fabrication of the cask; therefore, any resulting occupational
exposure or offsite dose rates would remain well within the 10 CFR part
20 annual limits for public and occupational radiological doses.
Additionally, Amendment No. 14 will not result in any radiological or
non-radiological environmental impacts that significantly differ from
the environmental impacts evaluated in the environmental assessment
supporting the final rule, ``Storage of Spent Fuel in NRC-Approved
Storage Casks at Power Reactor Sites'' (55 FR 29181; July 18, 1990).
There will be no significant change in the types of, or significant
revisions in the amounts of, any effluent released; no significant
increase in the individual or cumulative radiation exposures; and no
significant increase in the potential for, or consequences of,
radiological accidents. Therefore, this direct final rule will become
effective as scheduled.
Dated at Rockville, Maryland, this 6th day of December 2019.
For the Nuclear Regulatory Commission.
Pamela J. Shepherd-Vladimir,
Acting Chief, Regulatory Analysis and Rulemaking Support Branch,
Division of Rulemaking, Environmental and Financial Support, Office of
Nuclear Material Safety and Safeguards.
[FR Doc. 2019-26691 Filed 12-11-19; 8:45 am]
BILLING CODE 7590-01-P