List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 6, 26310-26312 [E9-12618]
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Federal Register / Vol. 74, No. 104 / Tuesday, June 2, 2009 / Proposed Rules
(iii) (A) Pumps and valves, in
facilities whose construction permit was
issued before November 22, 1999, which
are classified as ASME Code Class 1
must be designed and be provided with
access to enable the performance of
inservice testing of the pumps and
valves for assessing operational
readiness set forth in the editions and
addenda of Section XI of the ASME
Boiler and Pressure Vessel Code
incorporated by reference in paragraph
(b) of this section (or the optional ASME
Code cases listed in NRC Regulatory
Guide 1.147, Revision 16; or Regulatory
Guide 1.192 that are incorporated by
reference in paragraph (b) of this
section) applied to the construction of
the particular pump or valve or the
Summer 1973 Addenda, whichever is
later.
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(iv)(A) Pumps and valves, in facilities
whose construction permit was issued
before November 22, 1999, which are
classified as ASME Code Class 2 and
Class 3 must be designed and be
provided with access to enable the
performance of inservice testing of the
pumps and valves for assessing
operational readiness set forth in the
editions and addenda of Section XI of
the ASME Boiler and Pressure Vessel
Code incorporated by reference in
paragraph (b) of this section (or the
optional ASME Code Cases listed in
NRC Regulatory Guide 1.147, Revision
16, that are incorporated by reference in
paragraph (b) of this section) applied to
the construction of the particular pump
or valve or the Summer 1973 Addenda,
whichever is later.
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(4) * * *
(ii) Inservice tests to verify
operational readiness of pumps and
valves, whose function is required for
safety, conducted during successive
120-month intervals must comply with
the requirements of the latest edition
and addenda of the Code incorporated
by reference in paragraph (b) of this
section 12 months before the start of the
120-month interval (or the optional
ASME Code cases listed in NRC
Regulatory Guide 1.147, Revision 16; or
Regulatory Guide 1.192 that are
incorporated by reference in paragraph
(b) of this section), subject to the
conditions listed in paragraph (b) of this
section.
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(g) * * *
(2) For a boiling or pressurized watercooled nuclear power facility whose
construction permit was issued on or
after January 1, 1971, but before July 1,
1974, components (including supports)
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16:00 Jun 01, 2009
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which are classified as ASME Code
Class 1 and Class 2 must be designed
and be provided with access to enable
the performance of inservice
examination of such components
(including supports) and must meet the
preservice examination requirements set
forth in editions and addenda of Section
XI of the ASME Boiler and Pressure
Vessel Code incorporated by reference
in paragraph (b) of this section (or the
optional ASME Code cases listed in
NRC Regulatory Guide 1.147, Revision
16, that are incorporated by reference in
paragraph (b) of this section) in effect 6
months before the date of issuance of
the construction permit. The
components (including supports) may
meet the requirements set forth in
subsequent editions and addenda of this
Code which are incorporated by
reference in paragraph (b) of this section
(or the optional ASME Code cases listed
in NRC Regulatory Guide 1.147,
Revision 16, that are incorporated by
reference in paragraph (b) of this
section), subject to the applicable
limitations and modifications.
(3) * * *
(i) Components (including supports)
which are classified as ASME Code
Class 1 must be designed and be
provided with access to enable the
performance of inservice examination of
these components and must meet the
preservice examination requirements set
forth in the editions and addenda of
Section XI of the ASME Boiler and
Pressure Vessel Code incorporated by
reference in paragraph (b) of this section
(or the optional ASME Code cases listed
in NRC Regulatory Guide 1.147,
Revision 16, that are incorporated by
reference in paragraph (b) of this
section) applied to the construction of
the particular component.
(ii) Components which are classified
as ASME Code Class 2 and Class 3 and
supports for components which are
classified as ASME Code Class 1, Class
2, and Class 3 must be designed and be
provided with access to enable the
performance of inservice examination of
these components and must meet the
preservice examination requirements set
forth in the editions and addenda of
Section XI of the ASME Boiler and
Pressure Vessel Code incorporated by
reference in paragraph (b) of this section
(or the optional ASME Code Cases listed
in NRC Regulatory Guide 1.147,
Revision 16, that are incorporated by
reference in paragraph (b) of this
section) applied to the construction of
the particular component.
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(4) * * *
(i) Inservice examination of
components and system pressure tests
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conducted during the initial 120-month
inspection interval must comply with
the requirements in the latest edition
and addenda of the Code incorporated
by reference in paragraph (b) of this
section on the date 12 months before the
date of issuance of the operating license
(or the optional ASME Code cases listed
in NRC Regulatory Guide 1.147,
Revision 16, that are incorporated by
reference in paragraph (b) of this
section, subject to the conditions listed
in paragraph (b) of this section.
(ii) Inservice examination of
components and system pressure tests
conducted during successive 120-month
inspection intervals must comply with
the requirements of the latest edition
and addenda of the Code incorporated
by reference in paragraph (b) of this
section 12 months before the start of the
120-month inspection interval (or the
optional ASME Code cases listed in
NRC Regulatory Guide 1.147, Revision
16, that are incorporated by reference in
paragraph (b) of this section), subject to
the conditions listed in paragraph (b) of
this section.
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Dated at Rockville, Maryland, this 12th day
of May 2009.
For the Nuclear Regulatory Commission
R.W. Borchardt,
Executive Director for Operations.
[FR Doc. E9–12751 Filed 6–1–09; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 72
RIN 3150–AI60
[NRC–2009–0132]
List of Approved Spent Fuel Storage
Casks: HI–STORM 100 Revision 6
AGENCY: Nuclear Regulatory
Commission.
ACTION: Proposed rule.
SUMMARY: The U.S. Nuclear Regulatory
Commission (NRC) is proposing to
amend its spent fuel storage cask
regulations by revising the Holtec
International HI–STORM 100 dry
storage cask system listing within the
‘‘List of Approved Spent Fuel Storage
Casks’’ to include Amendment No. 6 to
Certificate of Compliance (CoC) Number
1014. Amendment No. 6 would modify
the CoC to add instrument tube tie rods
used for pressurized water reactor 15x15
and 17x17 fuel lattices, for both intact
and damaged fuel assemblies, to the
approved contents of the MPC–24,
MPC–24E, MPC–24EF, MPC–32, and
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02JNP1
Federal Register / Vol. 74, No. 104 / Tuesday, June 2, 2009 / Proposed Rules
MPC–32F models; and to correct legacy
editorial issues in Appendices A and B
Technical Specifications.
DATES: Comments on the proposed rule
must be received on or before July 2,
2009.
You may submit comments
by any one of the following methods.
Comments submitted in writing or in
electronic form will be made available
for public inspection. Because your
comments will not be edited to remove
any identifying or contact information,
the NRC cautions you against including
any information in your submission that
you do not want to be publicly
disclosed.
Federal e-Rulemaking Portal: Go to
https://www.regulations.gov and search
for documents filed under Docket ID
[NRC–2009–0132]. Address questions
about NRC dockets to Carol Gallagher,
301–492–3668; e-mail
Carol.Gallagher@nrc.gov.
Mail comments to: Secretary, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, Attn:
Rulemakings and Adjudications Staff.
E-mail comments to:
Rulemaking.Comments@nrc.gov. If you
do not receive a reply e-mail confirming
that we have received your comments,
contact us directly at 301–415–1677.
Hand deliver comments to: 11555
Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m.
Federal workdays. (Telephone 301–415–
1677.)
Fax comments to: Secretary, U.S.
Nuclear Regulatory Commission at
301–415–1101.
You can access publicly available
documents related to this document
using the following methods:
NRC’s Public Document Room (PDR):
The public may examine and have
copied for a fee publicly available
documents at the NRC’s PDR, Public
File Area O–1F21, One White Flint
North, 11555 Rockville Pike, Rockville,
Maryland.
NRC’s Agencywide Documents Access
and Management System (ADAMS):
Publicly available documents created or
received at the NRC are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this page,
the public can gain entry into ADAMS,
which provides text and image files of
NRC’s public documents. If you do not
have access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC’s
PDR Reference staff at 1–800–397–4209,
301–415–4737 or by e-mail to
pdr.resource@nrc.gov. An electronic
copy of the proposed Certificate of
ADDRESSES:
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16:00 Jun 01, 2009
Jkt 217001
Compliance (CoC) No. 1014, the
proposed technical specifications (TS),
and the preliminary safety evaluation
report (SER) can be found under
ADAMS Package Number
ML090290140.
The proposed CoC No. 1014, the
proposed TS, the preliminary SER, and
the environmental assessment are
available for inspection at the NRC PDR,
11555 Rockville Pike, Rockville, MD.
Single copies of these documents may
be obtained from Jayne M. McCausland,
Office of Federal and State Materials
and Environmental Management
Programs, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone (301) 415–6219, e-mail
Jayne.McCausland@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
Jayne M. McCausland, Office of Federal
and State Materials and Environmental
Management Programs, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone (301) 415–
6219, e-mail
Jayne.McCausland@nrc.gov.
SUPPLEMENTARY INFORMATION:
For additional supplementary
information, see the direct final rule
published in the Rules and Regulations
section of this Federal Register.
Procedural Background
This rule is limited to the changes
contained in Amendment No. 6 to CoC
No. 1014 and does not include other
aspects of the HI–STORM 100 design.
Because NRC considers this action
noncontroversial and routine, the NRC
is publishing this proposed rule
concurrently as a direct final rule in the
Rules and Regulations section of this
Federal Register. Adequate protection
of public health and safety continues to
be ensured. The direct final rule will
become effective on August 17, 2009.
However, if the NRC receives significant
adverse comments on the direct final
rule by July 2, 2009, then the NRC will
publish a document that withdraws the
direct final rule. If the direct final rule
is withdrawn, the NRC will address the
comments received in response to the
proposed revisions in a subsequent final
rule. Absent significant modifications to
the proposed revisions requiring
republication, the NRC will not initiate
a second comment period on this action
in the event the direct final rule is
withdrawn.
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
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26311
unacceptable without a change. A
comment is adverse and significant if:
(1) The comment opposes the rule and
provides a reason sufficient to require a
substantive response in a notice-andcomment process. For example, a
substantive response is required when:
(a) The comment causes the NRC staff
to reevaluate (or reconsider) its position
or conduct additional analysis;
(b) The comment raises an issue
serious enough to warrant a substantive
response to clarify or complete the
record; or
(c) The comment raises a relevant
issue that was not previously addressed
or considered by the NRC staff.
(2) The comment proposes a change
or an addition to the rule, and it is
apparent that the rule would be
ineffective or unacceptable without
incorporation of the change or addition.
(3) The comment causes the NRC staff
to make a change (other than editorial)
to the rule, CoC, or TS.
For additional procedural information
and the regulatory analysis, see the
direct final rule published in the Rules
and Regulations section of this Federal
Register.
List of Subjects in 10 CFR Part 72
Administrative practice and
procedure, Hazardous waste, Nuclear
materials, Occupational safety and
health, 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.
553; the NRC is proposing to adopt the
following amendments to 10 CFR Part
72.
PART 72—LICENSING
REQUIREMENTS FOR THE
INDEPENDENT STORAGE OF SPENT
NUCLEAR FUEL, HIGH–LEVEL
RADIOACTIVE WASTE, AND
REACTOR–RELATED GREATER THAN
CLASS C WASTE
1. The authority citation for Part 72
continues to read as follows:
Authority: Secs. 51, 53, 57, 62, 63, 65, 69,
81, 161, 182, 183, 184, 186, 187, 189, 68 Stat.
929, 930, 932, 933, 934, 935, 948, 953, 954,
955, as amended, sec. 234, 83 Stat. 444, as
amended (42 U.S.C. 2071, 2073, 2077, 2092,
2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2238, 2282); sec. 274, Pub.
L. 86–373, 73 Stat. 688, as amended (42
U.S.C. 2021); sec. 201, as amended, 202, 206,
88 Stat. 1242, as amended, 1244, 1246 (42
U.S.C. 5841, 5842, 5846); Pub. L. 95–601, sec.
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Federal Register / Vol. 74, No. 104 / Tuesday, June 2, 2009 / Proposed Rules
10, 92 Stat. 2951 as amended by Pub. L. 102–
486, sec. 7902, 106 Stat. 3123 (42 U.S.C.
5851); sec. 102, Pub. L. 91–190, 83 Stat. 853
(42 U.S.C. 4332); secs. 131, 132, 133, 135,
137, 141, Pub. L. 97–425, 96 Stat. 2229, 2230,
2232, 2241, sec. 148, Pub. L. 100–203, 101
Stat. 1330–235 (42 U.S.C. 10151, 10152,
10153, 10155, 10157, 10161, 10168); sec.
1704, 112 Stat. 2750 (44 U.S.C. 3504 note);
sec. 651(e), Pub. L. 109–58, 119 Stat. 806–10
(42 U.S.C. 2014, 2021, 2021b, 2111).
Section 72.44(g) also issued under secs.
142(b) and 148(c), (d), Pub. L. 100–203, 101
Stat. 1330–232, 1330–236 (42 U.S.C.
10162(b), 10168(c),(d)). Section 72.46 also
issued under sec. 189, 68 Stat. 955 (42 U.S.C.
2239); sec. 134, Pub. L. 97–425, 96 Stat. 2230
(42 U.S.C. 10154). Section 72.96(d) also
issued under sec. 145(g), Pub. L. 100–203,
101 Stat. 1330–235 (42 U.S.C. 10165(g)).
Subpart J also issued under secs. 2(2), 2(15),
2(19), 117(a), 141(h), Pub. L. 97–425, 96 Stat.
2202, 2203, 2204, 2222, 2244 (42 U.S.C.
10101, 10137(a), 10161(h)). Subparts K and L
are also issued under sec. 133, 98 Stat. 2230
(42 U.S.C. 10153) and sec. 218(a), 96 Stat.
2252 (42 U.S.C. 10198).
2. In § 72.214, Certificate of
Compliance 1014 is revised to read as
follows:
§ 72.214 List of approved spent fuel
storage casks.
*
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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.
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: June 1,
2020.
Model Number: HI–STORM 100.
*
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Dated at Rockville, Maryland, this 7th day
of May 2009.
For the Nuclear Regulatory Commission.
R.W. Borchardt,
Executive Director for Operations.
[FR Doc. E9–12618 Filed 6–1–09; 8:45 am]
BILLING CODE 7590–01–P
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DEPARTMENT OF TRANSPORTATION
Federal Aviation Administration
14 CFR Part 39
[Docket No. FAA–2009–0465; Directorate
Identifier 2007–NM–244–AD]
RIN 2120–AA64
Airworthiness Directives; Airbus Model
A310–203, –204, –221, –222, –304,
–322, –324, and –325 Airplanes
AGENCY: Federal Aviation
Administration (FAA), DOT.
ACTION: Notice of proposed rulemaking
(NPRM).
SUMMARY: We propose to adopt a new
airworthiness directive (AD) for the
products listed above that would
supersede an existing AD. This
proposed AD results from mandatory
continuing airworthiness information
(MCAI) originated by an aviation
authority of another country to identify
and correct an unsafe condition on an
aviation product. The MCAI describes
the unsafe condition as:
´ ´
DGAC [Direction Generale de l’Aviation
Civile] France issued AD F–2005–078 [which
corresponds to FAA AD 2006–02–06] to
require the modification (Airbus
modification 13023), defined in Airbus SB
[service bulletin] A310–53–2124, to increase
the service life of junctions of center box
upper frame bases to upper fuselage arches.
This structural modification falls within the
scope of the work related to the extension of
the service life of A310 aircraft and
widespread fatigue damage evaluations.
The threshold timescales for
accomplishment of the tasks as defined in SB
A310–53–2124 were refined and reduced.
* * *
*
*
*
*
*
The unsafe condition is fatigue
cracking of the frame foot run-outs,
which could lead to rupture of the frame
foot and cracking in adjacent frames and
skin, and which could result in reduced
structural integrity of the fuselage. The
proposed AD would require actions that
are intended to address the unsafe
condition described in the MCAI.
DATES: We must receive comments on
this proposed AD by July 2, 2009.
ADDRESSES: You may send comments 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–
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Fmt 4702
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30, West Building Ground Floor, Room
W12–40, 1200 New Jersey Avenue, SE.,
Washington, DC, between 9 a.m. and 5
p.m., Monday through Friday, except
Federal holidays.
For service information identified in
this proposed AD, contact Airbus SAS—
EAW (Airworthiness Office), 1 Rond
Point Maurice Bellonte, 31707 Blagnac
Cedex, France; telephone +33 5 61 93 36
96; fax +33 5 61 93 44 51; e-mail:
account.airworth-eas@airbus.com;
Internet https://www.airbus.com. You
may review copies of the referenced
service information at the FAA,
Transport Airplane Directorate, 1601
Lind Avenue, SW., Renton, Washington.
For information on the availability of
this material at the FAA, call 425–227–
1221 or 425–227–1152.
Examining the AD Docket
You may examine the AD docket on
the Internet at https://
www.regulations.gov; or in person at the
Docket Operations office between 9 a.m.
and 5 p.m., Monday through Friday,
except Federal holidays. The AD docket
contains this proposed AD, the
regulatory evaluation, any comments
received, and other information. The
street address for the Docket Operations
office (telephone (800) 647–5527) is in
the ADDRESSES section. Comments will
be available in the AD docket shortly
after receipt.
FOR FURTHER INFORMATION CONTACT: Tom
Stafford, Aerospace Engineer,
International Branch, ANM–116,
Transport Airplane Directorate, FAA,
1601 Lind Avenue, SW., Renton,
Washington 98055–4056; telephone
(425) 227–1622; fax (425) 227–1149.
SUPPLEMENTARY INFORMATION:
Comments Invited
We invite you to send any written
relevant data, views, or arguments about
this proposed AD. Send your comments
to an address listed under the
ADDRESSES section. Include ‘‘Docket No.
FAA–2009–0465; Directorate Identifier
2007–NM–244–AD’’ at the beginning of
your comments. We specifically invite
comments on the overall regulatory,
economic, environmental, and energy
aspects of this proposed AD. We will
consider all comments received by the
closing date and may amend this
proposed AD based on those comments.
We will post all comments we
receive, without change, to https://
www.regulations.gov, including any
personal information you provide. We
will also post a report summarizing each
substantive verbal contact we receive
about this proposed AD.
E:\FR\FM\02JNP1.SGM
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Agencies
[Federal Register Volume 74, Number 104 (Tuesday, June 2, 2009)]
[Proposed Rules]
[Pages 26310-26312]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-12618]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
RIN 3150-AI60
[NRC-2009-0132]
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision
6
AGENCY: Nuclear Regulatory Commission.
ACTION: Proposed rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is proposing to
amend its spent fuel storage cask regulations by revising the Holtec
International HI-STORM 100 dry storage cask system listing within the
``List of Approved Spent Fuel Storage Casks'' to include Amendment No.
6 to Certificate of Compliance (CoC) Number 1014. Amendment No. 6 would
modify the CoC to add instrument tube tie rods used for pressurized
water reactor 15x15 and 17x17 fuel lattices, for both intact and
damaged fuel assemblies, to the approved contents of the MPC-24, MPC-
24E, MPC-24EF, MPC-32, and
[[Page 26311]]
MPC-32F models; and to correct legacy editorial issues in Appendices A
and B Technical Specifications.
DATES: Comments on the proposed rule must be received on or before July
2, 2009.
ADDRESSES: You may submit comments by any one of the following methods.
Comments submitted in writing or in electronic form will be made
available for public inspection. Because your comments will not be
edited to remove any identifying or contact information, the NRC
cautions you against including any information in your submission that
you do not want to be publicly disclosed.
Federal e-Rulemaking Portal: Go to https://www.regulations.gov and
search for documents filed under Docket ID [NRC-2009-0132]. Address
questions about NRC dockets to Carol Gallagher, 301-492-3668; e-mail
Carol.Gallagher@nrc.gov.
Mail comments to: Secretary, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, Attn: Rulemakings and Adjudications Staff.
E-mail comments to: Rulemaking.Comments@nrc.gov. If you do not
receive a reply e-mail confirming that we have received your comments,
contact us directly at 301-415-1677.
Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m. Federal workdays. (Telephone
301-415-1677.)
Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at
301-415-1101.
You can access publicly available documents related to this
document using the following methods:
NRC's Public Document Room (PDR): The public may examine and have
copied for a fee publicly available documents at the NRC's PDR, Public
File Area O-1F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland.
NRC's Agencywide Documents Access and Management System (ADAMS):
Publicly available documents created or received at the NRC are
available electronically at the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain
entry into ADAMS, which provides text and image files of NRC's public
documents. If you do not have access to ADAMS or if there are problems
in accessing the documents located in ADAMS, contact the NRC's PDR
Reference staff at 1-800-397-4209, 301-415-4737 or by e-mail to
pdr.resource@nrc.gov. An electronic copy of the proposed Certificate of
Compliance (CoC) No. 1014, the proposed technical specifications (TS),
and the preliminary safety evaluation report (SER) can be found under
ADAMS Package Number ML090290140.
The proposed CoC No. 1014, the proposed TS, the preliminary SER,
and the environmental assessment are available for inspection at the
NRC PDR, 11555 Rockville Pike, Rockville, MD. Single copies of these
documents may be obtained from Jayne M. McCausland, Office of Federal
and State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6219, e-mail Jayne.McCausland@nrc.gov.
FOR FURTHER INFORMATION CONTACT: Jayne M. McCausland, Office of Federal
and State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6219, e-mail Jayne.McCausland@nrc.gov.
SUPPLEMENTARY INFORMATION:
For additional supplementary information, see the direct final rule
published in the Rules and Regulations section of this Federal
Register.
Procedural Background
This rule is limited to the changes contained in Amendment No. 6 to
CoC No. 1014 and does not include other aspects of the HI-STORM 100
design. Because NRC considers this action noncontroversial and routine,
the NRC is publishing this proposed rule concurrently as a direct final
rule in the Rules and Regulations section of this Federal Register.
Adequate protection of public health and safety continues to be
ensured. The direct final rule will become effective on August 17,
2009. However, if the NRC receives significant adverse comments on the
direct final rule by July 2, 2009, then the NRC will publish a document
that withdraws the direct final rule. If the direct final rule is
withdrawn, the NRC will address the comments received in response to
the proposed revisions in a subsequent final rule. Absent significant
modifications to the proposed revisions requiring republication, the
NRC will not initiate a second comment period on this action in the
event the direct final rule is withdrawn.
A significant adverse comment is a comment where the commenter
explains why the rule would be inappropriate, including challenges to
the rule's underlying premise or approach, or would be ineffective or
unacceptable without a change. A comment is adverse and significant if:
(1) The comment opposes the rule and provides a reason sufficient
to require a substantive response in a notice-and-comment process. For
example, a substantive response is required when:
(a) The comment causes the NRC staff to reevaluate (or reconsider)
its position or conduct additional analysis;
(b) The comment raises an issue serious enough to warrant a
substantive response to clarify or complete the record; or
(c) The comment raises a relevant issue that was not previously
addressed or considered by the NRC staff.
(2) The comment proposes a change or an addition to the rule, and
it is apparent that the rule would be ineffective or unacceptable
without incorporation of the change or addition.
(3) The comment causes the NRC staff to make a change (other than
editorial) to the rule, CoC, or TS.
For additional procedural information and the regulatory analysis,
see the direct final rule published in the Rules and Regulations
section of this Federal Register.
List of Subjects in 10 CFR Part 72
Administrative practice and procedure, Hazardous waste, Nuclear
materials, Occupational safety and health, 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. 553; the NRC is proposing to adopt the following
amendments to 10 CFR Part 72.
PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF
SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-
RELATED GREATER THAN CLASS C WASTE
1. The authority citation for Part 72 continues to read as follows:
Authority: Secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183,
184, 186, 187, 189, 68 Stat. 929, 930, 932, 933, 934, 935, 948, 953,
954, 955, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C.
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2238, 2282); sec. 274, Pub. L. 86-373, 73 Stat.
688, as amended (42 U.S.C. 2021); sec. 201, as amended, 202, 206, 88
Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846);
Pub. L. 95-601, sec.
[[Page 26312]]
10, 92 Stat. 2951 as amended by Pub. L. 102-486, sec. 7902, 106
Stat. 3123 (42 U.S.C. 5851); sec. 102, Pub. L. 91-190, 83 Stat. 853
(42 U.S.C. 4332); secs. 131, 132, 133, 135, 137, 141, Pub. L. 97-
425, 96 Stat. 2229, 2230, 2232, 2241, sec. 148, Pub. L. 100-203, 101
Stat. 1330-235 (42 U.S.C. 10151, 10152, 10153, 10155, 10157, 10161,
10168); sec. 1704, 112 Stat. 2750 (44 U.S.C. 3504 note); sec.
651(e), Pub. L. 109-58, 119 Stat. 806-10 (42 U.S.C. 2014, 2021,
2021b, 2111).
Section 72.44(g) also issued under secs. 142(b) and 148(c), (d),
Pub. L. 100-203, 101 Stat. 1330-232, 1330-236 (42 U.S.C. 10162(b),
10168(c),(d)). Section 72.46 also issued under sec. 189, 68 Stat.
955 (42 U.S.C. 2239); sec. 134, Pub. L. 97-425, 96 Stat. 2230 (42
U.S.C. 10154). Section 72.96(d) also issued under sec. 145(g), Pub.
L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10165(g)). Subpart J also
issued under secs. 2(2), 2(15), 2(19), 117(a), 141(h), Pub. L. 97-
425, 96 Stat. 2202, 2203, 2204, 2222, 2244 (42 U.S.C. 10101,
10137(a), 10161(h)). Subparts K and L are also issued under sec.
133, 98 Stat. 2230 (42 U.S.C. 10153) and sec. 218(a), 96 Stat. 2252
(42 U.S.C. 10198).
2. In 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.
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: June 1, 2020.
Model Number: HI-STORM 100.
* * * * *
Dated at Rockville, Maryland, this 7th day of May 2009.
For the Nuclear Regulatory Commission.
R.W. Borchardt,
Executive Director for Operations.
[FR Doc. E9-12618 Filed 6-1-09; 8:45 am]
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