Notice of Availability of Draft NUREG-1536, Revision 1A, “Standard Review Plan for Spent Fuel Dry Storage Systems at a General License Facility”, and Opportunity To Provide Comments, 17546-17547 [E9-8599]
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Federal Register / Vol. 74, No. 71 / Wednesday, April 15, 2009 / Notices
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Signed at Washington, DC, this 6th day of
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Douglas F. Small,
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[FR Doc. E9–8505 Filed 4–14–09; 8:45 am]
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26, 2009 deadline.
Michael P. McDonald,
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[FR Doc. E9–8594 Filed 4–14–09; 8:45 am]
to review and solicit comments on the
Draft NUREG–1536, Revision 1A,
‘‘Standard Review Plan for Spent Fuel
Dry Storage Systems at a General
License Facility’’. These comments will
be considered in the final version or
subsequent revisions.
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II. Opportunity To Provide Comments
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Notice of Availability of Draft NUREG–
1536, Revision 1A, ‘‘Standard Review
Plan for Spent Fuel Dry Storage
Systems at a General License Facility’’,
and Opportunity To Provide Comments
AGENCY: Nuclear Regulatory
Commission.
ACTION: Notice of availability and
opportunity to provide comments.
DATES: Comments must be provided by
July 14, 2009.
FOR FURTHER INFORMATION CONTACT: Ron
Parkhill, Senior Mechanical Engineer,
Thermal and Containment Branch,
Division of Spent Fuel Storage and
Transportation Division, Office of
Nuclear Material Safety and Safeguards,
U.S. Nuclear Regulatory Commission
Washington, DC 20005–0001.
Telephone: (301) 492–3324; fax number:
(301) 492–3342; e-mail:
ron.parkhill@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The Nuclear Regulatory Commission
(NRC) is issuing Draft Revision 1A to
NUREG–1536, ‘‘Standard Review Plan
for Spent Fuel Dry Storage Systems at a
General License Facility.’’ Its previous
title, ‘‘Standard Review Plan for Dry
Cask Storage Systems,’’ has been
changed to better reflect its
applicability. This revision incorporates
Interim Staff Guidance (ISG) documents
1 through 22, as applicable, as well as
other current NRC staff practices (e.g.
addition of a materials chapter) utilized
in its review of licensee integrated
safety analyses, license applications or
amendment requests, or other related
licensing activities for dry storage
systems under 10 CFR part 72.
Additionally, the guidance contained in
the Review Procedures section of each
chapter of the subject document has
been risk-informed to assist the NRC
staff in prioritizing its review with
respect to relative level of effort, and to
increase efficiency.
The purpose of this notice is to
provide the public with an opportunity
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Comments and questions on Draft
NUREG–1536, Revision 1A, should be
directed to Ron Parkhill, Thermal and
Containment Branch, Division of Spent
Fuel Storage and Transportation, Office
of Nuclear Materials Safety and
Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20005–
0001 by July 14, 2009. Comments
received after this date will be
considered if it is practical to do so, but
only those comments received on or
before the due date can be assured
consideration. Comments can also be
submitted by telephone, fax, or e-mail to
the following: Telephone: (301) 492–
3324; fax number: (301) 492–3331; email: Ron.Parkhill@NRC.gov.
III. Further Information
Documents related to this action are
available electronically at the NRC’s
Electronic Reading Room at https://
www.nrc.gov/reading-rm/adams.html.
From this site, you can access the NRC’s
Agencywide Document Access and
Management System (ADAMS), which
provides text and image files of NRC’s
public documents. The ADAMS
accession number for the document
related to this notice is [ML090400676].
If you do not have access to ADAMS, or
if there are problems in accessing the
documents located in ADAMS, contact
the NRC Public Document Room (PDR)
reference staff at 1–800–397–4209, 301–
415–4737, or by e-mail to
pdr.resource@nrc.gov. ISGs that have
been incorporated, as appropriate, into
the subject document can be viewed at
https://www.nrc.gov/reading-rm/
doc-collections/isg/spent-fuel.html.
During the public comment period for
this document, other ISGs could be
issued separately for public comment,
and may be incorporated into the final
version of NUREG–1536.
This document may also be viewed
electronically on the public computers
located at the NRC’s PDR, O–1 F21, One
White Flint North, 11555 Rockville
Pike, Rockville, MD 20852. The PDR
reproduction contractor will copy
documents for a fee.
Dated at Rockville, Maryland, this 2nd day
of April, 2009.
E:\FR\FM\15APN1.SGM
15APN1
Federal Register / Vol. 74, No. 71 / Wednesday, April 15, 2009 / Notices
For the Nuclear Regulatory Commission.
Nathan Sanfilippo,
Acting Chief, Thermal and Containment
Branch, Division of Spent Fuel Storage and
Transportation, Office of Nuclear Materials
Safety and Safeguards.
[FR Doc. E9–8599 Filed 4–14–09; 8:45 am]
I. Introduction
the safety function to be performed.
Where generally recognized codes and
standards are used, Criterion 1 requires
that they be identified and evaluated to
determine their applicability, adequacy,
and sufficiency and be supplemented or
modified as necessary to ensure a
quality product in keeping with the
required safety function.
Criterion 30, ‘‘Quality of Reactor
Coolant Pressure Boundary,’’ of the
same appendix requires, in part, that
components that are part of the reactor
coolant pressure boundary be designed,
fabricated, erected, and tested to the
highest practical quality standards.
Criterion 31, ‘‘Fracture Prevention of
Reactor Coolant Pressure Boundary,’’
requires, in part, that the reactor coolant
pressure boundary be designed with
sufficient margin to assure that when
stressed under operating, maintenance,
testing, and postulated accident
conditions (1) the boundary behaves in
a nonbrittle manner and (2) the
probability of rapidly propagating
fracture is minimized.
Appendix B, ‘‘Quality Assurance
Criteria for Nuclear Power Plants and
Fuel Reprocessing Plants,’’ to 10 CFR
part 50 requires, in part, that measures
be established for the control of special
processing such as heat treating and that
proper testing be performed.
The U.S. Nuclear Regulatory
Commission (NRC) is issuing for public
comment a draft regulatory guide in the
agency’s ‘‘Regulatory Guide’’ series.
This series was developed to describe
and make available to the public such
information as methods that are
acceptable to the NRC staff for
implementing specific parts of the
NRC’s regulations, techniques that the
staff uses in evaluating specific
problems or postulated accidents, and
data that the staff needs in its review of
applications for permits and licenses.
The draft regulatory guide (DG), titled,
‘‘Materials and Inspections for Reactor
Vessel Closure Studs,’’ is temporarily
identified by its task number, DG–1211,
which should be mentioned in all
related correspondence. DG–1211 is the
proposed Revision 1 of Regulatory
Guide 1.65.
General Design Criterion 1, ‘‘Quality
Standards and Records,’’ of Appendix
A, ‘‘General Design Criteria for Nuclear
Power Plants,’’ to Title 10, Part 50,
‘‘Domestic Licensing of Production and
Utilization Facilities,’’ of the Code of
Federal Regulations (10 CFR part 50),
requires, in part, that structures,
systems, and components important to
safety be designed, fabricated, erected,
and tested to quality standards
commensurate with the importance of
II. Further Information
The NRC staff is soliciting comments
on DG–1211. Comments may be
accompanied by relevant information or
supporting data, and should mention
DG–1211 in the subject line. Comments
submitted in writing or in electronic
form will be made available to the
public in their entirety through the
NRC’s Agencywide Documents Access
and Management System (ADAMS).
Personal information will not be
removed from the comments. Comments
may be submitted by any of the
following methods:
1. Mail to: Rulemaking and Directives
Branch, Mail Stop: TWB–05–B01M,
Office of Administration, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
2. Fax to: Rulemaking and Directives
Branch, Office of Administration, U.S.
Nuclear Regulatory Commission at (301)
492–3446.
Requests for technical information
about DG–1211 may be directed to
Wallace E. Norris at (301) 251–7650 or
e-mail to Wallace.Norris@nrc.gov.
Comments would be most helpful if
received by June 12, 2009. Comments
received after that 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
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[NRC–2009–0166]
Issuance and Availability of Draft
Regulatory Guide
AGENCY: Nuclear Regulatory
Commission.
ACTION: Notice of issuance and
availability of Draft Regulatory Guide
1211.
FOR FURTHER INFORMATION CONTACT:
Wallace E. Norris, Division of
Engineering, Office of Nuclear
Regulatory Research, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone (301) 251–
7650 or e-mail to
Wallace.Norris@nrc.gov.
rwilkins on PROD1PC63 with PROPOSALS
SUPPLEMENTARY INFORMATION:
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17547
this date. Although a time limit is given,
comments and suggestions in
connection with items for inclusion in
guides currently being developed or
improvements in all published guides
are encouraged at any time.
Electronic copies of DG–1211 are
available through the NRC’s public Web
site under Draft Regulatory Guides in
the ‘‘Regulatory Guides’’ collection of
the NRC’s Electronic Reading Room at
https://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also
available in ADAMS (https://
www.nrc.gov/reading-rm/adams.html),
under Accession No. ML082820439.
In addition, regulatory guides are
available for inspection at the NRC’s
Public Document Room (PDR), which is
located at Room O–1F21, One White
Flint North, 11555 Rockville Pike,
Rockville, Maryland 20852–2738. The
PDR’s mailing address is USNRC PDR,
Washington, DC 20555–0001. The PDR
can also be reached by telephone at
(301) 415–4737 or (800) 397–4209, by
fax at (301) 415–3548, and by e-mail to
pdr.resource@nrc.gov.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
Dated at Rockville, Maryland, this 6th day
of April 2009.
For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch,
Division of Engineering, Office of Nuclear
Regulatory Research.
[FR Doc. E9–8597 Filed 4–14–09; 8:45 am]
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E:\FR\FM\15APN1.SGM
15APN1
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[Federal Register Volume 74, Number 71 (Wednesday, April 15, 2009)]
[Notices]
[Pages 17546-17547]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-8599]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2009-0164]
Notice of Availability of Draft NUREG-1536, Revision 1A,
``Standard Review Plan for Spent Fuel Dry Storage Systems at a General
License Facility'', and Opportunity To Provide Comments
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of availability and opportunity to provide comments.
-----------------------------------------------------------------------
DATES: Comments must be provided by July 14, 2009.
FOR FURTHER INFORMATION CONTACT: Ron Parkhill, Senior Mechanical
Engineer, Thermal and Containment Branch, Division of Spent Fuel
Storage and Transportation Division, Office of Nuclear Material Safety
and Safeguards, U.S. Nuclear Regulatory Commission Washington, DC
20005-0001. Telephone: (301) 492-3324; fax number: (301) 492-3342; e-
mail: ron.parkhill@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The Nuclear Regulatory Commission (NRC) is issuing Draft Revision
1A to NUREG-1536, ``Standard Review Plan for Spent Fuel Dry Storage
Systems at a General License Facility.'' Its previous title, ``Standard
Review Plan for Dry Cask Storage Systems,'' has been changed to better
reflect its applicability. This revision incorporates Interim Staff
Guidance (ISG) documents 1 through 22, as applicable, as well as other
current NRC staff practices (e.g. addition of a materials chapter)
utilized in its review of licensee integrated safety analyses, license
applications or amendment requests, or other related licensing
activities for dry storage systems under 10 CFR part 72. Additionally,
the guidance contained in the Review Procedures section of each chapter
of the subject document has been risk-informed to assist the NRC staff
in prioritizing its review with respect to relative level of effort,
and to increase efficiency.
The purpose of this notice is to provide the public with an
opportunity to review and solicit comments on the Draft NUREG-1536,
Revision 1A, ``Standard Review Plan for Spent Fuel Dry Storage Systems
at a General License Facility''. These comments will be considered in
the final version or subsequent revisions.
II. Opportunity To Provide Comments
Comments and questions on Draft NUREG-1536, Revision 1A, should be
directed to Ron Parkhill, Thermal and Containment Branch, Division of
Spent Fuel Storage and Transportation, Office of Nuclear Materials
Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington,
DC 20005-0001 by July 14, 2009. Comments received after this date will
be considered if it is practical to do so, but only those comments
received on or before the due date can be assured consideration.
Comments can also be submitted by telephone, fax, or e-mail to the
following: Telephone: (301) 492-3324; fax number: (301) 492-3331; e-
mail: Ron.Parkhill@NRC.gov.
III. Further Information
Documents related to this action are available electronically at
the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this site, you can access the NRC's Agencywide
Document Access and Management System (ADAMS), which provides text and
image files of NRC's public documents. The ADAMS accession number for
the document related to this notice is [ML090400676]. If you do not
have access to ADAMS, or if there are problems in accessing the
documents located in ADAMS, contact the NRC Public Document Room (PDR)
reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to
pdr.resource@nrc.gov. ISGs that have been incorporated, as appropriate,
into the subject document can be viewed at https://www.nrc.gov/reading-rm/doc-collections/isg/spent-fuel.html. During the public comment
period for this document, other ISGs could be issued separately for
public comment, and may be incorporated into the final version of
NUREG-1536.
This document may also be viewed electronically on the public
computers located at the NRC's PDR, O-1 F21, One White Flint North,
11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction
contractor will copy documents for a fee.
Dated at Rockville, Maryland, this 2nd day of April, 2009.
[[Page 17547]]
For the Nuclear Regulatory Commission.
Nathan Sanfilippo,
Acting Chief, Thermal and Containment Branch, Division of Spent Fuel
Storage and Transportation, Office of Nuclear Materials Safety and
Safeguards.
[FR Doc. E9-8599 Filed 4-14-09; 8:45 am]
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