Issuance and Availability of Draft Regulatory Guide, 17547 [E9-8597]
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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
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[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:
VerDate Nov<24>2008
16:44 Apr 14, 2009
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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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April 13, 2009.
It appears to the Securities and
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Act of 1934, that trading in the
E:\FR\FM\15APN1.SGM
15APN1
Agencies
[Federal Register Volume 74, Number 71 (Wednesday, April 15, 2009)]
[Notices]
[Page 17547]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-8597]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[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.
SUPPLEMENTARY INFORMATION:
I. Introduction
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 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.
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 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/doc-collections/. 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]
BILLING CODE 7590-01-P