Final Regulatory Guide: Issuance, Availability, 189 [2010-33072]
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Federal Register / Vol. 76, No. 1 / Monday, January 3, 2011 / Notices
For the Nuclear Regulatory Commission.
Robert J. Pascarelli,
Chief, Plant Licensing Branch III–1, Division
of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2010–33073 Filed 12–30–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2010–0265]
Final Regulatory Guide: Issuance,
Availability
II. Further Information
Nuclear Regulatory
Commission.
ACTION: Notice of Issuance and
Availability of Regulatory Guide 3.71,
Revision 2, ‘‘Nuclear Criticality Safety
Standards for Fuels and Material
Facilities.’’
AGENCY:
jlentini on DSKJ8SOYB1PROD with NOTICES
FOR FURTHER INFORMATION CONTACT:
Tamara D. Powell, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–492–
3211 or e-mail: Tamara.Powell@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a revision
to an existing guide in the agency’s
‘‘Regulatory Guide’’ series. This series
was developed to describe and make
available to the public information such
as methods that are acceptable to the
NRC staff for implementing specific
parts of the agency’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.
Revision 2 of Regulatory Guide 3.71,
entitled, ‘‘Nuclear Criticality Safety
Standards for Fuels and Material
Facilities,’’ was issued with a temporary
identification as Draft Regulatory Guide,
DG–3030. Regulatory Guide 3.71
provides applicants, licensees, and
certificate holders with updated
guidance concerning criticality safety
standards that the NRC has endorsed for
use with nuclear fuels and material
facilities. As such, Regulatory Guide
3.71 describes methods that the NRC
staff considers acceptable for complying
with the NRC’s regulations in Title 10,
of the Code of Federal Regulations, parts
70, ‘‘Domestic Licensing of Special
Nuclear Material,’’ and 76, ‘‘Certification
of Gaseous Diffusion Plants’’ (10 CFR
parts 70 and 76).
The NRC staff has revised Regulatory
Guide 3.71 to provide guidance on
complying with these portions of the
VerDate Mar<15>2010
15:48 Dec 30, 2010
Jkt 223001
NRC’s regulations. This guide describes
procedures for preventing nuclear
criticality accidents in operations that
involve handling, processing, storing,
and/or transporting special nuclear
material at fuel and material facilities. It
also endorses specific nuclear criticality
safety standards developed by the
American Nuclear Society’s Standards
Subcommittee 8 (ANS–8), ‘‘Operations
with Fissionable Materials Outside
Reactors.’’ Regulatory Guide 3.71 is not
intended for use by nuclear reactor
licensees.
In July 2010, DG–3030 was published
with a public comment period of 60
days from the issuance of the guide. The
public comment period closed on
September 29, 2010. The staff’s
responses to the public comments
received are located in the NRC’s
Agencywide Documents Access and
Management System under Accession
Number ML103210349. Electronic
copies of Regulatory guide 3.71,
Revision 2 are available through the
NRC’s public Web site under
‘‘Regulatory Guides’’ at https://
www.nrc.gov/reading-rm/doccollections/.
In addition, regulatory guides are
available for inspection at the NRC’s
Public Document Room (PDR) located at
Room O–1F 21, 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: 301–
415–4737 or 800–397–4209, by fax:
301–415–3548, and by e-mail:
pdr@nrc.gov.
Regulatory guides are not
copyrighted, and Commission approval
is not required to reproduce them.
Dated at Rockville, Maryland this 23rd day
of December 2010.
For the Nuclear Regulatory Commission.
John N. Ridgely,
Acting Chief, Regulatory Guide Development
Branch, Division of Engineering, Office of
Nuclear Regulatory Research.
[FR Doc. 2010–33072 Filed 12–30–10; 8:45 am]
BILLING CODE 7590–01–P
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189
NUCLEAR REGULATORY
COMMISSION
[NRC–2009–0444]
Notice of Availability of the Models for
Plant-Specific Adoption of Technical
Specifications Task Force Traveler
TSTF–513, Revision 3, ‘‘Revise PWR
Operability Requirements and Actions
for RCS Leakage Instrumentation’’
AGENCY: U.S. Nuclear Regulatory
Commission (NRC).
ACTION: Notice of Availability.
SUMMARY: As part of the consolidated
line item improvement process (CLIIP),
the NRC is announcing the availability
of the model application (with model no
significant hazards consideration
determination) and model safety
evaluation (SE) for the plant-specific
adoption of Technical Specifications
Task Force (TSTF) Traveler TSTF–513,
Revision 3, ‘‘Revise PWR [pressurized
water reactor] Operability Requirements
and Actions for RCS [reactor coolant
system] Leakage Instrumentation.’’
TSTF–513, Revision 3, is available in
the Agencywide Documents Access and
Management System (ADAMS) under
Accession Number ML102360355. The
proposed changes would revise the
Standard Technical Specifications (STS)
to define a new time limit for restoring
inoperable RCS leakage detection
instrumentation to operable status and
establish alternate methods of
monitoring RCS leakage when one or
more required monitors are inoperable.
Changes to the Technical Specifications
(TS) Bases are included, which reflect
the proposed changes and more
accurately reflect the contents of the
facility design bases related to the
operability of the RCS leakage detection
instrumentation. The CLIIP model SE
will facilitate expedited approval of
plant-specific adoption of TSTF–513,
Revision 3.
Documents: You can access publicly
available documents related to this
notice 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 O1 F21, 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
E:\FR\FM\03JAN1.SGM
03JAN1
Agencies
[Federal Register Volume 76, Number 1 (Monday, January 3, 2011)]
[Notices]
[Page 189]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-33072]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2010-0265]
Final Regulatory Guide: Issuance, Availability
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of Issuance and Availability of Regulatory Guide 3.71,
Revision 2, ``Nuclear Criticality Safety Standards for Fuels and
Material Facilities.''
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Tamara D. Powell, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone: 301-492-
3211 or e-mail: Tamara.Powell@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision
to an existing guide in the agency's ``Regulatory Guide'' series. This
series was developed to describe and make available to the public
information such as methods that are acceptable to the NRC staff for
implementing specific parts of the agency'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.
Revision 2 of Regulatory Guide 3.71, entitled, ``Nuclear
Criticality Safety Standards for Fuels and Material Facilities,'' was
issued with a temporary identification as Draft Regulatory Guide, DG-
3030. Regulatory Guide 3.71 provides applicants, licensees, and
certificate holders with updated guidance concerning criticality safety
standards that the NRC has endorsed for use with nuclear fuels and
material facilities. As such, Regulatory Guide 3.71 describes methods
that the NRC staff considers acceptable for complying with the NRC's
regulations in Title 10, of the Code of Federal Regulations, parts 70,
``Domestic Licensing of Special Nuclear Material,'' and 76,
``Certification of Gaseous Diffusion Plants'' (10 CFR parts 70 and 76).
The NRC staff has revised Regulatory Guide 3.71 to provide guidance
on complying with these portions of the NRC's regulations. This guide
describes procedures for preventing nuclear criticality accidents in
operations that involve handling, processing, storing, and/or
transporting special nuclear material at fuel and material facilities.
It also endorses specific nuclear criticality safety standards
developed by the American Nuclear Society's Standards Subcommittee 8
(ANS-8), ``Operations with Fissionable Materials Outside Reactors.''
Regulatory Guide 3.71 is not intended for use by nuclear reactor
licensees.
II. Further Information
In July 2010, DG-3030 was published with a public comment period of
60 days from the issuance of the guide. The public comment period
closed on September 29, 2010. The staff's responses to the public
comments received are located in the NRC's Agencywide Documents Access
and Management System under Accession Number ML103210349. Electronic
copies of Regulatory guide 3.71, Revision 2 are available through the
NRC's public Web site under ``Regulatory Guides'' at https://www.nrc.gov/reading-rm/doc-collections/.
In addition, regulatory guides are available for inspection at the
NRC's Public Document Room (PDR) located at Room O-1F 21, 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: 301-415-4737 or 800-397-4209, by fax:
301-415-3548, and by e-mail: pdr@nrc.gov.
Regulatory guides are not copyrighted, and Commission approval is
not required to reproduce them.
Dated at Rockville, Maryland this 23rd day of December 2010.
For the Nuclear Regulatory Commission.
John N. Ridgely,
Acting Chief, Regulatory Guide Development Branch, Division of
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2010-33072 Filed 12-30-10; 8:45 am]
BILLING CODE 7590-01-P