Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants, 58574-58575 [2013-23250]
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Federal Register / Vol. 78, No. 185 / Tuesday, September 24, 2013 / Notices
Meeting) (Contact: George Wilson, 301–
415–1711)
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
September 19, 2013.
Rochelle C. Bavol,
Policy Coordinator, Office of the Secretary.
Friday, October 18, 2013
BILLING CODE 7590–01–P
9:00 a.m. Meeting with the Advisory
Committee on the Medical Uses of
Isotopes (Public Meeting) (Contact:
Sophie Holiday, 301–415–7865)
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
1:00 p.m. Briefing on Proposed
Rulemaking Concerning the Medical
Use of Byproduct Material (Public
Meeting) (Contact: Ashley Cockerham,
240–888–7129)
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
Week of October 21, 2013—Tentative
Week of October 28, 2013—Tentative
mstockstill on DSK4VPTVN1PROD with NOTICES
Thursday, October 31, 2013
10:00 a.m. NRC All Employees
Meeting (Public Meeting) Marriott
Bethesda North Hotel 5701 Marinelli
Road, Rockville, MD 20852
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The schedule for Commission
meetings is subject to change on short
notice. To verify the status of meetings,
call (recording)—301–415–1292.
Contact person for more information:
Rochelle Bavol, 301–415–1651.
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The NRC Commission Meeting
Schedule can be found on the Internet
at: https://www.nrc.gov/public-involve/
public-meetings/schedule.html.
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The NRC provides reasonable
accommodation to individuals with
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need a reasonable accommodation to
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need this meeting notice or the
transcript or other information from the
public meetings in another format (e.g.
braille, large print), please notify
Kimberly Meyer, NRC Disability
Program Manager, at 301–287–0727, or
by email at Kimberly.MeyerChambers@nrc.gov. Determinations on
requests for reasonable accommodation
will be made on a case-by-case basis.
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19:49 Sep 23, 2013
Jkt 229001
NUCLEAR REGULATORY
COMMISSION
[NRC–2013–0048]
Maintenance, Testing, and
Replacement of Vented Lead-Acid
Storage Batteries for Nuclear Power
Plants
Nuclear Regulatory
Commission.
ACTION: Regulatory guide; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing Revision 3
of Regulatory Guide (RG) 1.129,
‘‘Maintenance, Testing, and
Replacement of Vented Lead-Acid
Storage Batteries for Nuclear Power
Plants.’’ The guide describes methods
that the NRC staff considers acceptable
for use in complying with the agency’s
regulations with regard to the
maintenance, testing, and replacement
of vented lead-acid storage batteries in
nuclear power plants.
ADDRESSES: Please refer to Docket ID
NRC–2013–0048 when contacting the
NRC about the availability of
information regarding this document.
You may access publicly-available
information related to this action by the
following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2013–0048. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual(s) listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publicly
available documents online in the NRC
Library at https://www.nrc.gov/readingrm/adams.html. To begin the search,
select ‘‘ADAMS Public Documents’’ and
then 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
ADAMS accession number for each
document referenced in this notice (if
that document is available in ADAMS)
is provided the first time that a
document is referenced. Revision 3 of
SUMMARY:
There are no meetings scheduled for
the week of October 21, 2013.
VerDate Mar<15>2010
[FR Doc. 2013–23310 Filed 9–20–13; 4:15 pm]
PO 00000
Frm 00064
Fmt 4703
Sfmt 4703
Regulatory Guide 1.129 is available in
ADAMS under Accession No.
ML13170A112. The regulatory analysis
may be found in ADAMS under
Accession No. ML13170A116.
• 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.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT:
Liliana Ramadan, telephone: 301–251–
7642; email: Liliana.Ramadan@nrc.gov;
or Edward O’Donnell, telephone: 301–
251–7455; email: Edward.Odonnell@
nrc.gov. Both of the Office of Nuclear
Regulatory Research, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing a revision to an
existing guide in the NRC’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.
The NRC developed RG 1.129 to
describe a method that the NRC staff
considers acceptable for use in
complying with the agency’s regulations
with regard to the maintenance, testing,
and replacement of vented lead-acid
storage batteries in nuclear power
plants. Specifically, the method
described in this regulatory guide
relates to General Design Criteria (GDC)
1, 17, and 18 as set forth in appendix
A, ‘‘General Design Criteria for Nuclear
Power Plants,’’ to part 50 of Title 10 of
the Code of Federal Regulations (10
CFR), ‘‘Domestic Licensing of
Production and Utilization Facilities.’’
The NRC issued Revision 3 of RG
1.129 with a temporary identification as
Draft Regulatory Guide, DG–1269, in the
Federal Register on March 12, 2013 (78
FR 15753), for a 60-day public comment
period. The public comment period
closed on May 13, 2013, and the NRC
staff’s response to the comments can be
found in ADAMS under Accession No.
ML13170A114.
RG 1.129, Revision 3 endorses (with
certain clarifying regulatory positions)
the Institute of Electrical and
Electronics Engineers (IEEE) Std 450–
E:\FR\FM\24SEN1.SGM
24SEN1
Federal Register / Vol. 78, No. 185 / Tuesday, September 24, 2013 / Notices
2010, ‘‘IEEE Recommended Practice for
Maintenance, Testing, and Replacement
of Vented Lead-Acid Batteries for
Stationary Applications.’’ That standard
is an update of IEEE Std 450–2002,
which formed the basis for RG 1.129,
Revision 2. The revised IEEE Std 450–
2010 refines the condition monitoring
guidance and the use of rate-adjusted
test methods for acceptance testing to
ensure consistent performance of vented
lead-acid batteries. Among the changes
in RG 1.129, Revision 3 from the prior
version is the deletion of clarifying
regulatory positions 6 and 8. The former
is addressed by IEEE 450–2010 and is
not needed. The latter provides
information on optional test methods
and, unless otherwise stated in a
regulatory position, this endorsement of
IEEE–450–2010 does not apply to them.
Therefore it is superfluous.
Revision 3 of RG 1.129 represents the
NRC staff’s current guidance for future
users and applications. Earlier versions
of this regulatory guide, however,
continue to be acceptable for those
licensees whose licensing basis includes
earlier versions of this regulatory guide,
absent a licensee-initiated change to its
licensing basis. Additional information
on the NRC staff’s use of this revised
regulatory guide with respect to both
current and future users and
applications is set forth in the
‘‘Implementation’’ section of the revised
regulatory guide.
mstockstill on DSK4VPTVN1PROD with NOTICES
II. Congressional Review Act
This regulatory guide is a rule as
defined in the Congressional Review
Act (5 U.S.C. 801–808). However, the
Office of Management and Budget has
not found it to be a major rule as
defined in the Congressional Review
Act.
III. Backfitting and Issue Finality
Regulatory Guide 1.129, Revision 3,
does not constitute backfitting as
defined in 10 CFR 50.109 (the Backfit
Rule) and is not otherwise inconsistent
with the issue finality provisions in 10
CFR part 52, ‘‘Licenses, Certifications
and Approvals for Nuclear Power
Plants.’’ Revision 3 of this regulatory
guide provides guidance on one
possible means for meeting NRC’s
regulatory requirements with regard to
the maintenance, testing, and
replacement of vented lead-acid storage
batteries in nuclear power plants in
GDCs 1, 17 and 18, and the qualification
testing requirements of Criterion III of
10 CFR Part 50, Appendix B. Existing
licensees and applicants of final design
certification rules will not be required to
comply with the positions set forth in
Revision 3 of this regulatory guide,
VerDate Mar<15>2010
19:49 Sep 23, 2013
Jkt 229001
unless the licensee or design
certification rule applicant seeks a
voluntary change to its licensing basis
with respect to safety-related power
operated valve actuators, and where the
NRC determines that the safety review
must include consideration of the
qualification of the valve actuators.
Further information on the staff’s use of
the Regulatory Guide 1.129, Revision 3,
is contained in the regulatory guide
under section D. Implementation.
Dated at Rockville, Maryland, this 16th day
of September, 2013.
For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guide Development Branch,
Division of Engineering, Office of Nuclear
Regulatory Research.
[FR Doc. 2013–23250 Filed 9–23–13; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2013–0219]
Review of Experiments for Research
Reactors
Nuclear Regulatory
Commission.
ACTION: Regulatory guide; withdrawal.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is withdrawing
Regulatory Guide (RG) 2.4, ‘‘Review of
Experiments for Research Reactors.’’
The guide is being withdrawn because
the industry standard which it referred
to has been withdrawn, and
corresponding information is available
in other NRC guidance. ADDRESSES:
Please refer to Docket ID NRC–2013–
0219 when contacting the NRC about
the availability of information regarding
this document. You may access
publicly-available information related to
this action by the following methods:
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): Publicly available documents
created or received at the NRC are
available online in the NRC Library at
https://www.nrc.gov/reading-rm/
adams.html. To begin search, select
‘‘ADAMS Public Documents’’ and then
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, or 301–415–4737, or
by email at PDR.Resource@nrc.gov. The
ADAMS accession number for each
document referenced in this notice (if
that document is available in ADAMS)
is provided the first time that a
document is referenced. The review for
the withdrawal of RG 2.4 is available in
SUMMARY:
PO 00000
Frm 00065
Fmt 4703
Sfmt 4703
58575
ADAMS under Accession No.
ML13143A453.
• 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, MD 20852.
The documents are not copyrighted
and NRC approval is not required to
reproduce them. FOR FURTHER
INFORMATION CONTACT: Alexander
Adams Jr., telephone: 301–415–1127, by
email at Alexander.Adams@nrc.gov,
Office of Nuclear Reactor Regulation,
U.S. Nuclear Regulatory Commission,
Washington DC 20555–0001; or Richard
Jervey, telephone: 301–251–7404, by
email at Richard.Jervey@nrc.gov, Office
of Nuclear Regulatory Research, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is withdrawing RG 2.4,
‘‘Review of Experiments for Research
Reactors,’’ (ADAMS Accession No.
ML003740131) because its guidance no
longer provides useful information. RG
2.4 was published in July 1976 to
provide clarification on meeting the
requirements in part 50 of Title 10 of the
Code of Federal Regulations (10 CFR),
‘‘Domestic Licensing of Production and
Utilization Facilities,’’ for procedures
acceptable to the NRC staff for a
licensee’s review and approval of
experiments performed at research
reactor facilities. The NRC published RG
2.4 to endorse American National
Standards Institute (ANSI) N401–1974
(American Nuclear Society (ANS) 15.6),
‘‘Review of Experiments for Research
Reactors,’’ with exceptions and
additional considerations, concerning
performance of experiments which
could be undertaken without affecting
conditions of the facility license and
thus could be performed without prior
NRC approval. In 1982, ANS replaced
the N401 (ANS 15.6) standard with ANS
15.1, ‘‘American National Standard for
the Development of Technical
Specifications for Research Reactors.’’
ANS 15.6 is no longer supported by
ANS or available in print. RG 2.4 was
written using the text of ANS 15.6 for
reference, and because the standard no
longer exists, the text within the RG no
longer provides useful information.
II. Further Information
The withdrawal of RG 2.4 does not
alter any prior or existing licensing
commitments based on its use.
Regulatory guides may be withdrawn
when their guidance no longer provides
useful information, or is superseded by
technological innovations,
E:\FR\FM\24SEN1.SGM
24SEN1
]]>Agencies
[Federal Register Volume 78, Number 185 (Tuesday, September 24, 2013)]
[Notices]
[Pages 58574-58575]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-23250]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2013-0048]
Maintenance, Testing, and Replacement of Vented Lead-Acid Storage
Batteries for Nuclear Power Plants
AGENCY: Nuclear Regulatory Commission.
ACTION: Regulatory guide; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing
Revision 3 of Regulatory Guide (RG) 1.129, ``Maintenance, Testing, and
Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power
Plants.'' The guide describes methods that the NRC staff considers
acceptable for use in complying with the agency's regulations with
regard to the maintenance, testing, and replacement of vented lead-acid
storage batteries in nuclear power plants.
ADDRESSES: Please refer to Docket ID NRC-2013-0048 when contacting the
NRC about the availability of information regarding this document. You
may access publicly-available information related to this action by the
following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2013-0048. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual(s) listed in the FOR FURTHER INFORMATION CONTACT section
of this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at https://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then 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 ADAMS accession number
for each document referenced in this notice (if that document is
available in ADAMS) is provided the first time that a document is
referenced. Revision 3 of Regulatory Guide 1.129 is available in ADAMS
under Accession No. ML13170A112. The regulatory analysis may be found
in ADAMS under Accession No. ML13170A116.
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.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT: Liliana Ramadan, telephone: 301-251-
7642; email: Liliana.Ramadan@nrc.gov; or Edward O'Donnell, telephone:
301-251-7455; email: Edward.Odonnell@nrc.gov. Both of the Office of
Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing a revision to an existing guide in the NRC'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.
The NRC developed RG 1.129 to describe a method that the NRC staff
considers acceptable for use in complying with the agency's regulations
with regard to the maintenance, testing, and replacement of vented
lead-acid storage batteries in nuclear power plants. Specifically, the
method described in this regulatory guide relates to General Design
Criteria (GDC) 1, 17, and 18 as set forth in appendix A, ``General
Design Criteria for Nuclear Power Plants,'' to part 50 of Title 10 of
the Code of Federal Regulations (10 CFR), ``Domestic Licensing of
Production and Utilization Facilities.''
The NRC issued Revision 3 of RG 1.129 with a temporary
identification as Draft Regulatory Guide, DG-1269, in the Federal
Register on March 12, 2013 (78 FR 15753), for a 60-day public comment
period. The public comment period closed on May 13, 2013, and the NRC
staff's response to the comments can be found in ADAMS under Accession
No. ML13170A114.
RG 1.129, Revision 3 endorses (with certain clarifying regulatory
positions) the Institute of Electrical and Electronics Engineers (IEEE)
Std 450-
[[Page 58575]]
2010, ``IEEE Recommended Practice for Maintenance, Testing, and
Replacement of Vented Lead-Acid Batteries for Stationary
Applications.'' That standard is an update of IEEE Std 450-2002, which
formed the basis for RG 1.129, Revision 2. The revised IEEE Std 450-
2010 refines the condition monitoring guidance and the use of rate-
adjusted test methods for acceptance testing to ensure consistent
performance of vented lead-acid batteries. Among the changes in RG
1.129, Revision 3 from the prior version is the deletion of clarifying
regulatory positions 6 and 8. The former is addressed by IEEE 450-2010
and is not needed. The latter provides information on optional test
methods and, unless otherwise stated in a regulatory position, this
endorsement of IEEE-450-2010 does not apply to them. Therefore it is
superfluous.
Revision 3 of RG 1.129 represents the NRC staff's current guidance
for future users and applications. Earlier versions of this regulatory
guide, however, continue to be acceptable for those licensees whose
licensing basis includes earlier versions of this regulatory guide,
absent a licensee-initiated change to its licensing basis. Additional
information on the NRC staff's use of this revised regulatory guide
with respect to both current and future users and applications is set
forth in the ``Implementation'' section of the revised regulatory
guide.
II. Congressional Review Act
This regulatory guide is a rule as defined in the Congressional
Review Act (5 U.S.C. 801-808). However, the Office of Management and
Budget has not found it to be a major rule as defined in the
Congressional Review Act.
III. Backfitting and Issue Finality
Regulatory Guide 1.129, Revision 3, does not constitute backfitting
as defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise
inconsistent with the issue finality provisions in 10 CFR part 52,
``Licenses, Certifications and Approvals for Nuclear Power Plants.''
Revision 3 of this regulatory guide provides guidance on one possible
means for meeting NRC's regulatory requirements with regard to the
maintenance, testing, and replacement of vented lead-acid storage
batteries in nuclear power plants in GDCs 1, 17 and 18, and the
qualification testing requirements of Criterion III of 10 CFR Part 50,
Appendix B. Existing licensees and applicants of final design
certification rules will not be required to comply with the positions
set forth in Revision 3 of this regulatory guide, unless the licensee
or design certification rule applicant seeks a voluntary change to its
licensing basis with respect to safety-related power operated valve
actuators, and where the NRC determines that the safety review must
include consideration of the qualification of the valve actuators.
Further information on the staff's use of the Regulatory Guide 1.129,
Revision 3, is contained in the regulatory guide under section D.
Implementation.
Dated at Rockville, Maryland, this 16th day of September, 2013.
For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guide Development Branch, Division of Engineering,
Office of Nuclear Regulatory Research.
[FR Doc. 2013-23250 Filed 9-23-13; 8:45 am]
BILLING CODE 7590-01-P
