NUREG-1482, Revision 2, “Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report for Comment”, 52355-52356 [2011-21357]
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Federal Register / Vol. 76, No. 162 / Monday, August 22, 2011 / Notices
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amended by the Antarctic Science,
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has developed regulations for the
establishment of a permit system for
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[FR Doc. 2011–21296 Filed 8–19–11; 8:45 am]
BILLING CODE 7555–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2010–0278]
NUREG–1482, Revision 2, ‘‘Guidelines
for Inservice Testing at Nuclear Power
Plants, Draft Report for Comment’’
Nuclear Regulatory
Commission.
ACTION: Announcement of issuance for
public comment, availability.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) has issued for public
comment a document entitled: NUREG–
1482, Revision 2, ‘‘Guidelines for
Inservice Testing at Nuclear Power
Plants, Draft Report for Comment,’’ and
subtitled ‘‘Inservice Testing of Pumps
and Valves, and Inservice Examination
and Testing of Dynamic Restraints
(Snubbers) at Nuclear Power Plants’’.
(Note that this document was
submitted previously for public
comments as draft NUREG–1946. Based
on public comments, draft NUREG–
1482 is being updated as Revision 2 and
jlentini on DSK4TPTVN1PROD with NOTICES
SUMMARY:
VerDate Mar<15>2010
17:16 Aug 19, 2011
Jkt 223001
is being issued to incorporate all
comments received for draft report
NUREG–1946).
DATES: Please submit comments by
December 20, 2011. Comments received
after this date will be considered if it is
practical to do so, but the NRC staff is
able to ensure consideration only for
comments received on or before this
date.
Please include Docket ID
NRC–2010–0278 in the subject line of
your comments. For additional
instructions on submitting comments
and instructions on accessing
documents related to this action, see
‘‘Submitting Comments and Accessing
Information’’ in the SUPPLEMENTARY
INFORMATION section of this document.
You may submit comments by any one
of the following methods:
• Federal Rulemaking Web Site: Go to
https://www.regulations.gov and search
for documents filed under Docket ID
NRC–2010–0278. Address questions
about NRC dockets to Carol Gallagher,
telephone: 301–492–3668; e-mail:
Carol.Gallagher@nrc.gov.
• Mail comments to: Cindy Bladey,
Chief, Rules, Announcements, and
Directives Branch (RADB), Office of
Administration, Mail Stop: TWB–05–
B01M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
• Fax comments to: RADB at 301–
492–3446.
SUPPLEMENTARY INFORMATION:
ADDRESSES:
Submitting Comments and Accessing
Information
Comments submitted in writing or in
electronic form will be posted on the
NRC Web site and on the Federal
rulemaking Web site, https://
www.regulations.gov. 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.
The NRC requests that any party
soliciting or aggregating comments
received from other persons for
submission to the NRC inform those
persons that the NRC will not edit their
comments to remove any identifying or
contact information, and therefore, they
should not include any information in
their comments that they do not want
publicly disclosed.
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
PO 00000
Frm 00053
Fmt 4703
Sfmt 4703
52355
documents at the NRC’s PDR, O1–F21,
One White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
• 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. From this page, the public
can gain entry into ADAMS, which
provides text and image files of the
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. The NUREG–
1482, Revision 2, ‘‘Guidelines for
Inservice Testing at Nuclear Power
Plants, Draft Report for Comment,’’ and
subtitled ‘‘Inservice Testing of Pumps
and Valves, and Inservice Examination
and Testing of Dynamic Restraints
(Snubbers) at Nuclear Power Plants’’ is
available electronically under ADAMS
Accession Number ML112231412.
• Federal Rulemaking Web Site:
Public comments and supporting
materials related to this notice can be
found at https://www.regulations.gov by
searching on Docket ID NRC–2010–
0278.
FOR FURTHER INFORMATION CONTACT:
Gurjendra S. Bedi, Division of
Component Integrity, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–415–
1393, e-mail: Gurjendra.Bedi@nrc.gov.
NUREG–1482, Revision 2,
‘‘Guidelines for Inservice Testing at
Nuclear Power Plants, Draft Report for
Comment’’ provides updated
information on applicable regulations
for testing of pumps and valves, and
inservice examination and testing of
snubbers. The information in NUREG–
1482, ‘‘Guidelines for Inservice Testing
at Nuclear Plants,’’ Revision 0, issued
April 1995, and Revision 1, issued
January 2005, has described these topics
in the past.
This NUREG report replaces Revision
0 and Revision 1 of NUREG–1482, and
is applicable, unless stated otherwise, to
all editions and addenda of the
American Society of Mechanical
Engineers (ASME) Code of Operation
and Maintenance of Nuclear Power
Plants (OM Code), which Title 10 of the
Code of Federal Regulations (10 CFR)
50.55a(b) incorporates by reference (76
FR 36232–36279), dated June 21, 2011.
Note that the draft NUREG–1482,
Revision 2, is a substantial re-write from
issuance of draft NUREG–1946 (ADAMS
E:\FR\FM\22AUN1.SGM
22AUN1
52356
Federal Register / Vol. 76, No. 162 / Monday, August 22, 2011 / Notices
Accession Number: ML102100236).
This draft NUREG–1482, Revision 2,
incorporates all the public comments
received for draft NUREG–1946, because
based on public comments, NUREG–
1482, Revision 1, is revised and updated
instead of issuing the new NUREG–
1946. The NRC staff evaluation and
resolution of public comments for draft
NUREG–1946, including Inservice
Testing Owner Group comments, are
documented in ADAMS Accession
Number: ML112092872. Most of the
draft NUREG–1946 included in the
main text of draft NUREG–1482,
Revision 2, Appendix A, to this
NUREG–1482, Revision 2, contains
guidance provided in Revision 1 to
NUREG–1482 for pumps and valves that
has been updated for the development
of inservice testing programs at nuclear
power plants. Appendix B to this
NUREG contains guidance related to
inservice examination and testing of
dynamic restraints (snubbers), which is
included for the first time in the draft
NUREG–1482, Revision 2.
The guidelines and recommendations
provided in this NUREG and its
Appendices A and B do not supersede
the regulatory requirements specified in
10 CFR 50.55a. Further, this NUREG
does not authorize the use of
alternatives to, or grant relief from, the
ASME Code requirements for inservice
testing of pumps and valves, or
inservice examination and testing of
dynamic restraints (snubbers),
incorporated by reference in 10 CFR
50.55a. In addition, the NUREG
discusses other inservice test program
topics such as the NRC process for
review of the OM Code, conditions on
the use of the OM Code, and
interpretations of the OM Code.
Dated at Rockville, Maryland, this 11th day
of August 2011.
For the Nuclear Regulatory Commission.
Anthony C. McMurtray,
Chief, Component Performance and Testing
Branch, Division of Component Integrity,
Office of Nuclear Reactor Regulation.
[FR Doc. 2011–21357 Filed 8–19–11; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
jlentini on DSK4TPTVN1PROD with NOTICES
[NRC–2011–0188; Docket No. 50–315]
Indiana Michigan Power Company,
Donald C. Cook Nuclear Plant, Unit 1;
Environmental Assessment and
Finding of No Significant Impact
The U.S. Nuclear Regulatory
Commission (NRC or the Commission)
is considering issuance of an exemption
VerDate Mar<15>2010
17:16 Aug 19, 2011
Jkt 223001
and an amendment to Renewed Facility
Operating License No. NPF–58 issued to
Indiana Michigan Power Company (the
licensee), for operation of Donald C.
Cook Nuclear Plant, Unit 1 (DCCNP–1),
located in Berrien County, Michigan, in
accordance with Title 10 of the Code of
Federal Regulations (10 CFR) part 50,
§ 50.90. In accordance with 10 CFR
51.21, the NRC performed an
environmental assessment documenting
its findings. The NRC concluded that
the proposed actions would have no
significant environmental impact.
Environmental Assessment
Identification of the Proposed Actions
The proposed actions would issue an
exemption from 10 CFR 50.46 regarding
fuel cladding material, and revise the
Technical Specifications document,
which is part of the Renewed Facility
Operating Licenses, to permit use of
Optimized ZIRLOTM fuel to a peak road
average burnup limit of 62 gigawattdays per metric ton uranium (GWD/
MTU).
The proposed actions are in
accordance with the licensee’s
application dated December 16, 2010.
The Need for the Proposed Actions
The proposed actions to issue an
exemption to the fuel cladding
requirement of 10 CFR 50.46, and to
amend the Technical Specifications to
permit use of Optimized ZIRLOTM fuel
to a peak rod average burnup limit of 62
GWD/MTU would allow for more
effective fuel management. If the
exemption and amendment are not
approved, the licensee will not be
provided the opportunity to use
Optimized ZIRLOTM fuel design with a
peak rod average burnup as high as 62
GWD/MTU; the licensee would thus
lose fuel management flexibility.
Environmental Impacts of the Proposed
Actions
In this environmental assessment
regarding the impacts of the use of
Optimized ZIRLOTM fuel with the
possible burnup up to 62 GWD/MTU,
the Commission is relying on the results
of the updated study conducted for the
NRC by the Pacific Northwest National
Laboratory (PNNL), entitled
‘‘Environmental Effects of Extending
Fuel Burnup Above 60 GWD/MTU’’
(NUREG/CR–6703, PNNL–13257,
January 2001). Environmental impacts
of high burnup fuel up to 75 GWD/MTU
were evaluated in the study, but some
aspects of the review were limited to
evaluating the impacts of the extended
burnup up to 62 GWD/MTU, because of
the need for additional data on the effect
PO 00000
Frm 00054
Fmt 4703
Sfmt 4703
of extended burnup on gap release
fractions. All the aspects of the fuelcycle were considered during the study,
from mining, milling, conversion,
enrichment and fabrication through
normal reactor operation,
transportation, waste management, and
storage of spent fuel.
The amendment and exemption
would allow DCCNP–1 to use
Optimized ZIRLOTM fuel up to a burnup
limit of 62 GWD/MTU. The NRC staff
has completed its evaluation of the
proposed actions and concludes that
such changes would not adversely affect
plant safety, and would have no adverse
effect on the probability of any accident.
For the accidents that involve damage or
melting of the fuel in the reactor core,
fuel rod integrity has been shown to be
unaffected by extended burnup under
consideration; therefore, the probability
of an accident will not be affected by
fuel burnup to 62 GWD/MTU. For the
accidents in which the reactor core
remains intact, the increased burnup
may slightly change the mix of fission
products that could be released in the
event of a serious accident, but because
the radionuclides contributing most to
the dose are short-lived, increased
burnup would not have an effect on the
consequences of a serious accident
beyond the consequences of previously
evaluated accident scenarios. Thus,
there will be no significant increase in
projected dose consequences of
postulated accidents associated with
fuel burnup up to 62 GWD/MTU, and
doses will remain well below regulatory
limits.
Regulatory limits on radiological
effluent releases are independent of
burnup. The requirements of 10 CFR
part 20, 10 CFR 50.36a, and Appendix
I to 10 CFR part 50 ensure that routine
releases of gaseous, liquid or solid
radiological effluents to unrestricted
areas is kept ‘‘As Low As is Reasonably
Achievable.’’ Therefore, the NRC staff
concludes that during routine
operations, there would be no
significant increase in the amount of
gaseous radiological effluents released
into the environment as a result of the
proposed actions, nor will there be a
significant increase in the amount of
liquid radiological effluents or solid
radiological effluents released into the
environment.
The proposed actions will not change
normal plant operating conditions (i.e.,
no changes are expected in the fuel
handling, operational, or storing
processes). The fuel storage and
handling, radioactive waste, and other
systems which may contain
radioactivity are designed to assure
adequate safety under normal
E:\FR\FM\22AUN1.SGM
22AUN1
Agencies
[Federal Register Volume 76, Number 162 (Monday, August 22, 2011)]
[Notices]
[Pages 52355-52356]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2011-21357]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2010-0278]
NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at
Nuclear Power Plants, Draft Report for Comment''
AGENCY: Nuclear Regulatory Commission.
ACTION: Announcement of issuance for public comment, availability.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has issued for
public comment a document entitled: NUREG-1482, Revision 2,
``Guidelines for Inservice Testing at Nuclear Power Plants, Draft
Report for Comment,'' and subtitled ``Inservice Testing of Pumps and
Valves, and Inservice Examination and Testing of Dynamic Restraints
(Snubbers) at Nuclear Power Plants''.
(Note that this document was submitted previously for public
comments as draft NUREG-1946. Based on public comments, draft NUREG-
1482 is being updated as Revision 2 and is being issued to incorporate
all comments received for draft report NUREG-1946).
DATES: Please submit comments by December 20, 2011. Comments received
after this date will be considered if it is practical to do so, but the
NRC staff is able to ensure consideration only for comments received on
or before this date.
ADDRESSES: Please include Docket ID NRC-2010-0278 in the subject line
of your comments. For additional instructions on submitting comments
and instructions on accessing documents related to this action, see
``Submitting Comments and Accessing Information'' in the SUPPLEMENTARY
INFORMATION section of this document. You may submit comments by any
one of the following methods:
Federal Rulemaking Web Site: Go to https://www.regulations.gov and search for documents filed under Docket ID NRC-
2010-0278. Address questions about NRC dockets to Carol Gallagher,
telephone: 301-492-3668; e-mail: Carol.Gallagher@nrc.gov.
Mail comments to: Cindy Bladey, Chief, Rules,
Announcements, and Directives Branch (RADB), Office of Administration,
Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
Fax comments to: RADB at 301-492-3446.
SUPPLEMENTARY INFORMATION:
Submitting Comments and Accessing Information
Comments submitted in writing or in electronic form will be posted
on the NRC Web site and on the Federal rulemaking Web site, https://www.regulations.gov. 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.
The NRC requests that any party soliciting or aggregating comments
received from other persons for submission to the NRC inform those
persons that the NRC will not edit their comments to remove any
identifying or contact information, and therefore, they should not
include any information in their comments that they do not want
publicly disclosed.
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, O1-F21, One White Flint North, 11555 Rockville Pike, Rockville,
Maryland 20852.
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. From this page, the public can gain entry into ADAMS,
which provides text and image files of the 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.
The NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at
Nuclear Power Plants, Draft Report for Comment,'' and subtitled
``Inservice Testing of Pumps and Valves, and Inservice Examination and
Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants'' is
available electronically under ADAMS Accession Number ML112231412.
Federal Rulemaking Web Site: Public comments and
supporting materials related to this notice can be found at https://www.regulations.gov by searching on Docket ID NRC-2010-0278.
FOR FURTHER INFORMATION CONTACT: Gurjendra S. Bedi, Division of
Component Integrity, Office of Nuclear Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone: 301-415-
1393, e-mail: Gurjendra.Bedi@nrc.gov.
NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at
Nuclear Power Plants, Draft Report for Comment'' provides updated
information on applicable regulations for testing of pumps and valves,
and inservice examination and testing of snubbers. The information in
NUREG-1482, ``Guidelines for Inservice Testing at Nuclear Plants,''
Revision 0, issued April 1995, and Revision 1, issued January 2005, has
described these topics in the past.
This NUREG report replaces Revision 0 and Revision 1 of NUREG-1482,
and is applicable, unless stated otherwise, to all editions and addenda
of the American Society of Mechanical Engineers (ASME) Code of
Operation and Maintenance of Nuclear Power Plants (OM Code), which
Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(b)
incorporates by reference (76 FR 36232-36279), dated June 21, 2011.
Note that the draft NUREG-1482, Revision 2, is a substantial re-write
from issuance of draft NUREG-1946 (ADAMS
[[Page 52356]]
Accession Number: ML102100236). This draft NUREG-1482, Revision 2,
incorporates all the public comments received for draft NUREG-1946,
because based on public comments, NUREG-1482, Revision 1, is revised
and updated instead of issuing the new NUREG-1946. The NRC staff
evaluation and resolution of public comments for draft NUREG-1946,
including Inservice Testing Owner Group comments, are documented in
ADAMS Accession Number: ML112092872. Most of the draft NUREG-1946
included in the main text of draft NUREG-1482, Revision 2, Appendix A,
to this NUREG-1482, Revision 2, contains guidance provided in Revision
1 to NUREG-1482 for pumps and valves that has been updated for the
development of inservice testing programs at nuclear power plants.
Appendix B to this NUREG contains guidance related to inservice
examination and testing of dynamic restraints (snubbers), which is
included for the first time in the draft NUREG-1482, Revision 2.
The guidelines and recommendations provided in this NUREG and its
Appendices A and B do not supersede the regulatory requirements
specified in 10 CFR 50.55a. Further, this NUREG does not authorize the
use of alternatives to, or grant relief from, the ASME Code
requirements for inservice testing of pumps and valves, or inservice
examination and testing of dynamic restraints (snubbers), incorporated
by reference in 10 CFR 50.55a. In addition, the NUREG discusses other
inservice test program topics such as the NRC process for review of the
OM Code, conditions on the use of the OM Code, and interpretations of
the OM Code.
Dated at Rockville, Maryland, this 11th day of August 2011.
For the Nuclear Regulatory Commission.
Anthony C. McMurtray,
Chief, Component Performance and Testing Branch, Division of Component
Integrity, Office of Nuclear Reactor Regulation.
[FR Doc. 2011-21357 Filed 8-19-11; 8:45 am]
BILLING CODE 7590-01-P