[Federal Register Volume 79, Number 74 (Thursday, April 17, 2014)]
[Notices]
[Pages 21811-21812]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2014-08792]
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NUCLEAR REGULATORY COMMISSION
[NRC-2014-0023]
Effect of LWR Coolant Environments on the Fatigue Life of Reactor
Materials
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft NUREG; request for comment.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for
public comment a draft NUREG, NUREG/CR-6909, Revision 1, ``Effect of
LWR Coolant Environments on the Fatigue Life of Reactor Materials.''
This report summarizes the results of NRC research efforts and work
performed at Argonne National Laboratory on the fatigue of piping and
pressure vessel steels in light water reactor environments. Revision 1
of this report provides updates and improvements to the environmental
fatigue correction factor approach based on an extensive update to
available laboratory fatigue data from testing and results available
since this report was first published in 2007.
DATES: Submit comments by June 2, 2014. Comments received after this
date will be considered if it is practical to do so, but the Commission
is able to ensure consideration only for comments received before this
date.
ADDRESSES: You may submit comments by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0023. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Mail comments to: Cindy Bladey, Chief, Rules,
Announcements, and Directives Branch, Office of Administration, Mail
Stop: 3WFN-06-44M, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
For additional direction on accessing information and submitting
comments, see ``Accessing Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Gary Stevens, Office of Nuclear
Regulatory Research, U.S. Nuclear Regulatory Commission, Washington DC
20555-0001; telephone: 301-251-7569, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2014-0023 when contacting the NRC
about the availability of information regarding this document. You may
access publicly-available information related to this document by any
of the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0023.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the
ADAMS Public Documents collection at http://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 [email protected]. The
draft of NUREG/CR-6909, Revision 1 is available in ADAMS under
Accession No. ML14087A068.
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.
B. Submitting Comments
Please include Docket ID NRC-2014-0023 in the subject line of your
comment submission, in order to ensure that the NRC is able to make
your comment submission available to the public in this docket.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in you
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment submissions into ADAMS.
II. Discussion
The American Society of Mechanical Engineers Boiler and Pressure
Vessel Code (Code) provides rules for the design of Class 1 components
of nuclear power plants. Appendix I to Section III of the Code contains
fatigue design curves for applicable structural materials. However, the
effects of light water reactor coolant environments are
[[Page 21812]]
not explicitly addressed by the Code design curves. The existing
fatigue strain-vs.-life data illustrate potentially significant effects
of light water reactor coolant environments on the fatigue resistance
of pressure vessel and piping steels. Under certain environmental and
loading conditions, fatigue lives in water relative to those in air can
be significantly lower for austenitic stainless, nickel alloy, carbon
and low-alloy steels. In March 2007, Revision 0 of NUREG/CR-6909 (ADAMS
Accession No. ML070660620) was issued and it was the technical basis
document for NRC Regulatory Guide 1.207, ``Guidelines for Evaluating
Fatigue Analyses Incorporating the Life Reduction of Metal Components
Due to the Effects of the Light-Water Reactor Environment for New
Reactors.'' Revision 0 of NUREG/CR-6909 summarized the work performed
at Argonne National Laboratory on the fatigue of piping and pressure
vessel steels in light water reactor coolant environments. In that
document, the existing laboratory fatigue data were evaluated to
identify the various materials, environmental, and loading parameters
that influence fatigue crack initiation, and document the effects of
key parameters on the fatigue lives of pressure vessel and piping
steels. The report presented fatigue life models for estimating fatigue
lives as a function of material, loading, and environmental conditions,
and described the environmental fatigue correction factor for
incorporating the effects of light water reactor coolant environments
into Code fatigue evaluations.
Revision 1 of NUREG/CR-6909 provides updates and improvements to
the environmental fatigue correction factor approach based on an
extensive update to the laboratory fatigue data from testing and
results available since 2007. The NRC is particularly interested in
stakeholder feedback on the following three areas:
i. The extension of the best-fit mean air curve for ferritic steels
discussed in Section 3.1.10.
ii. The air fatigue design curve adjustment factors summarized in
Section 5.5.
iii. Accuracy check of the technical content of the NUREG,
particularly with respect to all of the numerical content of the
report.
Dated at Rockville, Maryland, this 9th day of April, 2014.
For the Nuclear Regulatory Commission.
David L. Rudland,
Chief, Component Integrity Branch, Division of Engineering, Office of
Nuclear Regulatory Research.
[FR Doc. 2014-08792 Filed 4-16-14; 8:45 am]
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