Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, 21811-21812 [2014-08792]

Download as PDF Federal Register / Vol. 79, No. 74 / Thursday, April 17, 2014 / Notices Total Burden Cost (operating/ maintenance): $0. Comments submitted in response to this notice will be summarized and/or included in the request for Office of Management and Budget approval of the information collection request; they will also become a matter of public record. Dated: April 11, 2014. Yoon Ferguson, Agency Clearance Officer, Office of Workers’ Compensation Programs, US Department of Labor. [FR Doc. 2014–08812 Filed 4–16–14; 8:45 am] BILLING CODE 4510–CK–P MARINE MAMMAL COMMISSION Sunshine Act Notice: Correction The Marine Mammal Commission published a notice in the Federal Register on 11 April 2014 announcing a meeting of the Commission. This document contains a correction to that notice, regarding the dates of the meeting. The Marine Mammal Commission and its Committee of Scientific Advisors on Marine Mammals will meet on Tuesday, 6 May 2014, from 9:00 a.m. to 5:30 p.m.; Wednesday, 7 May 2014, from 9:00 a.m. to 5:30 p.m.; Thursday, 8 May 2014, from 9:30 a.m. to 5:00 p.m. The Commission and the Committee also will meet in executive session on Monday, 5 May 2014, from 2:00 to 6:00 p.m. All other portions of the 11 April notice remain unchanged. CONTACT PERSON FOR MORE INFORMATION: Michael L. Gosliner, General Counsel, Marine Mammal Commission, 4340 East-West Highway, Room 700, Bethesda, MD 20814; (301) 504–0087; email: mgosliner@mmc.gov. TIME AND DATE: Dated: April 14, 2014. Rebecca J. Lent, Executive Director. [FR Doc. 2014–08817 Filed 4–15–14; 11:15 am] BILLING CODE 6820–31–P NUCLEAR REGULATORY COMMISSION TKELLEY on DSK3SPTVN1PROD with NOTICES [NRC–2014–0023] Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials Nuclear Regulatory Commission. ACTION: Draft NUREG; request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for public SUMMARY: VerDate Mar<15>2010 17:28 Apr 16, 2014 Jkt 232001 21811 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 https://www.regulations.gov and search for Docket ID NRC–2014–0023. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; email: Carol.Gallagher@nrc.gov. 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: Gary.Stevens@nrc.gov. SUPPLEMENTARY INFORMATION: • Federal Rulemaking Web site: Go to https://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 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 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. I. Accessing Information and Submitting Comments 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 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: PO 00000 Frm 00101 Fmt 4703 Sfmt 4703 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 https:// 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. E:\FR\FM\17APN1.SGM 17APN1 TKELLEY on DSK3SPTVN1PROD with NOTICES 21812 Federal Register / Vol. 79, No. 74 / Thursday, April 17, 2014 / Notices 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 lowalloy 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. VerDate Mar<15>2010 17:28 Apr 16, 2014 Jkt 232001 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] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2014–0085] Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components Nuclear Regulatory Commission. ACTION: Draft regulatory issue summary; request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on draft regulatory issue summary (RIS) 2014–XX. This draft RIS would provide guidance to applicants for, and holders of, nuclear power reactor licenses, construction permits, standard design approvals, and manufacturing licenses, and applicants for standard design certifications, on the scope and detail of information that should be provided in licensing applications regarding reactor vessel fracture toughness and associated pressure-temperature limits. DATES: Submit comments by May 19, 2014. Comments received after this date will be considered if it is practical to do so, but the NRC is able to assure consideration only for comments received on or before this date. ADDRESSES: You may submit comment 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 https://www.regulations.gov and search for Docket ID NRC–2014–0085. 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. • Mail comments to: Cindy Bladey, Chief, Rules, Announcements, and Directives Branch (RADB), 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, SUMMARY: PO 00000 Frm 00102 Fmt 4703 Sfmt 4703 see ‘‘Accessing Information and Submitting Comments’’ in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: Alexandra Popova, Office of Nuclear Reactor Regulation (NRR), telephone: 301–415–2876, email: Alexandra.Popova@nrc.gov; or Tanya Mensah, NRR, telephone: 301–415– 3610, email: Tanya.Mensah@nrc.gov, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. SUPPLEMENTARY INFORMATION: I. Accessing Information and Submitting Comments A. Accessing Information Please refer to Docket ID NRC–2014– 0085 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–2014–0085. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may access publiclyavailable 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. • 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– 0085 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 your comment submission. The NRC posts all comment submissions at https:// www.regulations.gov as well as entering the comment submissions into ADAMS. The NRC does not routinely edit E:\FR\FM\17APN1.SGM 17APN1

Agencies

[Federal Register Volume 79, Number 74 (Thursday, April 17, 2014)]
[Notices]
[Pages 21811-21812]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-08792]


=======================================================================
-----------------------------------------------------------------------

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.

-----------------------------------------------------------------------

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 https://www.regulations.gov and search for Docket ID NRC-2014-0023. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. 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: Gary.Stevens@nrc.gov.

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 https://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 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 
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 https://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]
BILLING CODE 7590-01-P
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