83_FR_26219 83 FR 26111 - Effect of LWR Water Environments on the Fatigue Life of Reactor Materials

83 FR 26111 - Effect of LWR Water Environments on the Fatigue Life of Reactor Materials

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 83, Issue 108 (June 5, 2018)

Page Range26111-26112
FR Document2018-11996

The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG/ CR-6909, Revision 1, ``Effect of LWR Water 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 (LWR) 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. This final document also incorporates changes to address public comments provided on the draft of Revision 1 of NUREG/CR-6909.

Federal Register, Volume 83 Issue 108 (Tuesday, June 5, 2018) 
[Federal Register Volume 83, Number 108 (Tuesday, June 5, 2018)]
[Notices]
[Pages 26111-26112]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2018-11996]


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NUCLEAR REGULATORY COMMISSION

[NRC-2014-0023]


Effect of LWR Water Environments on the Fatigue Life of Reactor 
Materials

AGENCY: Nuclear Regulatory Commission.

ACTION: NUREG; issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing NUREG/
CR-6909, Revision 1, ``Effect of LWR Water 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 
(LWR) 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. This final document also incorporates changes to address public 
comments provided on the draft of Revision 1 of NUREG/CR-6909.

ADDRESSES: Please refer to Docket ID NRC-2014-0023 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly-available information related to this document 
using any of the following methods:
     Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0023. Address 
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact 
the individuals listed in the FOR FURTHER INFORMATION CONTACT section 
of this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain 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 pdr.resource@nrc.gov. The 
ADAMS accession number for each document referenced (if it is available 
in ADAMS) is provided the first time that it is mentioned in this 
document. Revision 1 of NUREG/CR-6909 is available in ADAMS under 
Accession No. ML16319A004.
     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.

FOR FURTHER INFORMATION CONTACT: Robert Tregoning, Office of Nuclear 
Regulatory Research, telephone: 301-415-2324, email: 
Robert.Tregoning@nrc.gov; or Appajosula Rao, Office of Nuclear 
Regulatory Research, telephone: 301-415-2381, email: 
Appajosula.Rao@nrc.gov, U.S. Nuclear Regulatory Commission, Washington 
DC 20555-0001.

SUPPLEMENTARY INFORMATION: 
    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 LWR water environments are not explicitly addressed by the 
Code design curves. The existing fatigue strain-vs.-life ([epsi]-N) 
data illustrate potentially significant effects of LWR water 
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 steels, nickel alloy materials, carbon steels, and 
low-alloy steels. In March 2007, Revision 0 of NUREG/CR-6909 (ADAMS 
Accession No. ML070660620) was issued. That report was the technical 
basis document for NRC Regulatory Guide (RG) 1.207, Revision 0, 
``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'' (ADAMS Accession No. 
ML070380586). Revision 0 of NUREG/CR-6909 summarized the work performed 
at Argonne National Laboratory on the fatigue of piping and pressure 
vessel steels in LWR coolant environments. That report evaluated the 
existing laboratory fatigue data to identify the various materials, 
environmental, and loading parameters that influence fatigue crack 
initiation and summarized the effects of key parameters on the fatigue 
lives of pressure vessel and piping steels. The report presented 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 LWR 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 
additional laboratory fatigue data and other results available since 
2007. On April 17, 2014 (79 FR 21811), a draft of Revision 1 was 
noticed in the Federal Register for public comment under Docket ID NRC-
2014-0023. The public comment period ended on June 2, 2014. The final 
version of Revision 1 of NUREG/CR-6909 reflects changes made to address 
the public comments. Appendix F of the document provides responses to 
the public comments received.
    Revision 1 of NUREG/CR-6909 is the technical basis document for 
Revision 1 of RG 1.207, ``Guidelines for Evaluating the Effects of 
Light-Water Reactor Water Environments in Fatigue Analyses of Metal 
Components'' (ADAMS Accession No. ML16315A130). This RG describes 
methods and procedures that the NRC staff considers acceptable for use 
in determining the acceptable fatigue lives

[[Page 26112]]

of components evaluated by a cumulative usage factor calculation in 
accordance with the fatigue design provisions in Section III, ``Rules 
for Construction of Nuclear Power Plant Components,'' of the American 
Society of Mechanical Engineers Boiler and Pressure Vessel Code to 
account for the effects of LWR water environments. The NRC is issuing 
Revision 1 of RG 1.207 concurrently with Revision 1 of NUREG/CR-6909 
under a separate notice associated with Docket ID NRC-2014-0244.
    The NRC notes that Revision 1 of RG 1.207 was issued in draft form 
as a draft RG (DG-1309). The NRC published a notice of the availability 
of DG-1309 in the Federal Register on November 24, 2014 (79 FR 69884), 
under Docket ID NRC-2014-0244, with a public comment period that closed 
on January 24, 2015. Public comments on DG-1309 and the NRC staff's 
responses are available in ADAMS under Accession No. ML16315A127.

    Dated at Rockville, Maryland, this 30th day of May 2018.

    For the Nuclear Regulatory Commission.
Thomas Boyce,
Chief, Regulatory Guidance and Generic Issues Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2018-11996 Filed 6-4-18; 8:45 am]
 BILLING CODE 7590-01-P

Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices 26111 provisions in these part 52 licenses and report was first published in 2007. This addressed by the Code design curves. regulatory approvals. If, in the future, final document also incorporates The existing fatigue strain–vs.–life the NRC staff seeks to impose a position changes to address public comments (e¥N) data illustrate potentially in this RG in a manner that does not provided on the draft of Revision 1 of significant effects of LWR water provide issue finality as described in the NUREG/CR–6909. environments on the fatigue resistance applicable issue finality provision, then ADDRESSES: Please refer to Docket ID of pressure vessel and piping steels. the NRC staff must address the criteria NRC–2014–0023 when contacting the Under certain environmental and for avoiding issue finality as described NRC about the availability of loading conditions, fatigue lives in in the applicable issue finality information regarding this document. water relative to those in air can be provision. You may obtain publicly-available significantly lower for austenitic Existing licensees and applicants of information related to this document stainless steels, nickel alloy materials, final design certification rules will not using any of the following methods: carbon steels, and low-alloy steels. In be required to comply with the • Federal Rulemaking Website: Go to March 2007, Revision 0 of NUREG/CR– positions set forth in this RG unless the http://www.regulations.gov and search 6909 (ADAMS Accession No. licensee or design certification rule for Docket ID NRC–2014–0023. Address ML070660620) was issued. That report applicant seeks a voluntary change to its questions about NRC dockets to Jennifer was the technical basis document for licensing basis with respect to the Borges; telephone: 301–287–9127; NRC Regulatory Guide (RG) 1.207, effects of light-water reactor coolant email: Jennifer.Borges@nrc.gov. For Revision 0, ‘‘Guidelines for Evaluating environments on the fatigue lives of technical questions, contact the Fatigue Analyses Incorporating the Life nuclear power plant components by individuals listed in the FOR FURTHER Reduction of Metal Components Due to means of a cumulative usage factor, and INFORMATION CONTACT section of this the Effects of the Light-Water Reactor where the NRC determines that the document. Environment for New Reactors’’ safety review of the licensee’s request • NRC’s Agencywide Documents (ADAMS Accession No. ML070380586). must include consideration of the Access and Management System Revision 0 of NUREG/CR–6909 effects of light-water reactor coolant (ADAMS): You may obtain publicly- summarized the work performed at environments on the fatigue lives of available documents online in the Argonne National Laboratory on the nuclear power plant components. ADAMS Public Documents collection at fatigue of piping and pressure vessel Further information on the staff’s use of http://www.nrc.gov/reading-rm/ steels in LWR coolant environments. the RG is contained in the RG under adams.html. To begin the search, select That report evaluated the existing Section D, ‘‘Implementation.’’ ‘‘ADAMS Public Documents’’ and then laboratory fatigue data to identify the select ‘‘Begin Web-based ADAMS various materials, environmental, and Dated at Rockville, Maryland, this 30th day loading parameters that influence of May 2018. Search.’’ For problems with ADAMS, please contact the NRC’s Public fatigue crack initiation and summarized For the Nuclear Regulatory Commission. the effects of key parameters on the Document Room (PDR) reference staff at Thomas H. Boyce, fatigue lives of pressure vessel and 1–800–397–4209, 301–415–4737, or by Chief, Regulatory Guidance and Generic piping steels. The report presented email to pdr.resource@nrc.gov. The Issues Branch, Division of Engineering, Office models for estimating fatigue lives as a of Nuclear Regulatory Research. ADAMS accession number for each document referenced (if it is available in function of material, loading, and [FR Doc. 2018–11995 Filed 6–4–18; 8:45 am] environmental conditions, and ADAMS) is provided the first time that BILLING CODE 7590–01–P it is mentioned in this document. described the environmental fatigue Revision 1 of NUREG/CR–6909 is correction factor for incorporating the available in ADAMS under Accession effects of LWR coolant environments NUCLEAR REGULATORY into Code fatigue evaluations. COMMISSION No. ML16319A004. • NRC’s PDR: You may examine and Revision 1 of NUREG/CR–6909 [NRC–2014–0023] purchase copies of public documents at provides updates and improvements to the NRC’s PDR, Room O1–F21, One the environmental fatigue correction Effect of LWR Water Environments on White Flint North, 11555 Rockville factor approach based on additional the Fatigue Life of Reactor Materials Pike, Rockville, Maryland 20852. laboratory fatigue data and other results available since 2007. On April 17, 2014 AGENCY: Nuclear Regulatory FOR FURTHER INFORMATION CONTACT: (79 FR 21811), a draft of Revision 1 was Commission. Robert Tregoning, Office of Nuclear noticed in the Federal Register for Regulatory Research, telephone: 301– ACTION: NUREG; issuance. public comment under Docket ID NRC– 415–2324, email: Robert.Tregoning@ 2014–0023. The public comment period SUMMARY: The U.S. Nuclear Regulatory nrc.gov; or Appajosula Rao, Office of ended on June 2, 2014. The final version Commission (NRC) is issuing NUREG/ Nuclear Regulatory Research, telephone: of Revision 1 of NUREG/CR–6909 CR–6909, Revision 1, ‘‘Effect of LWR 301–415–2381, email: Appajosula.Rao@ reflects changes made to address the Water Environments on the Fatigue Life nrc.gov, U.S. Nuclear Regulatory public comments. Appendix F of the of Reactor Materials.’’ This report Commission, Washington DC 20555– document provides responses to the summarizes the results of NRC research 0001. public comments received. efforts and work performed at Argonne SUPPLEMENTARY INFORMATION: Revision 1 of NUREG/CR–6909 is the National Laboratory on the fatigue of The American Society of Mechanical technical basis document for Revision 1 piping and pressure vessel steels in Engineers Boiler and Pressure Vessel of RG 1.207, ‘‘Guidelines for Evaluating amozie on DSK3GDR082PROD with NOTICES1 light-water reactor (LWR) environments. Code (Code) provides rules for the the Effects of Light-Water Reactor Water Revision 1 of this report provides design of Class 1 components of nuclear Environments in Fatigue Analyses of updates and improvements to the power plants. Appendix I to Section III Metal Components’’ (ADAMS Accession environmental fatigue correction factor of the Code contains fatigue design No. ML16315A130). This RG describes approach based on an extensive update curves for applicable structural methods and procedures that the NRC to available laboratory fatigue data from materials. However, the effects of LWR staff considers acceptable for use in testing and results available since this water environments are not explicitly determining the acceptable fatigue lives VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 PO 00000 Frm 00117 Fmt 4703 Sfmt 4703 E:\FR\FM\05JNN1.SGM 05JNN1

26112 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices of components evaluated by a Quynh.Nguyen@nrc.gov) five days prior ACTION: License amendment request; cumulative usage factor calculation in to the meeting, if possible, so that notice of opportunity to comment, accordance with the fatigue design arrangements can be made. Thirty-five request a hearing, and petition for leave provisions in Section III, ‘‘Rules for hard copies of each presentation or to intervene; order imposing Construction of Nuclear Power Plant handout should be provided to the DFO procedures. Components,’’ of the American Society thirty minutes before the meeting. In of Mechanical Engineers Boiler and addition, one electronic copy of each SUMMARY: The U.S. Nuclear Regulatory Pressure Vessel Code to account for the presentation should be emailed to the Commission (NRC) received and is effects of LWR water environments. The DFO one day before the meeting. If an considering approval of three NRC is issuing Revision 1 of RG 1.207 electronic copy cannot be provided amendment requests. The amendment concurrently with Revision 1 of within this timeframe, presenters requests are for River Bend Station, Unit NUREG/CR–6909 under a separate should provide the DFO with a CD 1; Grand Gulf Nuclear Station, Unit 1; notice associated with Docket ID NRC– containing each presentation at least and Browns Ferry Nuclear Plant, Units 2014–0244. thirty minutes before the meeting. 1, 2, and 3. For each amendment The NRC notes that Revision 1 of RG Electronic recordings will be permitted request, the NRC proposes to determine 1.207 was issued in draft form as a draft only during those portions of the that they involve no significant hazards RG (DG–1309). The NRC published a meeting that are open to the public. consideration. Because each amendment notice of the availability of DG–1309 in Detailed procedures for the conduct of request contains sensitive unclassified the Federal Register on November 24, and participation in ACRS meetings non-safeguards information (SUNSI) an 2014 (79 FR 69884), under Docket ID were published in the Federal Register order imposes procedures to obtain NRC–2014–0244, with a public on October 4, 2017 (82 FR 46312). The access to SUNSI for contention comment period that closed on January bridgeline number for this meeting is preparation. 24, 2015. Public comments on DG–1309 888–790–7128, passcode 7802533#. DATES: Comments must be filed by July and the NRC staff’s responses are Information regarding changes to the 5, 2018. A request for a hearing must be available in ADAMS under Accession agenda, whether the meeting has been filed by August 6, 2018. Any potential No. ML16315A127. canceled or rescheduled, and the time party as defined in § 2.4 of title 10 of the Dated at Rockville, Maryland, this 30th day allotted to present oral statements can Code of Federal Regulations (10 CFR) of May 2018. be obtained by contacting the identified who believes access to SUNSI is For the Nuclear Regulatory Commission. DFO. Moreover, in view of the necessary to respond to this notice must Thomas Boyce, possibility that the schedule for ACRS request document access by June 15, meetings may be adjusted by the 2018. Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office Chairman as necessary to facilitate the ADDRESSES: You may submit comments of Nuclear Regulatory Research. conduct of the meeting, persons by any of the following methods: planning to attend should check with [FR Doc. 2018–11996 Filed 6–4–18; 8:45 am] • Federal Rulemaking website: Go to the DFO if such rescheduling would BILLING CODE 7590–01–P http://www.regulations.gov and search result in a major inconvenience. for Docket ID NRC–2018–0102. Address If attending this meeting, please enter questions about NRC dockets to Jennifer NUCLEAR REGULATORY through the One White Flint North Borges; telephone: 301–287–9127; COMMISSION building, 11555 Rockville Pike, email: Jennifer.Borges@nrc.gov. For Rockville, Maryland 20852. After technical questions, contact the Advisory Committee on Reactor registering with Security, please contact individual listed in the FOR FURTHER Safeguards (ACRS); Meeting of the Mr. Theron Brown at 301–415–6702 to INFORMATION CONTACT section of this ACRS Subcommittee on Planning and be escorted to the meeting room. document. Procedures; Notice of Meeting Dated: May 23, 2018. • Mail comments to: May Ma, Office The ACRS Subcommittee on Planning Mark L. Banks, of Administration, Mail Stop: TWFN–7– and Procedures will hold a meeting on Chief, Technical Support Branch, Advisory A60M, U.S. Nuclear Regulatory June 6, 2018, 11545 Rockville Pike, Committee on Reactor Safeguards. Commission, Washington, DC 20555– Room T–2B3, Rockville, Maryland [FR Doc. 2018–12023 Filed 6–4–18; 8:45 am] 0001. 20852. BILLING CODE 7590–01–P For additional direction on obtaining The meeting will be open to public information and submitting comments, attendance. see ‘‘Obtaining Information and The agenda for the subject meeting NUCLEAR REGULATORY Submitting Comments’’ in the shall be as follows: COMMISSION SUPPLEMENTARY INFORMATION section of [NRC–2018–0102] this document. Wednesday, June 6, 2018—12:00 p.m. Until 1:00 p.m. FOR FURTHER INFORMATION CONTACT: Applications and Amendments to Beverly Clayton, Office of Nuclear The Subcommittee will discuss Facility Operating Licenses and Reactor Regulation, U.S. Nuclear proposed ACRS activities and related Combined Licenses Involving Regulatory Commission, Washington, matters. The Subcommittee will gather Proposed No Significant Hazards DC 20555–0001; telephone: 301–415– information, analyze relevant issues and Considerations and Containing 3475; email: Beverly.Clayton@nrc.gov. facts, and formulate proposed positions amozie on DSK3GDR082PROD with NOTICES1 Sensitive Unclassified Non-Safeguards SUPPLEMENTARY INFORMATION: and actions, as appropriate, for Information and Order Imposing deliberation by the Full Committee. Procedures for Access to Sensitive I. Obtaining Information and Members of the public desiring to Unclassified Non-Safeguards Submitting Comments provide oral statements and/or written Information comments should notify the Designated A. Obtaining Information Federal Official (DFO), Quynh Nguyen AGENCY:Nuclear Regulatory Please refer to Docket ID NRC–2018– (Telephone 301–415–5844 or Email: Commission. 0102, facility name, unit number(s), VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 PO 00000 Frm 00118 Fmt 4703 Sfmt 4703 E:\FR\FM\05JNN1.SGM 05JNN1


Document Created: 2018-11-02 11:47:05
Document Modified: 2018-11-02 11:47:05
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionNotices
ActionNUREG; issuance.
ContactRobert Tregoning, Office of Nuclear Regulatory Research, telephone: 301-415-2324, email: [email protected]; or Appajosula Rao, Office of Nuclear Regulatory Research, telephone: 301-415-2381, email: [email protected], U.S. Nuclear Regulatory Commission, Washington DC 20555-0001.
FR Citation83 FR 26111 
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