83 FR 26110 - Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components
NUCLEAR REGULATORY COMMISSION Federal Register Volume 83, Issue 108 (June 5, 2018)
Federal Register Volume 83, Issue 108 (June 5, 2018)
| Page Range | 26110-26111 | |
| FR Document | 2018-11995 |
[Federal Register Volume 83, Number 108 (Tuesday, June 5, 2018)] [Notices] [Pages 26110-26111] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2018-11995] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2014-0244] Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 1 to Regulatory Guide (RG) 1.207, ``Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components.'' This RG describes methods and procedures that the staff of the NRC considers acceptable for use in determining the acceptable fatigue lives 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 light-water reactor water environments. DATES: Revision 1 to RG 1.207 is available on June 5, 2018. ADDRESSES: Please refer to Docket ID NRC-2014-0244 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-2014-0244. 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. RG 1.207, ``Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components,'' is available in ADAMS under Accession No. ML16315A130. 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. RGs are not copyrighted, and NRC approval is not required to reproduce them. FOR FURTHER INFORMATION CONTACT: Robert Tregoning, Office of Nuclear Regulatory Research, telephone: 301-415-2324, email: Robert.Tregoning@nrc.gov and Stephen Burton, Office of Nuclear Regulatory Research, telephone: 301-415-7000, Stephen.Burton@nrc.gov. Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. SUPPLEMENTARY INFORMATION: I. Discussion 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 regarding methods that are acceptable to the NRC staff for implementing specific parts of the agency's regulations, techniques that the NRC staff uses in evaluating specific issues or postulated events, and data that the NRC staff needs in its review of applications for permits and licenses. Revision 1 of RG 1.207 was issued with a temporary identification of Draft Regulatory Guide, DG-1309. This RG describes methods and procedures that the NRC staff considers acceptable for use in determining the acceptable fatigue lives 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 light-water reactor water environments. II. Additional Information The NRC published a notice of the availability of DG-1309 in the Federal Register on November 24, 2014 (79 FR 69884), for a 60-day public comment period. The public comment period closed on January 24, 2015. Public comments on DG-1309 and the NRC staff's responses to the public comments are available in ADAMS under Accession No. ML16315A127. III. Congressional Review Act This RG 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. IV. Backfitting and Issue Finality This RG describes methods and procedures that the NRC staff considers acceptable for use in applications for license renewal and subsequent license renewal in determining the acceptable fatigue lives 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 ASME Code. This RG also supports reviews of applications for new nuclear reactor construction permits or operating licenses under part 50 of title 10 of the Code of Federal Regulations (10 CFR), design certifications under 10 CFR part 52, and combined licenses under 10 CFR part 52, which do not cite a standard design, in addition to renewed operating licenses under 10 CFR part 54. This RG may also be used by existing holders of combined licenses and operating licenses in accordance with their existing licensing basis and applicable regulatory requirements. This RG 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. Applicants and potential applicants are not, with certain exceptions, protected by either the Backfit Rule or any issue finality provisions under 10 CFR part 52. Neither the Backfit Rule nor the issue finality provisions under 10 CFR part 52, with certain exclusions discussed below, were intended to apply to every NRC action that substantially changes the expectations of current and future applicants. The exceptions to the general principle are applicable whenever a combined license applicant references a part 52 license (i.e., an early site permit or a manufacturing license) and/or part 52 regulatory approval (i.e., a design certification rule or design approval). The NRC staff does not, at this time, intend to impose the positions represented in the RG in a manner that is inconsistent with any issue finality [[Page 26111]] provisions in these part 52 licenses and regulatory approvals. If, in the future, the NRC staff seeks to impose a position in this RG in a manner that does not provide issue finality as described in the applicable issue finality provision, then the NRC staff must address the criteria for avoiding issue finality as described in the applicable issue finality provision. Existing licensees and applicants of final design certification rules will not be required to comply with the positions set forth in this RG unless the licensee or design certification rule applicant seeks a voluntary change to its licensing basis with respect to the effects of light-water reactor coolant environments on the fatigue lives of nuclear power plant components by means of a cumulative usage factor, and where the NRC determines that the safety review of the licensee's request must include consideration of the effects of light- water reactor coolant environments on the fatigue lives of nuclear power plant components. Further information on the staff's use of the RG is contained in the RG under Section D, ``Implementation.'' Dated at Rockville, Maryland, this 30th day of May 2018. For the Nuclear Regulatory Commission. Thomas H. Boyce, Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2018-11995 Filed 6-4-18; 8:45 am] BILLING CODE 7590-01-P
![26110 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices
Dated: May 23, 2018. select ‘‘Begin Web-based ADAMS period. The public comment period
Mark L. Banks, Search.’’ For problems with ADAMS, closed on January 24, 2015. Public
Chief, Technical Support Branch, Advisory please contact the NRC’s Public comments on DG–1309 and the NRC
Committee on Reactor Safeguards. Document Room (PDR) reference staff at staff’s responses to the public comments
[FR Doc. 2018–12024 Filed 6–4–18; 8:45 am] 1–800–397–4209, 301–415–4737, or by are available in ADAMS under
BILLING CODE P email to pdr.resource@nrc.gov. RG Accession No. ML16315A127.
1.207, ‘‘Guidelines for Evaluating the III. Congressional Review Act
Effects of Light-Water Reactor Water
NUCLEAR REGULATORY Environments in Fatigue Analyses of This RG is a rule as defined in the
COMMISSION Metal Components,’’ is available in Congressional Review Act (5 U.S.C.
ADAMS under Accession No. 801–808). However, the Office of
[NRC–2014–0244] Management and Budget has not found
ML16315A130.
• NRC’s PDR: You may examine and it to be a major rule as defined in the
Guidelines for Evaluating the Effects of Congressional Review Act.
Light-Water Reactor Water purchase copies of public documents at
Environments in Fatigue Analyses of the NRC’s PDR, Room O1–F21, One IV. Backfitting and Issue Finality
Metal Components White Flint North, 11555 Rockville
This RG describes methods and
Pike, Rockville, Maryland 20852.
AGENCY: Nuclear Regulatory procedures that the NRC staff considers
RGs are not copyrighted, and NRC
Commission. acceptable for use in applications for
approval is not required to reproduce
license renewal and subsequent license
ACTION: Regulatory guide; issuance. them.
renewal in determining the acceptable
FOR FURTHER INFORMATION CONTACT: fatigue lives of components evaluated
SUMMARY: The U.S. Nuclear Regulatory
Commission (NRC) is issuing Revision 1 Robert Tregoning, Office of Nuclear by a cumulative usage factor calculation
to Regulatory Guide (RG) 1.207, Regulatory Research, telephone: 301– in accordance with the fatigue design
‘‘Guidelines for Evaluating the Effects of 415–2324, email: Robert.Tregoning@ provisions in Section III, ‘‘Rules for
Light-Water Reactor Water nrc.gov and Stephen Burton, Office of Construction of Nuclear Power Plant
Environments in Fatigue Analyses of Nuclear Regulatory Research, telephone: Components,’’ of the ASME Code. This
Metal Components.’’ This RG describes 301–415–7000, Stephen.Burton@ RG also supports reviews of
methods and procedures that the staff of nrc.gov. Both are staff of the U.S. applications for new nuclear reactor
the NRC considers acceptable for use in Nuclear Regulatory Commission, construction permits or operating
determining the acceptable fatigue lives Washington, DC 20555–0001. licenses under part 50 of title 10 of the
of components evaluated by a SUPPLEMENTARY INFORMATION: Code of Federal Regulations (10 CFR),
cumulative usage factor calculation in design certifications under 10 CFR part
I. Discussion 52, and combined licenses under 10
accordance with the fatigue design
provisions in Section III, ‘‘Rules for The NRC is issuing a revision to an CFR part 52, which do not cite a
Construction of Nuclear Power Plant existing guide in the NRC’s ‘‘Regulatory standard design, in addition to renewed
Components,’’ of the American Society Guide’’ series. This series was operating licenses under 10 CFR part 54.
of Mechanical Engineers Boiler and developed to describe and make This RG may also be used by existing
Pressure Vessel Code to account for the available to the public information holders of combined licenses and
effects of light-water reactor water regarding methods that are acceptable to operating licenses in accordance with
environments. the NRC staff for implementing specific their existing licensing basis and
parts of the agency’s regulations, applicable regulatory requirements.
DATES: Revision 1 to RG 1.207 is techniques that the NRC staff uses in This RG does not constitute
available on June 5, 2018. evaluating specific issues or postulated backfitting as defined in 10 CFR 50.109
ADDRESSES: Please refer to Docket ID events, and data that the NRC staff (the Backfit Rule) and is not otherwise
NRC–2014–0244 when contacting the needs in its review of applications for inconsistent with the issue finality
NRC about the availability of permits and licenses. provisions in 10 CFR part 52.
information regarding this document. Revision 1 of RG 1.207 was issued Applicants and potential applicants are
You may obtain publicly-available with a temporary identification of Draft not, with certain exceptions, protected
information related to this document Regulatory Guide, DG–1309. This RG by either the Backfit Rule or any issue
using any of the following methods: describes methods and procedures that finality provisions under 10 CFR part
• Federal Rulemaking Website: Go to the NRC staff considers acceptable for 52. Neither the Backfit Rule nor the
http://www.regulations.gov and search use in determining the acceptable issue finality provisions under 10 CFR
for Docket ID NRC–2014–0244. Address fatigue lives of components evaluated part 52, with certain exclusions
questions about NRC dockets to Jennifer by a cumulative usage factor calculation discussed below, were intended to
Borges; telephone: 301–287–9127; in accordance with the fatigue design apply to every NRC action that
email: Jennifer.Borges@nrc.gov. For provisions in Section III, ‘‘Rules for substantially changes the expectations
technical questions, contact the Construction of Nuclear Power Plant of current and future applicants.
individuals listed in the FOR FURTHER Components,’’ of the American Society The exceptions to the general
INFORMATION CONTACT section of this of Mechanical Engineers’ Boiler and principle are applicable whenever a
document. Pressure Vessel Code to account for the combined license applicant references a
• NRC’s Agencywide Documents effects of light-water reactor water part 52 license (i.e., an early site permit
amozie on DSK3GDR082PROD with NOTICES1
Access and Management System environments. or a manufacturing license) and/or part
(ADAMS): You may obtain publicly 52 regulatory approval (i.e., a design
available documents online in the II. Additional Information certification rule or design approval).
ADAMS Public Documents collection at The NRC published a notice of the The NRC staff does not, at this time,
http://www.nrc.gov/reading-rm/ availability of DG–1309 in the Federal intend to impose the positions
adams.html. To begin the search, select Register on November 24, 2014 (79 FR represented in the RG in a manner that
‘‘ADAMS Public Documents’’ and then 69884), for a 60-day public comment is inconsistent with any issue finality
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![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
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Document Created: 2018-11-02 11:47:01
Document Modified: 2018-11-02 11:47:01
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Regulatory guide; issuance. | |
| Dates | Revision 1 to RG 1.207 is available on June 5, 2018. | |
| Contact | Robert Tregoning, Office of Nuclear Regulatory Research, telephone: 301-415-2324, email: [email protected] and Stephen Burton, Office of Nuclear Regulatory Research, telephone: 301-415-7000, [email protected] Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. | |
| FR Citation | 83 FR 26110 |
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