83_FR_26218 83 FR 26110 - Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components

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)

Page Range26110-26111
FR Document2018-11995

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.

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


                                         VerDate Sep<11>2014   20:19 Jun 04, 2018   Jkt 241001   PO 00000   Frm 00116   Fmt 4703   Sfmt 4703   E:\FR\FM\05JNN1.SGM   05JNN1


                                                                              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
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
ActionRegulatory guide; issuance.
DatesRevision 1 to RG 1.207 is available on June 5, 2018.
ContactRobert 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 Citation83 FR 26110 

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