Updated Aging Management Criteria for Reactor Vessel Internal Components for Pressurized-Water Reactors, 5266-5267 [2021-01041]
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Federal Register / Vol. 86, No. 11 / Tuesday, January 19, 2021 / Notices
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divisions, and combined NECTAs
should be discontinued.
(3) Research should be undertaken on
an additional, territorially exhaustive
classification that covers all of the
United States and Puerto Rico.
(4) The first annual delineation
update of the coming decade should be
combined with the decennial-based
delineations.
(5) OMB should make publicly
available a schedule for updates to the
core based statistical areas (see
proposed update schedule below).
(6) OMB should continue use of
American Community Survey
commuting data in measurement of
intercounty connectivity, though
changing societal and economic trends
may warrant considering changes in the
2030 standards.
Under the recommendations of the
committee, OMB would release three
different types of updates, subject to the
proposed standards.
(1) Annual Updates—These updates
would address qualification of new
metropolitan and micropolitan
statistical areas and typically would
affect a small number of counties. (In
some years, there may be no updates
warranted by the data.)
(2) Five-Year (‘‘mid-decade’’)
Update—This broader update would
include: Qualification of metropolitan
and micropolitan statistical areas,
qualification of outlying counties,
merging of adjacent metropolitan or
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qualification of principal cities,
categorization of metropolitan and
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qualification of metropolitan divisions,
qualification of combined statistical
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statistical areas.
(3) Decennial Delineation—The initial
re-delineation following adoption of
revised standards would include all of
the changes listed for the five-year
update, plus the qualification of central
counties.
The schedule for these updates as
described in the attached proposed
standards is as follows:
Update type
Release date
Decennial Delineation ........
Annual Update ...................
Annual Update ...................
Annual Update ...................
Annual Update ...................
Five-Year Update ..............
Annual Update ...................
June 2023.
December 2024.
December 2025.
December 2026.
December 2027.
December 2028.
December 2029.
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19:19 Jan 17, 2021
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4. Issues for Comment
OMB is seeking comments on the
specific recommendations of the
committee for revising the 2010
standards and their potential effects on
the statistical area delineations (see
Section 3 above). Comments are also
sought on any other aspect of the
current 2010 Standards that are of
interest to reviewers, including topics
such as commuting thresholds,
alternative sources of data, stakeholder
engagement, and procedures for OMB
dissemination of updates to the
delineations, as well as editorial
suggestions to help improve the clarity
of the standards.
Dominic J. Mancini,
Deputy Administrator.
[FR Doc. 2021–00988 Filed 1–15–21; 8:45 am]
BILLING CODE 3110–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2020–0153]
Updated Aging Management Criteria
for Reactor Vessel Internal
Components for Pressurized-Water
Reactors
Nuclear Regulatory
Commission.
ACTION: Interim staff guidance; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing Interim
Staff Guidance (ISG) SLR–ISG–2021–
01–PWRVI, ‘‘Updated Aging
Management Criteria for Reactor Vessel
Internal Components for PressurizedWater Reactors.’’ This ISG updates the
aging management criteria for
pressurized-water reactor (PWR) vessel
internals components in the NRC’s
subsequent license renewal (SLR)
guidance documents. Specifically, the
ISG revises guidance contained in
NUREG–2191, ‘‘Generic Aging Lessons
Learned for Subsequent License
Renewal (GALL–SLR) Report,’’ and
NUREG–2192, ‘‘Standard Review Plan
for Review of Subsequent License
Renewal Applications for Nuclear
Power Plants.’’ This ISG is intended to
facilitate preparation of SLR
applications by clarifying existing
guidance for aging management and
adding new guidance, which also will
facilitate the NRC staff’s review of SLR
applications.
DATES: This guidance is effective on
February 18, 2021.
ADDRESSES: Please refer to Docket ID
NRC–2020–0153 when contacting the
NRC about the availability of
SUMMARY:
PO 00000
Frm 00137
Fmt 4703
Sfmt 4703
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
https://www.regulations.gov and search
for Docket ID NRC–2020–0153. Address
questions about Docket IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; email:
Jennifer.Borges@nrc.gov. For technical
questions, contact the individual 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
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, 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. For the convenience of the
reader, instructions about obtaining
materials referenced in this document
are provided in the ‘‘Availability of
Documents’’ section.
• Attention: The PDR, where you may
examine and order copies of public
documents, is currently closed. You
may submit your request to the PDR via
email at pdr.resource@nrc.gov or call 1–
800–397–4209 or 301–415–4737,
between 8:00 a.m. and 4:00 p.m. (EST),
Monday through Friday, except Federal
holidays.
FOR FURTHER INFORMATION CONTACT:
Jeffrey Mitchell, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–415–
0833; email: jeffrey.mitchell2@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
On August 3, 2020 (85 FR 46735), the
staff requested public comments on
draft SLR–ISG–PWRVI–2020–XX,
‘‘Updated Aging Management Criteria
for Reactor Vessel Internal Components
for Pressurized-Water Reactors.’’ The
NRC received comments from the
Electric Power Research Institute,
Materials Reliability Program (EPRI
MRP) by letter dated September 1, 2020
(ADAMS Accession No. ML20245E539),
and from the Nuclear Energy Institute
by letter dated September 2, 2020
(ADAMS Accession No. ML20246G654).
No other comments were submitted.
The NRC staff considered those
comments in developing the final
version of the ISG. The staff’s responses
to the comments are provided in
E:\FR\FM\19JAN1.SGM
19JAN1
5267
Federal Register / Vol. 86, No. 11 / Tuesday, January 19, 2021 / Notices
Appendix H, ‘‘Disposition of Public
Comments,’’ of the final ISG.
This ISG updates NUREG–2191,
‘‘Generic Aging Lessons Learned for
Subsequent License Renewal (GALL–
SLR) Report,’’ and NUREG–2192,
‘‘Standard Review Plan for Review of
Subsequent License Renewal
Applications for Nuclear Power Plants.’’
NUREG–2191 and NUREG–2192 were
published in July 2017, and a full
review and revision to these documents
is not scheduled to be performed for
several years. The staff has reviewed the
first three subsequent license renewal
applications (SLRAs) that were based on
the above guidance documents. During
these reviews, the staff and applicants
identified improvements to the
guidance that would assist in preparing
and reviewing future SLRAs more
effectively and efficiently. This ISG
provides an interim update to NUREG–
2191 and NUREG–2192 to implement
these improvements.
This ISG is not intended for
standalone use. It provides revisions to
NUREG–2191 and NUREG–2192
sections and tables that supersede the
content in the NUREGs and is intended
to be used within the context of the
NUREGs. The revisions captured in this
ISG include:
• Updates to GALL–SLR Report aging
management program XI.M16A, ‘‘PWR
Vessel Internals’’;
• changes to aging management
review items in NUREG–2191 tables and
corresponding summary tables in
NUREG–2192;
• new aging management review
items in NUREG–2191 tables and
corresponding summary tables in
NUREG–2192;
• changes to NUREG–2192 ‘‘further
evaluation’’ guidance sections;
• updates to references listed in
affected NUREG–2191 sections; and
• editorial corrections to relevant
sections.
II. Availability of Documents
The documents identified in the
following table are available to
interested persons in ADAMS, as
indicated.
Document
ADAMS accession No.
NUREG–2191, ‘‘Generic Aging Lessons Learned for Subsequent License Renewal (GALL–SLR) Report’’ ...............
NUREG–2192, ‘‘Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power
Plants’’.
Draft SLR–ISG–PWRVI–2020–XX, ‘‘Updated Aging Management Criteria for Reactor Vessel Internal Components
for Pressurized-Water Reactors’’.
Final SLR–ISG–2021–01–PWRVI, ‘‘Updated Aging Management Criteria for Reactor Vessel Internal Components
for Pressurized-Water Reactors’’.
March 28, 2019, Summary of Category 2 Public Meeting on Lessons Learned from the Review of the First Subsequent License Renewal Applications.
Summary of December 12, 2019, Category 2 Public Meeting on Lessons Learned from the Review of the First
Subsequent License Renewal Applications.
February 20, 2020, Summary of Category 2 Public Meeting on Lessons Learned from the Review of the First Subsequent License Renewal Applications.
Summary of March 25, 2020 Meeting with Industry Related to Revisions to Subsequent License Renewal Guidance Documents.
Summary of April 3, 2020, Meeting with Industry Regarding Changes to Subsequent License Renewal Guidance
Documents.
Summary of April 7, 2020, Meeting with Industry Regarding Revisions to the Subsequent License Renewal Guidance Documents.
Comment Letter (1) of Christopher Koehler and Brian Burgos, on behalf of the Electric Power Research Institute,
Subject: ‘‘Industry Comments to Draft Interim Staff Guidance (ISG)–SLR–ISG–PWRVI–2020–XX’’.
Comment Letter (2) of Peter W. Kissinger, on behalf of Nuclear Energy Institute, Subject: ‘‘Comments on the proposed changes to subsequent license renewal document SLR–ISG–PWRVI–2020–XX’’.
khammond on DSKJM1Z7X2PROD with NOTICES
III. Backfit Discussion
This ISG intends to revise guidance
for the NRC staff reviewing SLRAs and
for prospective applicants in preparing
SLRAs. Issuance of this ISG does not
constitute a backfit as defined in section
50.109(a)(1) of title 10 of the Code of
Federal Regulations (10 CFR) and is not
otherwise inconsistent with the issue
finality provisions in 10 CFR part 52. As
discussed in the ‘‘Backfitting’’ section of
the final ISG, the ISG positions do not
constitute backfitting inasmuch as the
ISG is guidance directed to the NRC
staff with respect to its regulatory
responsibilities and to applicants who
choose to follow the guidance.
Applicants and potential applicants are
not, with certain exceptions, the subject
of either the backfit rule or any issue
finality provisions under 10 CFR part
52. The NRC staff has no intention to
VerDate Sep<11>2014
19:19 Jan 17, 2021
Jkt 253001
ML16274A389 (Vol. 1)
ML16274A399 (Vol. 2).
ML16274A402.
ML20156A343.
ML20217L203.
ML19112A206.
ML20016A347.
ML20076E074.
ML20107F702.
ML20107F733.
ML20107F699.
ML20245E539.
ML20246G654.
impose the ISG positions on existing
nuclear power plant licensees either
now or in the future (absent a voluntary
request for a change from the licensee).
NUCLEAR REGULATORY
COMMISSION
IV. Congressional Review Act
Application and Testing of SafetyRelated Diesel Generators in Nuclear
Power Plants
This ISG 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.
Dated: January 13, 2021.
For the Nuclear Regulatory Commission.
Robert Caldwell,
Deputy Director, Division of New and
Renewed Licenses, Office of Nuclear Reactor
Regulation.
[FR Doc. 2021–01041 Filed 1–15–21; 8:45 am]
BILLING CODE 7590–01–P
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[NRC–2020–0279]
Nuclear Regulatory
Commission.
ACTION: Draft regulatory guide; request
for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing for public
comment draft regulatory guide (DG),
DG–1303, ‘‘Application and Testing of
Safety-Related Diesel Generators in
Nuclear Power.’’ This draft guide is
proposed revision 5 of Regularity Guide
(RG) 1.9. DG–1303 provides updated
guidance that the staff of the NRC
considers acceptable to demonstrate
SUMMARY:
E:\FR\FM\19JAN1.SGM
19JAN1
]]>Agencies
[Federal Register Volume 86, Number 11 (Tuesday, January 19, 2021)]
[Notices]
[Pages 5266-5267]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2021-01041]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2020-0153]
Updated Aging Management Criteria for Reactor Vessel Internal
Components for Pressurized-Water Reactors
AGENCY: Nuclear Regulatory Commission.
ACTION: Interim staff guidance; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing
Interim Staff Guidance (ISG) SLR-ISG-2021-01-PWRVI, ``Updated Aging
Management Criteria for Reactor Vessel Internal Components for
Pressurized-Water Reactors.'' This ISG updates the aging management
criteria for pressurized-water reactor (PWR) vessel internals
components in the NRC's subsequent license renewal (SLR) guidance
documents. Specifically, the ISG revises guidance contained in NUREG-
2191, ``Generic Aging Lessons Learned for Subsequent License Renewal
(GALL-SLR) Report,'' and NUREG-2192, ``Standard Review Plan for Review
of Subsequent License Renewal Applications for Nuclear Power Plants.''
This ISG is intended to facilitate preparation of SLR applications by
clarifying existing guidance for aging management and adding new
guidance, which also will facilitate the NRC staff's review of SLR
applications.
DATES: This guidance is effective on February 18, 2021.
ADDRESSES: Please refer to Docket ID NRC-2020-0153 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 https://www.regulations.gov and search for Docket ID NRC-2020-0153. Address
questions about Docket IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
questions, contact the individual 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 https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS
Search.'' For problems with ADAMS, please contact the NRC's Public
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or
by email to [email protected]. For the convenience of the reader,
instructions about obtaining materials referenced in this document are
provided in the ``Availability of Documents'' section.
Attention: The PDR, where you may examine and order copies
of public documents, is currently closed. You may submit your request
to the PDR via email at [email protected] or call 1-800-397-4209 or
301-415-4737, between 8:00 a.m. and 4:00 p.m. (EST), Monday through
Friday, except Federal holidays.
FOR FURTHER INFORMATION CONTACT: Jeffrey Mitchell, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone: 301-415-0833; email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Background
On August 3, 2020 (85 FR 46735), the staff requested public
comments on draft SLR-ISG-PWRVI-2020-XX, ``Updated Aging Management
Criteria for Reactor Vessel Internal Components for Pressurized-Water
Reactors.'' The NRC received comments from the Electric Power Research
Institute, Materials Reliability Program (EPRI MRP) by letter dated
September 1, 2020 (ADAMS Accession No. ML20245E539), and from the
Nuclear Energy Institute by letter dated September 2, 2020 (ADAMS
Accession No. ML20246G654). No other comments were submitted. The NRC
staff considered those comments in developing the final version of the
ISG. The staff's responses to the comments are provided in
[[Page 5267]]
Appendix H, ``Disposition of Public Comments,'' of the final ISG.
This ISG updates NUREG-2191, ``Generic Aging Lessons Learned for
Subsequent License Renewal (GALL-SLR) Report,'' and NUREG-2192,
``Standard Review Plan for Review of Subsequent License Renewal
Applications for Nuclear Power Plants.'' NUREG-2191 and NUREG-2192 were
published in July 2017, and a full review and revision to these
documents is not scheduled to be performed for several years. The staff
has reviewed the first three subsequent license renewal applications
(SLRAs) that were based on the above guidance documents. During these
reviews, the staff and applicants identified improvements to the
guidance that would assist in preparing and reviewing future SLRAs more
effectively and efficiently. This ISG provides an interim update to
NUREG-2191 and NUREG-2192 to implement these improvements.
This ISG is not intended for standalone use. It provides revisions
to NUREG-2191 and NUREG-2192 sections and tables that supersede the
content in the NUREGs and is intended to be used within the context of
the NUREGs. The revisions captured in this ISG include:
Updates to GALL-SLR Report aging management program
XI.M16A, ``PWR Vessel Internals'';
changes to aging management review items in NUREG-2191
tables and corresponding summary tables in NUREG-2192;
new aging management review items in NUREG-2191 tables and
corresponding summary tables in NUREG-2192;
changes to NUREG-2192 ``further evaluation'' guidance
sections;
updates to references listed in affected NUREG-2191
sections; and
editorial corrections to relevant sections.
II. Availability of Documents
The documents identified in the following table are available to
interested persons in ADAMS, as indicated.
----------------------------------------------------------------------------------------------------------------
Document ADAMS accession No.
----------------------------------------------------------------------------------------------------------------
NUREG-2191, ``Generic Aging Lessons Learned for Subsequent ML16274A389 (Vol. 1)
License Renewal (GALL-SLR) Report''. ML16274A399 (Vol. 2).
NUREG-2192, ``Standard Review Plan for Review of Subsequent ML16274A402.
License Renewal Applications for Nuclear Power Plants''.
Draft SLR-ISG-PWRVI-2020-XX, ``Updated Aging Management ML20156A343.
Criteria for Reactor Vessel Internal Components for
Pressurized-Water Reactors''.
Final SLR-ISG-2021-01-PWRVI, ``Updated Aging Management ML20217L203.
Criteria for Reactor Vessel Internal Components for
Pressurized-Water Reactors''.
March 28, 2019, Summary of Category 2 Public Meeting on ML19112A206.
Lessons Learned from the Review of the First Subsequent
License Renewal Applications.
Summary of December 12, 2019, Category 2 Public Meeting on ML20016A347.
Lessons Learned from the Review of the First Subsequent
License Renewal Applications.
February 20, 2020, Summary of Category 2 Public Meeting on ML20076E074.
Lessons Learned from the Review of the First Subsequent
License Renewal Applications.
Summary of March 25, 2020 Meeting with Industry Related to ML20107F702.
Revisions to Subsequent License Renewal Guidance Documents.
Summary of April 3, 2020, Meeting with Industry Regarding ML20107F733.
Changes to Subsequent License Renewal Guidance Documents.
Summary of April 7, 2020, Meeting with Industry Regarding ML20107F699.
Revisions to the Subsequent License Renewal Guidance
Documents.
Comment Letter (1) of Christopher Koehler and Brian Burgos, ML20245E539.
on behalf of the Electric Power Research Institute,
Subject: ``Industry Comments to Draft Interim Staff
Guidance (ISG)-SLR-ISG-PWRVI-2020-XX''.
Comment Letter (2) of Peter W. Kissinger, on behalf of ML20246G654.
Nuclear Energy Institute, Subject: ``Comments on the
proposed changes to subsequent license renewal document
SLR-ISG-PWRVI-2020-XX''.
----------------------------------------------------------------------------------------------------------------
III. Backfit Discussion
This ISG intends to revise guidance for the NRC staff reviewing
SLRAs and for prospective applicants in preparing SLRAs. Issuance of
this ISG does not constitute a backfit as defined in section
50.109(a)(1) of title 10 of the Code of Federal Regulations (10 CFR)
and is not otherwise inconsistent with the issue finality provisions in
10 CFR part 52. As discussed in the ``Backfitting'' section of the
final ISG, the ISG positions do not constitute backfitting inasmuch as
the ISG is guidance directed to the NRC staff with respect to its
regulatory responsibilities and to applicants who choose to follow the
guidance. Applicants and potential applicants are not, with certain
exceptions, the subject of either the backfit rule or any issue
finality provisions under 10 CFR part 52. The NRC staff has no
intention to impose the ISG positions on existing nuclear power plant
licensees either now or in the future (absent a voluntary request for a
change from the licensee).
IV. Congressional Review Act
This ISG 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.
Dated: January 13, 2021.
For the Nuclear Regulatory Commission.
Robert Caldwell,
Deputy Director, Division of New and Renewed Licenses, Office of
Nuclear Reactor Regulation.
[FR Doc. 2021-01041 Filed 1-15-21; 8:45 am]
BILLING CODE 7590-01-P
