[Federal Register Volume 85, Number 149 (Monday, August 3, 2020)]
[Notices]
[Pages 46735-46737]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2020-16699]
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NUCLEAR REGULATORY COMMISSION
[NRC-2020-0153]
Changes to Subsequent License Renewal Guidance Documents
Regarding Reactor Vessel Internal Components in Pressurized Water
Reactors
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft interim staff guidance; request for comment.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting
public comment on draft interim staff guidance (ISG) that proposes
changes to the NRC's subsequent license renewal guidance documents.
Specifically, this 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.''
NUREG-2191 and NUREG-2192 were published in July 2017 and are not
scheduled to be updated for several years. The proposed changes to
these documents are contained in a draft ISG entitled, ``Draft SLR-ISG-
PWRVI-2020-XX; Updated Aging Management Criteria for Reactor Vessel
Internal Components in Pressurized Water Reactors.''
DATES: Submit comments by September 2, 2020. Comments received after
this date will be considered if it is practical to do so, but the
Commission is able to ensure consideration only for comments received
before this date.
ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2020-0153. Address
questions about NRC 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.
Mail comments to: Office of Administration, Mail Stop:
TWFN-7-A60M, U.S. Nuclear Regulatory
[[Page 46736]]
Commission, Washington, DC 20555-0001, ATTN: Program Management,
Announcements and Editing Staff.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: William (Butch) Burton, Office of
Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001; telephone: 301-415-6332; email:
[email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2020-0153 when contacting the NRC
about the availability of information for this action. You may obtain
publicly-available information related to this action by any of the
following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2020-0153.
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 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.
NRC's License Renewal Interim Staff Guidance Website: SLR-
ISG documents are available online at https://www.nrc.gov/reading-rm/doc-collections/isg/license-renewal.html.
B. Submitting Comments
Please include Docket ID NRC-2020-0153 in your comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC will post all comment submissions at
https://www.regulations.gov as well as enter the comment submissions
into ADAMS. The NRC does not routinely edit comment submissions to
remove identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment into ADAMS.
II. Background
The NRC staff has completed its safety reviews of the first three
Subsequent License Renewal Applications (SLRAs), for Turkey Point
Nuclear Generating Units 3 and 4, Peach Bottom Atomic Power Station,
Units 2 and 3, and Surry Power Station, Units 1 and 2. The NRC staff
used the 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,'' to conduct its SLRA safety
reviews for those SLRAs. Through the first three SLRA reviews, the NRC
staff, the Nuclear Energy Institute (NEI), and members of the nuclear
industry identified potential changes to NUREG-2191 and NUREG-2192 to
improve the effectiveness and efficiency of future SLRA safety reviews.
Since March 2019, the NRC staff held several public meetings to
consider lessons learned from these safety reviews and identify areas
where the technical guidance in NUREG-2191 and NUREG-2192 could be
improved or clarified and where new technical guidance was warranted.
The meeting summaries and respective ADAMS Accession Numbers are listed
under the ``Availability of Documents'' section of this document.
III. Specific Requests for Comments
The NRC is soliciting public comment on a draft ISG that proposes
changes to the NRC's subsequent license renewal guidance in NUREG-2191
and NUREG-2192. NUREG-2191 and NUREG-2192 were published in July 2017
and are not scheduled to be updated for several years. The process of
updating these NUREGs involves major review and evaluation by the
staff, the nuclear industry, and the public and will take approximately
five years once the process begins. Several SLRAs are scheduled for
submittal to the NRC for review within the next two years. Issuance of
this ISG is intended to provide improvements in the effectiveness and
efficiency of the preparation and review of the SLRAs, and would become
effective before the updates to NUREG-2191 and NUREG-2192 are
completed.
The proposed changes to NUREG-2191 and NUREG-2192 are contained in
a draft ISG that updates aging management criteria for PWR reactor
vessel internal components. In addition, minor edits are proposed where
errors were identified in the existing guidance.
Draft SLR-ISG-PWRVI-2020-XX, ``Updated Aging Management Criteria
for Reactor Vessel Internal Components in Pressurized Water Reactors''
The reactor vessel internal components ISG is titled, ``Draft SLR-
ISG-PWRVI-2020-XX; Updated Aging Management Criteria for Reactor Vessel
Internal Components in Pressurized Water Reactors,'' and is available
in ADAMS under Accession No. ML20156A343. In addition to addressing
lessons learned from the initial SLRA safety reviews, this draft ISG
also incorporates the conclusions of the NRC staff's April 25, 2019
safety evaluation of Electric Power Research Institute Technical Report
No. 3002017168, ``Materials Reliability Program: Pressurized Water
Internals Inspection and Evaluation Guidelines (MRP-227, Revision 1-
A).'' The NRC staff's safety evaluation for the MRP-227, Revision 1-A
report may be accessed in ADAMS under Accession No. ML19081A001.
Draft SLR-ISG-PWRVI-2020-XX revises the following aging management
guidance:
Standard Review Plan--Subsequent License Renewal (SRP-SLR)
Table 3.1-1, ``Summary of Aging Management Programs for Reactor Vessel,
Internals, and Reactor Coolant System Evaluated in Chapter IV of the
GALL-SLR Report''.
Generic Aging Lessons Learned for Subsequent License
Renewal (GALL-SLR) Report Tables IV.B2, IV.B3, IV.B4, IV.E.
SRP-SLR sections 3.1.2.2.9 and 3.1.3.2.9.
Aging Management Program XI.M16A, ``PWR Vessel Internals''
and GALL-SLR Report Table XI-01, ``FSAR Supplement Summaries for GALL-
SLR Report Chapter XI Aging Management Programs''.
GALL-SLR Report Table IX.C, ``Use of Terms for
Materials,'' to add the term ``Stellite''.
SRP-SLR Table 4.7-1, ``Examples of Potential Plant-
Specific TLAA Topics''.
IV. Availability of Documents
The documents identified in the following table are available in
ADAMS, as indicated.
[[Page 46737]]
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Document ADAMS accession No.
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NUREG-2191, ``Generic Aging Lessons ML16274A389, ML16274A399
Learned for Subsequent License
Renewal (GALL-SLR) Report''.
NUREG[dash]2192, ``Standard Review ML16274A402
Plan for Review of Subsequent License
Renewal Applications for Nuclear
Power Plants''.
Draft SLR-ISG-PWRVI-2020-XX; Updated ML20156A343
Aging Management Criteria for Reactor
Vessel Internal Components in
Pressurized Water Reactors.
MRP-227, Revision 1-A, ``Materials ML19339G350
Reliability Program: Pressurized
Water Reactor Internals Inspection
and Evaluation Guidelines'' dated
December 2019.
Final Safety Evaluation For Electric ML19081A001
Power Research Institute Topical
Report MRP-227, Revision 1,
``Materials Reliability Program:
Pressurized Water Reactor Internals
Inspection And Evaluations
Guideline'' dated April 2019.
March 28, 2019, Summary Of Category 2 ML19112A206
Public Meeting On Lessons Learned
From The Review Of The First
Subsequent License Renewal
Applications.
Summary of December 12, 2019, Category ML20016A347
2 Public Meeting On Lessons Learned
From The Review Of The First
Subsequent License Renewal
Applications..
February 20, 2020, Summary of Category ML20076E074
2 Public Meeting on Lessons Learned
from the Review of the First
Subsequent License Renewal
Applications.
Summary of March 25, 2020 Meeting with ML20107F702
Industry Related to Revisions to
Subsequent License Renewal Guidance
Documents.
Summary of April 3, 2020 Meeting with ML20107F733
Industry Regarding Changes to
Subsequent License Renewal Guidance
Documents.
Summary of April 7, 2020 Meeting with ML20107F699
Industry Regarding Revisions to the
Subsequent License Renewal Guidance
Documents.
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The NRC may post additional materials to the Federal Rulemaking
website at https://www.regulations.gov under Docket ID NRC-2020-0153.
The Federal Rulemaking website allows you to receive alerts when
changes or additions occur in a docket folder. To subscribe: (1)
Navigate to the docket folder (NRC-2020-0153); (2) click the ``Sign up
for Email Alerts'' link; and (3) enter your email address and select
how frequently you would like to receive emails (daily, weekly, or
monthly).
Dated: July 28, 2020.
For the Nuclear Regulatory Commission.
Robert Caldwell,
Deputy Director, Division of New and Renewed Licenses, Office of
Nuclear Reactor Regulation.
[FR Doc. 2020-16699 Filed 7-31-20; 8:45 am]
BILLING CODE 7590-01-P