[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