Changes to Subsequent License Renewal Guidance Documents Regarding Reactor Vessel Internal Components in Pressurized Water Reactors, 46735-46737 [2020-16699]
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<![CDATA[
Federal Register / Vol. 85, No. 149 / Monday, August 3, 2020 / Notices
see ‘‘Obtaining Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
FOR FURTHER INFORMATION CONTACT:
Thomas Aird, Office of Nuclear
Regulatory Research, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 301–415–
2442; email: Thomas.Aird@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2018–
0028 when contacting the NRC about
the availability of information for this
action. You may obtain publiclyavailable 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–2018–0028.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable 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 pdr.resource@
nrc.gov. The draft NUREG–2240 is
available in ADAMS under Accession
ML20206L359.
khammond on DSKJM1Z7X2PROD with NOTICES
B. Submitting Comments
Please include Docket ID NRC–2018–
0028 in the subject line of 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 posts all comment
submissions at https://
www.regulations.gov as well as entering
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
VerDate Sep<11>2014
20:39 Jul 31, 2020
Jkt 250001
entering the comment submissions into
ADAMS.
II. Discussion
Draft NUREG–2240 summarizes the
results of a research project on flood
penetration seals installed at nuclear
power plants (NPPs). The objectives of
this research project were to
characterize flood penetration seals
currently installed at NPPs and to
develop a test protocol that evaluated
the effectiveness and performance of
flood penetration seals in their installed
configurations. The test protocol
described in draft NUREG–2240 is
intended to support the evaluation of
the flood mitigation performance of
penetration seals that are installed to
protect openings in barriers (walls/
floors) that have been otherwise
credited as having a flood resistance
rating in support of a flood mitigation
program at NPPs.
The overall research project consisted
of three phases: (1) Profiling of flood
penetration seals currently used in U.S.
NPPs; (2) developing a draft ex-situ
performance testing protocol; and (3)
performing limited testing of several
seal types and applications to evaluate
and refine the testing protocol. Project
materials including a draft test protocol
from phases 1 and 2 were published in
the Federal Register for public comment
on February 20, 2018 (83 FR 7239).
After a 30-day public comment period,
the public comments were assessed, and
the draft test protocol was updated as
necessary.
As part of the third and final phase of
this research project, a limited series of
flood tests were conducted to assess the
effectiveness and viability of the
developed testing protocol. As the flood
experiments took place, the draft
protocol was assessed using the test
data. Informal observations of
individual flood seal performance were
recorded and described in the draft
NUREG, but such observations should
not be considered exhaustive or as
ascribing specific properties/
qualifications to the flood seals
themselves. The overall results of these
tests and subsequent amendments to the
test protocol are outlined in draft
NUREG–2240.
This document is not intended for
interim use. The NRC will review public
comments received on the document
and incorporate suggested changes as
appropriate.
PO 00000
Dated: July 28, 2020.
Frm 00150
Fmt 4703
Sfmt 4703
46735
For the Nuclear Regulatory Commission.
Mark H. Salley,
Chief, Fire and External Hazard Analysis
Branch, Division of Risk Analysis, Office of
Nuclear Regulatory Research.
[FR Doc. 2020–16717 Filed 7–31–20; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2020–0153]
Changes to Subsequent License
Renewal Guidance Documents
Regarding Reactor Vessel Internal
Components in Pressurized Water
Reactors
Nuclear Regulatory
Commission.
ACTION: Draft interim staff guidance;
request for comment.
AGENCY:
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:
Jennifer.Borges@nrc.gov. 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
SUMMARY:
E:\FR\FM\03AUN1.SGM
03AUN1
46736
Federal Register / Vol. 85, No. 149 / Monday, August 3, 2020 / Notices
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: William.Burton@
nrc.gov.
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 publiclyavailable 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 publiclyavailable 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 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.
• NRC’s License Renewal Interim
Staff Guidance Website: SLR–ISG
documents are available online at
https://www.nrc.gov/reading-rm/doccollections/isg/license-renewal.html.
khammond on DSKJM1Z7X2PROD with NOTICES
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.
VerDate Sep<11>2014
20:39 Jul 31, 2020
Jkt 250001
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
PO 00000
Frm 00151
Fmt 4703
Sfmt 4703
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.
E:\FR\FM\03AUN1.SGM
03AUN1
Federal Register / Vol. 85, No. 149 / Monday, August 3, 2020 / Notices
ADAMS accession
No.
Document
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 in Pressurized Water Reactors.
MRP–227, Revision 1–A, ‘‘Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation
Guidelines’’ dated December 2019.
Final Safety Evaluation For Electric 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 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.
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]
POSTAL REGULATORY COMMISSION
[Docket Nos. MC2020–206 and CP2020–233]
New Postal Product
Postal Regulatory Commission.
Notice.
AGENCY:
The Commission is noticing a
recent Postal Service filing for the
Commission’s consideration concerning
a negotiated service agreement. This
notice informs the public of the filing,
invites public comment, and takes other
administrative steps.
khammond on DSKJM1Z7X2PROD with NOTICES
SUMMARY:
VerDate Sep<11>2014
20:39 Jul 31, 2020
Jkt 250001
Comments are due: August 5,
2020.
Submit comments
electronically via the Commission’s
Filing Online system at https://
www.prc.gov. Those who cannot submit
comments electronically should contact
the person identified in the FOR FURTHER
INFORMATION CONTACT section by
telephone for advice on filing
alternatives.
ADDRESSES:
FOR FURTHER INFORMATION CONTACT:
David A. Trissell, General Counsel, at
202–789–6820.
SUPPLEMENTARY INFORMATION:
Table of Contents
I. Introduction
II. Docketed Proceeding(s)
I. Introduction
BILLING CODE 7590–01–P
ACTION:
DATES:
The Commission gives notice that the
Postal Service filed request(s) for the
Commission to consider matters related
to negotiated service agreement(s). The
request(s) may propose the addition or
removal of a negotiated service
agreement from the market dominant or
the competitive product list, or the
modification of an existing product
currently appearing on the market
dominant or the competitive product
list.
Section II identifies the docket
number(s) associated with each Postal
Service request, the title of each Postal
Service request, the request’s acceptance
date, and the authority cited by the
PO 00000
Frm 00152
Fmt 4703
46737
Sfmt 4703
ML16274A389,
ML16274A399
ML16274A402
ML20156A343
ML19339G350
ML19081A001
ML19112A206
ML20016A347
ML20076E074
ML20107F702
ML20107F733
ML20107F699
Postal Service for each request. For each
request, the Commission appoints an
officer of the Commission to represent
the interests of the general public in the
proceeding, pursuant to 39 U.S.C. 505
(Public Representative). Section II also
establishes comment deadline(s)
pertaining to each request.
The public portions of the Postal
Service’s request(s) can be accessed via
the Commission’s website (https://
www.prc.gov). Non-public portions of
the Postal Service’s request(s), if any,
can be accessed through compliance
with the requirements of 39 CFR
3011.301.1
The Commission invites comments on
whether the Postal Service’s request(s)
in the captioned docket(s) are consistent
with the policies of title 39. For
request(s) that the Postal Service states
concern market dominant product(s),
applicable statutory and regulatory
requirements include 39 U.S.C. 3622, 39
U.S.C. 3642, 39 CFR part 3030, and 39
CFR part 3040, subpart B. For request(s)
that the Postal Service states concern
competitive product(s), applicable
statutory and regulatory requirements
include 39 U.S.C. 3632, 39 U.S.C. 3633,
39 U.S.C. 3642, 39 CFR part 3035, and
39 CFR part 3040, subpart B. Comment
deadline(s) for each request appear in
section II.
1 See Docket No. RM2018–3, Order Adopting
Final Rules Relating to Non-Public Information,
June 27, 2018, Attachment A at 19–22 (Order No.
4679).
E:\FR\FM\03AUN1.SGM
03AUN1
]]>Agencies
[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]
-----------------------------------------------------------------------
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.
-----------------------------------------------------------------------
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.
------------------------------------------------------------------------
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.
------------------------------------------------------------------------
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
