Changes to Subsequent License Renewal Guidance Documents Regarding Reactor Vessel Internal Components in Pressurized Water Reactors, 46735-46737 [2020-16699]

Download as PDF 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 http:// 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 (http:// 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]]



------------------------------------------------------------------------
               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