Acceptability of ASME Code Section XI, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants, for Non-Light Water Reactors, 54253-54254 [2021-21295]

Download as PDF Federal Register / Vol. 86, No. 187 / Thursday, September 30, 2021 / Notices NATIONAL SCIENCE FOUNDATION Notice of Permit Applications Received Under the Antarctic Conservation Act of 1978 National Science Foundation. Notice of permit applications received. AGENCY: ACTION: The National Science Foundation (NSF) is required to publish a notice of permit applications received to conduct activities regulated under the Antarctic Conservation Act of 1978. NSF has published regulations under the Antarctic Conservation Act in the Code of Federal Regulations. This is the required notice of permit applications received. DATES: Interested parties are invited to submit written data, comments, or views with respect to this permit application by November 1, 2021. This application may be inspected by interested parties at the Permit Office, address below. ADDRESSES: Comments should be addressed to Permit Office, Office of Polar Programs, National Science Foundation, 2415 Eisenhower Avenue, Alexandria, Virginia 22314 or ACApermits@nsf.gov. FOR FURTHER INFORMATION CONTACT: Polly Penhale, ACA Permit Officer, at the above address, 703–292–8030. SUPPLEMENTARY INFORMATION: The National Science Foundation, as directed by the Antarctic Conservation Act of 1978 (Pub. L. 95–541, 45 CFR 670), as amended by the Antarctic Science, Tourism and Conservation Act of 1996, has developed regulations for the establishment of a permit system for various activities in Antarctica and designation of certain animals and certain geographic areas as requiring special protection. The regulations establish such a permit system to designate Antarctic Specially Protected Areas. SUMMARY: LOTTER on DSK11XQN23PROD with NOTICES1 Application Details Permit Application: 2022–011 1. Applicant: Dr. John Durban, 446 Harbor Vista Drive, Friday Harbor WA, 98250. Activity for Which Permit is Requested: Waste Management. The applicant seeks a waste management permit under the Antarctic Conservation Act for activities associated with ongoing cetacean research in the Southern Ocean and Antarctic Peninsula region. The applicant proposes using unmanned aerial systems (UAS) pilots from ships and small boats to collect photogrammetry VerDate Sep<11>2014 18:15 Sep 29, 2021 Jkt 253001 images and blow samples from whales. UAS flights will be performed by experienced pilots and will last for a period of under 30 minutes. In addition to the pilots’ extensive experience, mitigation measures will be put into place to minimize loss of equipment and to recover equipment in the unlikely event of equipment failure. The applicant also seeks to use small projectile biopsy darts to collect tissue samples. Following discharge and sampling, the darts will float, and highvisibility collars ensure a high likelihood for retrieval. Location: Antarctic Peninsula Region. Southern Ross Sea Region. Dates of Permitted Activities: December 1, 2021–April 30, 2026. Erika N. Davis, Program Specialist, Office of Polar Programs. [FR Doc. 2021–21202 Filed 9–29–21; 8:45 am] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION [NRC–2021–0166] Acceptability of ASME Code Section XI, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants, for Non-Light Water Reactors Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft regulatory guide (DG), DG–1383, ‘‘Acceptability of ASME Code Section XI, Division 2, ‘Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,’ for Non-Light Water Reactors.’’ This proposed DG describes an approach that is acceptable to the NRC staff for the development and implementation of a preservice inspection (PSI) and inservice inspection (ISI) program for non-light water reactors (non-LWRs). It endorses, with conditions, the 2019 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), Section XI, ‘‘Rules for Inservice Inspection of Nuclear Power Plant Components,’’ Division 2, for non-LWR applications. This RG also describes a method that applicants can use to incorporate PSI and ISI programs into a licensing basis. DATES: Submit comments by November 15, 2021. Comments received after this date will be considered if it is practical SUMMARY: PO 00000 Frm 00105 Fmt 4703 Sfmt 4703 54253 to do so, but the NRC is able to ensure consideration only for comments received on or before this date. Although a time limit is given, comments and suggestions in connection with items for inclusion in guides currently being developed or improvements in all published guides are encouraged at any time. ADDRESSES: You may submit comments by any of the following methods; however, the NRC encourages electronic comment submission through the Federal Rulemaking Website: • Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC–2021–0166. Address questions about Docket IDs in Regulations.gov to Stacy Schumann; telephone: 301–415–0624; email: Stacy.Schumann@nrc.gov. For technical questions, contact the individuals 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 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: Timothy Lupold, Office of Nuclear Reactor Regulation, telephone: 301– 415–6448, email: Timothy.Lupold@ nrc.gov; Stephen Philpott, Office of Nuclear Reactor Regulation, telephone: 301–415–2365, email: Stephen.Philpott@nrc.gov; and Robert Roche-Rivera, Office of Nuclear Regulatory Research, telephone: 301– 415–8113, email: Robert.Roche-Rivera@ nrc.gov. All are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC–2021– 0166 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–2021–0166. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publicly available documents online in the E:\FR\FM\30SEN1.SGM 30SEN1 54254 Federal Register / Vol. 86, No. 187 / Thursday, September 30, 2021 / Notices 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. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. • 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. (ET), Monday through Friday, except Federal holidays. B. Submitting Comments The NRC encourages electronic comment submission through the Federal Rulemaking Website (https:// www.regulations.gov). Please include Docket ID NRC–2021–0166 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. LOTTER on DSK11XQN23PROD with NOTICES1 II. Additional Information The NRC is issuing for public comment a DG in the NRC’s ‘‘Regulatory Guide’’ series. This series was developed to describe methods that are acceptable to the NRC staff for implementing specific parts of the agency’s regulations, to explain techniques that the staff uses in evaluating specific issues or postulated events, and to describe information that the staff needs in its review of applications for permits and licenses. VerDate Sep<11>2014 18:15 Sep 29, 2021 Jkt 253001 The DG, entitled, ‘‘Acceptability of ASME Code Section XI, Division 2, ‘Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,’ for Non-Light Water Reactors,’’ is a proposed new Regulatory Guide 1.246 and is temporarily identified by its task number, DG–1383 (ADAMS Accession No. ML21120A185). The staff is also issuing for public comment a draft regulatory analysis (ADAMS Accession No. ML21120A192). This DG endorses, with conditions, the 2019 edition of ASME BPV Code, Section XI, Division 2. It also describes a method that applicants can use to incorporate PSI and ISI programs into a licensing basis. ASME BPV Code, Section XI, Division 2 provides a process for developing a RIM program similar to a traditional PSI and ISI program under ASME Code, Section XI, Division 1, ‘‘Rules for Inspection and Testing of Components of Light-WaterCooled Plants,’’ for all types of nuclear power plants. Because ASME Code, Section XI, Division 1, provides requirements for a PSI and ISI program for an LWR, the scope of this DG focuses on non-LWRs. The RIM program contains provisions beyond a traditional program, such as significant use of probabilistic risk assessment (PRA) to develop reliability targets for structures, systems, and components (SSCs) within the scope of the program. It also relies on establishing such practices as monitoring, nondestructive examination and repair and replacement to maintain the reliability of components based on the degradation mechanisms that may exist throughout the life of the plant. ASME Code, Section XI, Division 2, also provides a process for the identification of the scope, degradation mechanisms, and reliability targets for the in-scope SSCs; identification and evaluation of RIM strategies and uncertainties; program implementation; performance monitoring; and program updates to be applied for passive components to give assurance that the reliability will meet preestablished targets (developed from the PRA information for the facility). ASME Code, Section XI, Division 2, does not stipulate any specific strategies to be employed but calls for these to be developed by expert panels, considering types of examinations currently used for ASME Code, Section XI, Division 1, and known or potential degradation mechanisms for typical materials used in the construction of nuclear facilities. PO 00000 Frm 00106 Fmt 4703 Sfmt 4703 III. Backfitting, Forward Fitting, and Issue Finality DG–1383, if finalized, would not constitute backfitting as defined in section 50.109 of title 10 of the Code of Federal Regulations (10 CFR), ‘‘Backfitting,’’ and as described in NRC Management Directive (MD) 8.4, ‘‘Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests’’ (ADAMS Accession No. ML18093B087); constitute forward fitting as that term is defined and described in MD 8.4; or affect the issue finality of any approval issued under 10 CFR part 52, ‘‘Licenses, Certificates, and Approvals for Nuclear Power Plants.’’ As explained in DG–1383, applicants and licensees are not required to comply with the positions set forth in DG–1383. Dated: September 27, 2021. For the Nuclear Regulatory Commission. Meraj Rahimi, Chief, Regulatory Guide and Programs Management Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2021–21295 Filed 9–29–21; 8:45 am] BILLING CODE 7590–01–P SECURITIES AND EXCHANGE COMMISSION [Investment Company Act Release No. 34384] Notice of Applications for Deregistration Under Section 8(f) of the Investment Company Act of 1940 September 24, 2021. The following is a notice of applications for deregistration under section 8(f) of the Investment Company Act of 1940 for the month of September 2021. A copy of each application may be obtained via the Commission’s website by searching for the file number, or for an applicant using the Company name box, at https://www.sec.gov/search/ search.htm or by calling (202) 551– 8090. An order granting each application will be issued unless the SEC orders a hearing. Interested persons may request a hearing on any application by emailing the SEC’s Secretary at Secretarys-Office@sec.gov and serving the relevant applicant with a copy of the request by email, if an email address is listed for the relevant applicant below, or personally or by mail, if a physical address is listed for the relevant applicant below. Hearing requests should be received by the SEC by 5:30 p.m. on October 19, 2021, and should be accompanied by proof of service on applicants, in the form of an affidavit or, for lawyers, a certificate of E:\FR\FM\30SEN1.SGM 30SEN1

Agencies

[Federal Register Volume 86, Number 187 (Thursday, September 30, 2021)]
[Notices]
[Pages 54253-54254]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2021-21295]


=======================================================================
-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[NRC-2021-0166]


Acceptability of ASME Code Section XI, Division 2, Requirements 
for Reliability and Integrity Management (RIM) Programs for Nuclear 
Power Plants, for Non-Light Water Reactors

AGENCY: Nuclear Regulatory Commission.

ACTION: Draft regulatory guide; request for comment.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for 
public comment a draft regulatory guide (DG), DG-1383, ``Acceptability 
of ASME Code Section XI, Division 2, `Requirements for Reliability and 
Integrity Management (RIM) Programs for Nuclear Power Plants,' for Non-
Light Water Reactors.'' This proposed DG describes an approach that is 
acceptable to the NRC staff for the development and implementation of a 
preservice inspection (PSI) and inservice inspection (ISI) program for 
non-light water reactors (non-LWRs). It endorses, with conditions, the 
2019 Edition of the American Society of Mechanical Engineers (ASME) 
Boiler and Pressure Vessel Code (ASME Code), Section XI, ``Rules for 
Inservice Inspection of Nuclear Power Plant Components,'' Division 2, 
for non-LWR applications. This RG also describes a method that 
applicants can use to incorporate PSI and ISI programs into a licensing 
basis.

DATES: Submit comments by November 15, 2021. Comments received after 
this date will be considered if it is practical to do so, but the NRC 
is able to ensure consideration only for comments received on or before 
this date. Although a time limit is given, comments and suggestions in 
connection with items for inclusion in guides currently being developed 
or improvements in all published guides are encouraged at any time.

ADDRESSES: You may submit comments by any of the following methods; 
however, the NRC encourages electronic comment submission through the 
Federal Rulemaking Website:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2021-0166. Address 
questions about Docket IDs in Regulations.gov to Stacy Schumann; 
telephone: 301-415-0624; email: [email protected]. For technical 
questions, contact the individuals 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 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: Timothy Lupold, Office of Nuclear 
Reactor Regulation, telephone: 301-415-6448, email: 
[email protected]; Stephen Philpott, Office of Nuclear Reactor 
Regulation, telephone: 301-415-2365, email: [email protected]; 
and Robert Roche-Rivera, Office of Nuclear Regulatory Research, 
telephone: 301-415-8113, email: [email protected]. All are 
staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2021-0166 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-2021-0166.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly available documents online in the

[[Page 54254]]

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]. The ADAMS accession number for each 
document referenced (if it is available in ADAMS) is provided the first 
time that it is mentioned in this document.
     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. (ET), Monday through 
Friday, except Federal holidays.

B. Submitting Comments

    The NRC encourages electronic comment submission through the 
Federal Rulemaking Website (https://www.regulations.gov). Please 
include Docket ID NRC-2021-0166 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. Additional Information

    The NRC is issuing for public comment a DG in the NRC's 
``Regulatory Guide'' series. This series was developed to describe 
methods that are acceptable to the NRC staff for implementing specific 
parts of the agency's regulations, to explain techniques that the staff 
uses in evaluating specific issues or postulated events, and to 
describe information that the staff needs in its review of applications 
for permits and licenses.
    The DG, entitled, ``Acceptability of ASME Code Section XI, Division 
2, `Requirements for Reliability and Integrity Management (RIM) 
Programs for Nuclear Power Plants,' for Non-Light Water Reactors,'' is 
a proposed new Regulatory Guide 1.246 and is temporarily identified by 
its task number, DG-1383 (ADAMS Accession No. ML21120A185). The staff 
is also issuing for public comment a draft regulatory analysis (ADAMS 
Accession No. ML21120A192).
    This DG endorses, with conditions, the 2019 edition of ASME BPV 
Code, Section XI, Division 2. It also describes a method that 
applicants can use to incorporate PSI and ISI programs into a licensing 
basis. ASME BPV Code, Section XI, Division 2 provides a process for 
developing a RIM program similar to a traditional PSI and ISI program 
under ASME Code, Section XI, Division 1, ``Rules for Inspection and 
Testing of Components of Light-Water-Cooled Plants,'' for all types of 
nuclear power plants. Because ASME Code, Section XI, Division 1, 
provides requirements for a PSI and ISI program for an LWR, the scope 
of this DG focuses on non-LWRs. The RIM program contains provisions 
beyond a traditional program, such as significant use of probabilistic 
risk assessment (PRA) to develop reliability targets for structures, 
systems, and components (SSCs) within the scope of the program. It also 
relies on establishing such practices as monitoring, nondestructive 
examination and repair and replacement to maintain the reliability of 
components based on the degradation mechanisms that may exist 
throughout the life of the plant.
    ASME Code, Section XI, Division 2, also provides a process for the 
identification of the scope, degradation mechanisms, and reliability 
targets for the in-scope SSCs; identification and evaluation of RIM 
strategies and uncertainties; program implementation; performance 
monitoring; and program updates to be applied for passive components to 
give assurance that the reliability will meet preestablished targets 
(developed from the PRA information for the facility). ASME Code, 
Section XI, Division 2, does not stipulate any specific strategies to 
be employed but calls for these to be developed by expert panels, 
considering types of examinations currently used for ASME Code, Section 
XI, Division 1, and known or potential degradation mechanisms for 
typical materials used in the construction of nuclear facilities.

III. Backfitting, Forward Fitting, and Issue Finality

    DG-1383, if finalized, would not constitute backfitting as defined 
in section 50.109 of title 10 of the Code of Federal Regulations (10 
CFR), ``Backfitting,'' and as described in NRC Management Directive 
(MD) 8.4, ``Management of Backfitting, Forward Fitting, Issue Finality, 
and Information Requests'' (ADAMS Accession No. ML18093B087); 
constitute forward fitting as that term is defined and described in MD 
8.4; or affect the issue finality of any approval issued under 10 CFR 
part 52, ``Licenses, Certificates, and Approvals for Nuclear Power 
Plants.'' As explained in DG-1383, applicants and licensees are not 
required to comply with the positions set forth in DG-1383.

    Dated: September 27, 2021.

    For the Nuclear Regulatory Commission.
Meraj Rahimi,
Chief, Regulatory Guide and Programs Management Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2021-21295 Filed 9-29-21; 8:45 am]
BILLING CODE 7590-01-P
This site is protected by reCAPTCHA and the Google Privacy Policy and Terms of Service apply.