Operational Leakage, 2361-2362 [2022-00686]

Download as PDF Federal Register / Vol. 87, No. 10 / Friday, January 14, 2022 / Proposed Rules maintained by DOE. For administrative purposes only, and in compliance with requirements of the Office of the Federal Register, the undersigned DOE Federal Register Liaison Officer has been authorized to sign and submit the document in electronic format for publication, as an official document of the Department of Energy. This administrative process in no way alters the legal effect of this document upon publication in the Federal Register. Signed in Washington, DC, on January 11, 2022. Treena V. Garrett, Federal Register Liaison Officer, U.S. Department of Energy. [FR Doc. 2022–00679 Filed 1–13–22; 8:45 am] BILLING CODE 6450–01–P NUCLEAR REGULATORY COMMISSION [NRC–2021–0173] Operational Leakage Nuclear Regulatory Commission. ACTION: Draft regulatory issue summary; public meeting and request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is seeking public comment on a draft regulatory issue summary (RIS) Operational Leakage. The NRC staff seeks to clarify regulatory requirements for all licensees of boiling and pressurized water reactors that apply to operational leakage. This draft RIS is a clarification for the NRC requirements for evaluation, control, and treatment of operational leakage in systems required to be operable by plant technical specifications (TS). DATES: Submit comments by March 15, 2022. 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 on or before this date. 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–2021–0173. 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 lotter on DSK11XQN23PROD with PROPOSALS1 SUMMARY: 16:36 Jan 13, 2022 • 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: Brian Benney, telephone: 301–415– 2767, email: Brian.Benney@nrc.gov, and Jay Collins, telephone: 301–415–4038, email: Jay.Collins@nrc.gov. Both are staff in the Office of Nuclear Reactor Regulation at the U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments 10 CFR Chapter I VerDate Sep<11>2014 in the FOR FURTHER INFORMATION CONTACT section of this document. Jkt 256001 A. Obtaining Information Please refer to Docket ID NRC–2021– 0173 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–2021–0173. • 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 (PDR) reference staff at 1–800–397–4209, 301– 415–4737, or by email to PDR.Resource@nrc.gov. The RIS 2022– XX, Operational Leakage, is available in ADAMS under Accession No. ML21166A122. • NRC’s PDR: You may examine and purchase copies of public documents, by appointment, at the PDR, Room P1 B35, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. To make an appointment to visit the PDR, please send an email to 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 PO 00000 Frm 00003 Fmt 4702 Sfmt 4702 2361 Federal Rulemaking website (https:// www.regulations.gov). Please include Docket ID NRC–2021–0173 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 This RIS is intended for all holders of operating licenses and combined licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel. Operational leakage is leakage through a flaw in the pressure retaining boundary of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) Code Class 1, 2 or 3 systems, structures, and components (SSC) discovered during the operational life of the nuclear power plant outside any ASME BPVC-required pressure test. The term ‘‘through-wall’’ describes a condition that extends from one surface to another surface in a component. If through-wall operational leakage is observed from an ASME BPVC Class 1, 2 or 3 SSC, and the structural integrity of the SSC must be established to conclude that the system remains operable, then the methods described in the provisions of the applicable inservice inspection requirements, as specified in paragraph 50.55a(g) of title 10 of the Code of Federal Regulations, must be used. These methods require analysis in accordance with the original construction code, the implementation of an NRC-approved ASME BPVC Code Case, or Nonmandatory Appendix U of ASME BPVC, Section XI, to verify structural integrity or perform a repair/ replacement activity. E:\FR\FM\14JAP1.SGM 14JAP1 2362 Federal Register / Vol. 87, No. 10 / Friday, January 14, 2022 / Proposed Rules This RIS emphasizes that operational leakage must be addressed in the same manner as leakage detected during an ASME BPVC, Section XI, pressure test. That is, when operational leakage is found in a system that is within the scope of ASME BPVC, Section XI, and is required to be operable by plant TS, the component must be evaluated by the licensee for operability. Structural integrity determinations must be conducted in accordance with the applicable provisions of the original construction code, the ASME BPVC, Section XI, or otherwise addressed through authorized methods. This entails evaluation in accordance with an NRC-approved Code Case; the use of Nonmandatory Appendix U of ASME BPVC, Section XI; or a repair/ replacement activity. The NRC issues RISs to communicate with stakeholders on a broad range of matters. This may include communication and clarification of NRC technical or policy positions on regulatory matters that have not been communicated to or are not broadly understood by the nuclear industry. As noted in ‘‘Relocation of Regulatory Issue Summary Notices in the Federal Register’’ (May 8, 2018, 83 FR 20858), this document is being published in the Proposed Rules section of the Federal Register to comply with publication requirements under 1 CFR chapter I. II. Proposed Action lotter on DSK11XQN23PROD with PROPOSALS1 The NRC is requesting public comments on the draft RIS. The NRC plans to hold a public meeting to discuss this RIS and the issues associated with it. Additional details regarding the meeting will be posted at least 10 days prior to the public meeting on the NRC’s Public Meeting Schedule website at https://www.nrc.gov/publicinvolve/public-meetings/index.cfm. All comments that are to receive consideration in the final RIS must still be submitted electronically or in writing as indicated in the ADDRESSES section of this document. The NRC staff will make a final determination regarding issuance of the RIS after it considers any public comments received in response to this request. Dated: January 11, 2022. For the Nuclear Regulatory Commission. Lisa M. Regner, Chief, Generic Communications and Operating Experience Branch, Division of Reactor Oversight, Office of Nuclear Regulatory Research. [FR Doc. 2022–00686 Filed 1–13–22; 8:45 am] BILLING CODE 7590–01–P VerDate Sep<11>2014 16:36 Jan 13, 2022 Jkt 256001 DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 39 [Docket No. FAA–2021–1178; Project Identifier MCAI–2021–00986–R] RIN 2120–AA64 Airworthiness Directives; Bell Textron Canada Limited (Type Certificate Previously Held by Bell Helicopter Textron Canada Limited) Helicopters Federal Aviation Administration (FAA), DOT. ACTION: Notice of proposed rulemaking (NPRM). AGENCY: The FAA proposes to supersede Airworthiness Directive (AD) 2020–20–06, which applies to certain Bell Helicopter Textron Canada Limited (now Bell Textron Canada Limited) Model 429 helicopters. AD 2020–20–06 requires repetitive inspections of certain cyclic and collective assembly bearings. Since the FAA issued AD 2020–20–06, the collective and cyclic bellcrank assemblies have been upgraded with corrosion resistant steel bearings. This proposed AD would retain some of the requirements of AD 2020–20–06 and depending on the inspection results, would require removing certain parts from service and installing the upgraded cyclic and collective bellcrank assemblies. This proposed AD would also require installing the upgraded collective and cyclic bellcrank assemblies on certain helicopters if not already installed, and would prohibit installing certain bellcrank assemblies. The FAA is proposing this AD to address the unsafe condition on these products. DATES: The FAA must receive comments on this proposed AD by February 28, 2022. ADDRESSES: You may send comments, using the procedures found in 14 CFR 11.43 and 11.45, by any of the following methods: • Federal eRulemaking Portal: Go to https://www.regulations.gov. Follow the instructions for submitting comments. • Fax: (202) 493–2251. • Mail: U.S. Department of Transportation, Docket Operations, M– 30, West Building Ground Floor, Room W12–140, 1200 New Jersey Avenue SE, Washington, DC 20590. • Hand Delivery: Deliver to Mail address above between 9 a.m. and 5 p.m., Monday through Friday, except Federal holidays. For service information identified in this NPRM, contact Bell Textron Canada SUMMARY: PO 00000 Frm 00004 Fmt 4702 Sfmt 4702 Limited, 12,800 Rue de l’Avenir, Mirabel, Quebec J7J 1R4, Canada; telephone 1–450–437–2862 or 1–800– 363–8023; fax 1–450–433–0272; email productsupport@bellflight.com; or at https://www.bellflight.com/support/ contact-support. You may view this service information at the FAA, Office of the Regional Counsel, Southwest Region, 10101 Hillwood Pkwy., Room 6N–321, Fort Worth, TX 76177. For information on the availability of this material at the FAA, call (817) 222– 5110. Examining the AD Docket You may examine the AD docket at https://www.regulations.gov by searching for and locating Docket No. FAA–2021–1178; or in person at Docket Operations between 9 a.m. and 5 p.m., Monday through Friday, except Federal holidays. The AD docket contains this NPRM, the Transport Canada AD, any comments received, and other information. The street address for Docket Operations is listed above. FOR FURTHER INFORMATION CONTACT: Andrea Jimenez, Aerospace Engineer, COS Program Management Section, Operational Safety Branch, Compliance & Airworthiness Division, FAA, 1600 Stewart Ave., Suite 410, Westbury, NY 11590; telephone (516) 228–7330; email andrea.jimenez@faa.gov. SUPPLEMENTARY INFORMATION: Comments Invited The FAA invites you to send any written relevant data, views, or arguments about this proposal. Send your comments to an address listed under ADDRESSES. Include ‘‘Docket No. FAA–2021–1178; Project Identifier MCAI–2021–00986–R’’ at the beginning of your comments. The most helpful comments reference a specific portion of the proposal, explain the reason for any recommended change, and include supporting data. The FAA will consider all comments received by the closing date and may amend this proposal because of those comments. Except for Confidential Business Information (CBI) as described in the following paragraph, and other information as described in 14 CFR 11.35, the FAA will post all comments received, without change, to https:// www.regulations.gov, including any personal information you provide. The agency will also post a report summarizing each substantive verbal contact received about this NPRM. Confidential Business Information CBI is commercial or financial information that is both customarily and actually treated as private by its owner. E:\FR\FM\14JAP1.SGM 14JAP1

Agencies

[Federal Register Volume 87, Number 10 (Friday, January 14, 2022)]
[Proposed Rules]
[Pages 2361-2362]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2022-00686]


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NUCLEAR REGULATORY COMMISSION

10 CFR Chapter I

[NRC-2021-0173]


Operational Leakage

AGENCY: Nuclear Regulatory Commission.

ACTION: Draft regulatory issue summary; public meeting and request for 
comment.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is seeking public 
comment on a draft regulatory issue summary (RIS) Operational Leakage. 
The NRC staff seeks to clarify regulatory requirements for all 
licensees of boiling and pressurized water reactors that apply to 
operational leakage. This draft RIS is a clarification for the NRC 
requirements for evaluation, control, and treatment of operational 
leakage in systems required to be operable by plant technical 
specifications (TS).

DATES: Submit comments by March 15, 2022. 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 on or before 
this date.

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-2021-0173. 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: Brian Benney, telephone: 301-415-2767, 
email: [email protected], and Jay Collins, telephone: 301-415-4038, 
email: [email protected]. Both are staff in the Office of Nuclear 
Reactor Regulation at 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-2021-0173 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-2021-0173.
     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 (PDR) reference staff at 1-800-397-4209, 301-415-4737, or 
by email to [email protected]. The RIS 2022-XX, Operational Leakage, 
is available in ADAMS under Accession No. ML21166A122.
     NRC's PDR: You may examine and purchase copies of public 
documents, by appointment, at the PDR, Room P1 B35, One White Flint 
North, 11555 Rockville Pike, Rockville, Maryland 20852. To make an 
appointment to visit the PDR, please send an email to 
[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-2021-0173 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

    This RIS is intended for all holders of operating licenses and 
combined licenses for nuclear power reactors, except those who have 
permanently ceased operations and have certified that fuel has been 
permanently removed from the reactor vessel.
    Operational leakage is leakage through a flaw in the pressure 
retaining boundary of American Society of Mechanical Engineers (ASME) 
Boiler and Pressure Vessel Code (BPVC) Code Class 1, 2 or 3 systems, 
structures, and components (SSC) discovered during the operational life 
of the nuclear power plant outside any ASME BPVC-required pressure 
test. The term ``through-wall'' describes a condition that extends from 
one surface to another surface in a component. If through-wall 
operational leakage is observed from an ASME BPVC Class 1, 2 or 3 SSC, 
and the structural integrity of the SSC must be established to conclude 
that the system remains operable, then the methods described in the 
provisions of the applicable inservice inspection requirements, as 
specified in paragraph 50.55a(g) of title 10 of the Code of Federal 
Regulations, must be used. These methods require analysis in accordance 
with the original construction code, the implementation of an NRC-
approved ASME BPVC Code Case, or Nonmandatory Appendix U of ASME BPVC, 
Section XI, to verify structural integrity or perform a repair/
replacement activity.

[[Page 2362]]

    This RIS emphasizes that operational leakage must be addressed in 
the same manner as leakage detected during an ASME BPVC, Section XI, 
pressure test. That is, when operational leakage is found in a system 
that is within the scope of ASME BPVC, Section XI, and is required to 
be operable by plant TS, the component must be evaluated by the 
licensee for operability. Structural integrity determinations must be 
conducted in accordance with the applicable provisions of the original 
construction code, the ASME BPVC, Section XI, or otherwise addressed 
through authorized methods. This entails evaluation in accordance with 
an NRC-approved Code Case; the use of Nonmandatory Appendix U of ASME 
BPVC, Section XI; or a repair/replacement activity.
    The NRC issues RISs to communicate with stakeholders on a broad 
range of matters. This may include communication and clarification of 
NRC technical or policy positions on regulatory matters that have not 
been communicated to or are not broadly understood by the nuclear 
industry.
    As noted in ``Relocation of Regulatory Issue Summary Notices in the 
Federal Register'' (May 8, 2018, 83 FR 20858), this document is being 
published in the Proposed Rules section of the Federal Register to 
comply with publication requirements under 1 CFR chapter I.

II. Proposed Action

    The NRC is requesting public comments on the draft RIS. The NRC 
plans to hold a public meeting to discuss this RIS and the issues 
associated with it. Additional details regarding the meeting will be 
posted at least 10 days prior to the public meeting on the NRC's Public 
Meeting Schedule website at https://www.nrc.gov/public-involve/public-meetings/index.cfm. All comments that are to receive consideration in 
the final RIS must still be submitted electronically or in writing as 
indicated in the ADDRESSES section of this document.
    The NRC staff will make a final determination regarding issuance of 
the RIS after it considers any public comments received in response to 
this request.

    Dated: January 11, 2022.

    For the Nuclear Regulatory Commission.
Lisa M. Regner,
Chief, Generic Communications and Operating Experience Branch, Division 
of Reactor Oversight, Office of Nuclear Regulatory Research.
[FR Doc. 2022-00686 Filed 1-13-22; 8:45 am]
BILLING CODE 7590-01-P
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