Acceptability of ASME Code Section III, Division 5, High Temperature Reactors, 46888-46889 [2021-17916]
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Federal Register / Vol. 86, No. 159 / Friday, August 20, 2021 / Notices
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 a requiring
special protection. The regulations
establish such a permit system to
designate Antarctic Specially Protected
Areas.
Application Details
Permit Application: 2022–006
1. Applicant: Ron Naveen, Oceanites,
PO Box 15259, Chevy Case, MD 20825.
Activity for Which Permit Is
Requested: Waste management. The
applicant seeks a waste management
permit to expand upon existing research
activities conducted in the West
Antarctica Peninsula. The applicant
seeks to use unoccupied aerial systems
(UAS) to enable more efficient
monitoring of penguin breeding sites
and to increase penguin censusing
capabilities. The permit will cover any
unintentional or accidental loss of
remotely piloted aircrafts through
planned research operations. The
applicant has provided a detailed
mitigation plan to minimize risk of
equipment loss, including use of
observers and experienced pilots.
Location: West Antarctic Peninsula.
Dates of Permitted Activities:
November 1, 2021–August 31, 2023.
Erika N. Davis,
Program Specialist, Office of Polar Programs.
[FR Doc. 2021–17823 Filed 8–19–21; 8:45 am]
BILLING CODE 7555–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2021–0117]
Acceptability of ASME Code Section III,
Division 5, High Temperature Reactors
Nuclear Regulatory
Commission.
ACTION: Draft regulatory guide; draft
NUREG; request for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing for public
comment a draft regulatory guide (DG),
DG–1380 (proposed Revision 2 to
Regulatory Guide [RG] 1.87),
‘‘Acceptability of ASME Code Section
III, Division 5, ‘High Temperature
Reactors’’’ and accompanying draft
NUREG–2245, ‘‘Technical Review of the
2017 Edition of ASME Section III,
Division 5, ‘High Temperature
Reactors,’’’ that documents the NRC
staff’s review of the 2017 Edition of
ASME Section III, Division 5, certain
khammond on DSKJM1Z7X2PROD with NOTICES
SUMMARY:
VerDate Sep<11>2014
17:27 Aug 19, 2021
Jkt 253001
portions of the 2019 Edition, and
associated Code Cases N–861 and N–
862. This DG describes an approach that
is acceptable to the staff of the NRC to
meet regulatory requirements for
mechanical/structural integrity of
components that operate in elevated
temperature environments and that are
subject to time-dependent material
properties and failure modes. It
endorses, with conditions, the American
Society of Mechanical Engineers
(ASME) Boiler and Pressure Vessel Code
(ASME Code) Section III, ‘‘Rules for
Construction of Nuclear Facility
Components,’’ Division 5, ‘‘High
Temperature Reactors.’’ The draft
NUREG provides the technical basis for
DG–1380.
DATES: Submit comments by October 19,
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–2021–0117. 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:
Jeffrey Poehler, Office of Nuclear
Regulatory Research, telephone: 301–
415–8353, email: Jeffrey.Poehler@
nrc.gov, Robert Roche-Rivera, Office of
Nuclear Regulatory Research, telephone:
301–415–8113, email: Robert.RocheRivera@nrc.gov, and Jordan Hoellman,
Office of Nuclear Reactor Regulation,
telephone: 301–415–5481, email:
PO 00000
Frm 00068
Fmt 4703
Sfmt 4703
Jordan.Hoellman2@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–
0117 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–2021–0117.
• 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 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–2021–0117 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
E:\FR\FM\20AUN1.SGM
20AUN1
Federal Register / Vol. 86, No. 159 / Friday, August 20, 2021 / Notices
khammond on DSKJM1Z7X2PROD with NOTICES
they do not want to be publicly
disclosed in their comment
submissions. 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 draft guide 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.
This proposed Revision 2 to RG 1.87,
entitled ‘‘Acceptability of ASME Code
Section III, Division 5, ‘High
Temperature Reactors,’’’ is temporarily
identified by its task number, DG–1380
(ADAMS Accession No. ML21091A276).
The staff is also issuing for public
comment a draft regulatory analysis
(ADAMS Accession No. ML21091A277),
and draft NUREG–2245, ‘‘Technical
Review of the 2017 Edition of ASME
Section III, Division 5, ‘High
Temperature Reactors,’’’ (ADAMS
Accession No. ML21223A097) that
documents the NRC staff’s review of the
2017 Edition of ASME Section III,
Division 5, certain portions of the 2019
Edition, and associated Code Cases N–
861 and N–862. Code Cases N–872 and
N–898 (‘‘the Alloy 617 Code Cases’’),
approved by ASME in 2020, are not
included in this review and are being
considered for endorsement in a parallel
effort.
The NRC published Revision 1 of RG
1.87, ‘‘Guidance for Construction of
Class 1 Components in ElevatedTemperature Reactors,’’ in June 1975 to
provide licensees and applicants with
agency-approved guidance for
complying with paragraph 50.55a of
title 10 of the Code of Federal
Regulations (10 CFR) ‘‘Codes and
standards,’’ and General Design
Criterion 1, ‘‘Quality Standards and
Records.’’ The guide described interim
licensing guidelines to aid applicants in
implementing these requirements with
respect to ASME Class 1 components
operating at elevated temperatures.
Specifically, the guide approved, with
conditions, the initial versions of five
Code Cases namely, Code Cases 1592–
0, 1593–0, 1594–0, 1595–0, and 1596–0.
These five Code Cases are the precursors
to the other iterations of ASME’s high
temperature construction rules: Code
VerDate Sep<11>2014
17:27 Aug 19, 2021
Jkt 253001
Cases N–47 through N–51; ASME Code,
Section III, Subsection NH; and
currently ASME Code, Section III,
Division 5. The current version of RG
1.87 (Revision 1) does not reflect the
changes and updates with respect to
modern design, fabrication, inspection,
testing, and overpressure provisions
(among others) addressed by the
aforementioned Code iterations,
research, and operating experience.
This revision (Revision 2) updates the
guidance to endorse, with conditions,
the 2017 Edition of ASME Code Section
III, Division 5, as a method acceptable
to the staff for the materials,
mechanical/structural design,
construction, testing, and quality
assurance of mechanical systems and
components and their supports of hightemperature reactors. This revision of
the guide also addresses the
acceptability of the Code Cases N–861
and N–862, which are related to
Division 5 of the ASME Code, Section
III. Draft NUREG–2245 provides the
technical basis for NRC staff positions
stated in the DG, including proposed
exceptions and limitations on the use of
Division 5. Additionally, this revision
adds an appendix to the RG namely
Appendix A, ‘‘High Temperature
Reactor Quality Group Classification,’’
which provides guidance for the quality
group classification of components in
non-light water reactor designs.
III. Backfitting, Forward Fitting, and
Issue Finality
DG–1380 and NUREG–2245, if
finalized, would not constitute
backfitting as defined in 10 CFR 50.109,
‘‘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.’’
The guidance would not apply to any
current licensees or applicants or
existing or requested approvals under
10 CFR part 52, and therefore its
issuance cannot be a backfit or forward
fit or affect issue finality. Further, as
explained in DG–1380, applicants and
licensees would not be required to
comply with the positions set forth in
DG–1380.
Dated: August 17, 2021.
PO 00000
Frm 00069
Fmt 4703
Sfmt 4703
46889
For the Nuclear Regulatory Commission.
Ronaldo V. Jenkins,
Acting Chief, Regulatory Guidance and
Programs Management Branch, Division of
Engineering, Office of Nuclear Regulatory
Research.
[FR Doc. 2021–17916 Filed 8–19–21; 8:45 am]
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[Docket Nos. MC2021–126 and CP2021–130]
New Postal Products
Postal Regulatory Commission.
Notice.
AGENCY:
ACTION:
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.
DATES: Comments are due: August 23,
2021.
ADDRESSES: 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.
FOR FURTHER INFORMATION CONTACT:
David A. Trissell, General Counsel, at
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SUPPLEMENTARY INFORMATION:
SUMMARY:
Table of Contents
I. Introduction
II. Docketed Proceeding(s)
I. Introduction
The Commission gives notice that the
Postal Service filed request(s) for the
Commission to consider matters related
to negotiated service agreement(s). The
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removal of a negotiated service
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the competitive product list, or the
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E:\FR\FM\20AUN1.SGM
20AUN1
Agencies
[Federal Register Volume 86, Number 159 (Friday, August 20, 2021)]
[Notices]
[Pages 46888-46889]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2021-17916]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2021-0117]
Acceptability of ASME Code Section III, Division 5, High
Temperature Reactors
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft regulatory guide; draft NUREG; request for comment.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for
public comment a draft regulatory guide (DG), DG-1380 (proposed
Revision 2 to Regulatory Guide [RG] 1.87), ``Acceptability of ASME Code
Section III, Division 5, `High Temperature Reactors''' and accompanying
draft NUREG-2245, ``Technical Review of the 2017 Edition of ASME
Section III, Division 5, `High Temperature Reactors,''' that documents
the NRC staff's review of the 2017 Edition of ASME Section III,
Division 5, certain portions of the 2019 Edition, and associated Code
Cases N-861 and N-862. This DG describes an approach that is acceptable
to the staff of the NRC to meet regulatory requirements for mechanical/
structural integrity of components that operate in elevated temperature
environments and that are subject to time-dependent material properties
and failure modes. It endorses, with conditions, the American Society
of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME
Code) Section III, ``Rules for Construction of Nuclear Facility
Components,'' Division 5, ``High Temperature Reactors.'' The draft
NUREG provides the technical basis for DG-1380.
DATES: Submit comments by October 19, 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-2021-0117. 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: Jeffrey Poehler, Office of Nuclear
Regulatory Research, telephone: 301-415-8353, email:
[email protected], Robert Roche-Rivera, Office of Nuclear
Regulatory Research, telephone: 301-415-8113, email: [email protected], and Jordan Hoellman, Office of Nuclear Reactor
Regulation, telephone: 301-415-5481, 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-2021-0117 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-2021-0117.
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 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-2021-0117 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
[[Page 46889]]
they do not want to be publicly disclosed in their comment submissions.
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 draft guide 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.
This proposed Revision 2 to RG 1.87, entitled ``Acceptability of
ASME Code Section III, Division 5, `High Temperature Reactors,''' is
temporarily identified by its task number, DG-1380 (ADAMS Accession No.
ML21091A276). The staff is also issuing for public comment a draft
regulatory analysis (ADAMS Accession No. ML21091A277), and draft NUREG-
2245, ``Technical Review of the 2017 Edition of ASME Section III,
Division 5, `High Temperature Reactors,''' (ADAMS Accession No.
ML21223A097) that documents the NRC staff's review of the 2017 Edition
of ASME Section III, Division 5, certain portions of the 2019 Edition,
and associated Code Cases N-861 and N-862. Code Cases N-872 and N-898
(``the Alloy 617 Code Cases''), approved by ASME in 2020, are not
included in this review and are being considered for endorsement in a
parallel effort.
The NRC published Revision 1 of RG 1.87, ``Guidance for
Construction of Class 1 Components in Elevated-Temperature Reactors,''
in June 1975 to provide licensees and applicants with agency-approved
guidance for complying with paragraph 50.55a of title 10 of the Code of
Federal Regulations (10 CFR) ``Codes and standards,'' and General
Design Criterion 1, ``Quality Standards and Records.'' The guide
described interim licensing guidelines to aid applicants in
implementing these requirements with respect to ASME Class 1 components
operating at elevated temperatures. Specifically, the guide approved,
with conditions, the initial versions of five Code Cases namely, Code
Cases 1592-0, 1593-0, 1594-0, 1595-0, and 1596-0. These five Code Cases
are the precursors to the other iterations of ASME's high temperature
construction rules: Code Cases N-47 through N-51; ASME Code, Section
III, Subsection NH; and currently ASME Code, Section III, Division 5.
The current version of RG 1.87 (Revision 1) does not reflect the
changes and updates with respect to modern design, fabrication,
inspection, testing, and overpressure provisions (among others)
addressed by the aforementioned Code iterations, research, and
operating experience.
This revision (Revision 2) updates the guidance to endorse, with
conditions, the 2017 Edition of ASME Code Section III, Division 5, as a
method acceptable to the staff for the materials, mechanical/structural
design, construction, testing, and quality assurance of mechanical
systems and components and their supports of high-temperature reactors.
This revision of the guide also addresses the acceptability of the Code
Cases N-861 and N-862, which are related to Division 5 of the ASME
Code, Section III. Draft NUREG-2245 provides the technical basis for
NRC staff positions stated in the DG, including proposed exceptions and
limitations on the use of Division 5. Additionally, this revision adds
an appendix to the RG namely Appendix A, ``High Temperature Reactor
Quality Group Classification,'' which provides guidance for the quality
group classification of components in non-light water reactor designs.
III. Backfitting, Forward Fitting, and Issue Finality
DG-1380 and NUREG-2245, if finalized, would not constitute
backfitting as defined in 10 CFR 50.109, ``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.'' The guidance
would not apply to any current licensees or applicants or existing or
requested approvals under 10 CFR part 52, and therefore its issuance
cannot be a backfit or forward fit or affect issue finality. Further,
as explained in DG-1380, applicants and licensees would not be required
to comply with the positions set forth in DG-1380.
Dated: August 17, 2021.
For the Nuclear Regulatory Commission.
Ronaldo V. Jenkins,
Acting Chief, Regulatory Guidance and Programs Management Branch,
Division of Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2021-17916 Filed 8-19-21; 8:45 am]
BILLING CODE 7590-01-P