Approval of American Society of Mechanical Engineers' Code Cases, 11934-11950 [2022-04374]
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11934
Federal Register / Vol. 87, No. 42 / Thursday, March 3, 2022 / Rules and Regulations
heading for subpart G, consisting of
§§ 201.29 through 201.34, in its place to
read as follows:
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 50
Subpart G—Market Agency, Dealer,
and Packer Bonds
[NRC–2017–0025]
RIN 3150–AJ94
10. Remove the undesignated center
heading before § 201.39 and add a
heading for subpart H, consisting of
§§ 201.39 through 201.42, in its place to
read as follows:
■
Subpart H—Proceeds of Sale
Approval of American Society of
Mechanical Engineers’ Code Cases
Nuclear Regulatory
Commission.
ACTION: Final rule.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is amending its
regulations to incorporate by reference
revisions of three regulatory guides to
approve new, revised, and reaffirmed
code cases published by the American
Society of Mechanical Engineers. The
NRC is also incorporating by reference
one NRC NUREG associated with a
condition on one of the regulatory
guides. This action allows nuclear
power plant licensees and applicants for
construction permits, operating licenses,
combined licenses, standard design
certifications, standard design
approvals, and manufacturing licenses
to use the code cases listed in these
regulatory guides as voluntary
alternatives to engineering standards for
the construction, inservice inspection,
and inservice testing of nuclear power
plant components. These engineering
standards are set forth in the American
Society of Mechanical Engineers’ Boiler
and Pressure Vessel Codes and
American Society of Mechanical
Engineers’ Operation and Maintenance
Codes, which are currently incorporated
by reference into the NRC’s regulations.
Further, this final rule announces the
availability of a related regulatory guide,
not incorporated by reference into the
NRC’s regulations, that lists code cases
that the NRC has not approved for use.
DATES: This final rule is effective on
April 4, 2022. The incorporation by
reference of certain publications listed
in the regulation is approved by the
Director of the Federal Register as of
April 4, 2022.
ADDRESSES: Please refer to Docket ID
NRC–2017–0025 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–2017–0025. Address
questions about NRC dockets to Dawn
Forder; telephone: 301–415–3407;
email: Dawn.Forder@nrc.gov. For
technical questions, contact the
SUMMARY:
11. Remove the undesignated center
heading before § 201.43 and add a
heading for subpart I, consisting of
§§ 201.43 through 201.49, in its place to
read as follows:
■
Subpart I—Accounts and Records
12. Remove the undesignated center
heading before § 201.53 and add a
heading for subpart J, consisting of
§§ 201.53 through 201.70, in its place to
read as follows:
■
Subpart J—Trade Practices
13. Remove the undesignated center
heading before § 201.71 and add a
heading for subpart K, consisting of
§§ 201.71 through 201.82, in its place to
read as follows:
■
Subpart K—Services
14. Remove the undesignated center
heading before § 201.86 and add a
heading for subpart L, consisting of
§§ 201.86, in its place to read as follows:
■
Subpart L—Inspection of Brands
15. Remove the undesignated center
heading before § 201.94 and add a
heading for subpart M, consisting of
§§ 201.94 through 201.99, in its place to
read as follows:
■
Subpart M—General
16. Remove the undesignated center
heading before § 201.100 and add a
heading for subpart N, consisting of
§§ 201.100 through 201.218, in its place
to read as follows:
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■
Subpart N—Packers and Live Poultry
Dealers
Erin Morris,
Associate Administrator, Agricultural
Marketing Service.
[FR Doc. 2022–04172 Filed 3–2–22; 8:45 am]
BILLING CODE P
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individuals listed in the FOR FURTHER
section of this
document.
• 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 (PDR)
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 PDR: You may examine and
purchase copies of public documents,
by appointment, at the NRC’s 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.
• Technical Library: The Technical
Library, which is located at Two White
Flint North, 11545 Rockville Pike,
Rockville, Maryland 20852, is open by
appointment only. Interested parties
may make appointments to examine
documents by contacting the NRC
Technical Library by email at
Library.Resource@nrc.gov between 8:00
a.m. and 4:00 p.m. (ET), Monday
through Friday, except Federal holidays.
FOR FURTHER INFORMATION CONTACT:
Martha Barillas, Office of Nuclear
Material Safety and Safeguards;
telephone: 301–415–2760, email:
Martha.Barillas@nrc.gov; or Bruce Lin,
Office of Nuclear Regulatory Research,
telephone: 301–415–2446; email:
Bruce.Lin@nrc.gov. Both are staff of the
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
INFORMATION CONTACT
Executive Summary
A. Need for the Regulatory Action
The purpose of this regulatory action
is to incorporate by reference into the
NRC’s regulations the latest revisions of
three regulatory guides (RGs). This
regulatory action is also incorporating
by reference, NUREG–2228, ‘‘Weld
Residual Stress Finite Element Analysis
Validation: Part II—Proposed Validation
Procedure,’’ that is associated with a
condition in one of the regulatory
guides. The three RGs identify new,
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revised, and reaffirmed code cases
published by the American Society of
Mechanical Engineers (ASME), which
the NRC has determined are acceptable
for use as voluntary alternatives to
compliance with certain provisions of
the ASME Boiler and Pressure Vessel
Code (BPV Code) and the ASME Code
for Operation and Maintenance of
Nuclear Power Plants, Division 1, OM
Code: Section IST (OM Code), currently
incorporated by reference into the
NRC’s regulations.
B. Major Provisions
The three RGs that the NRC is
incorporating by reference are RG 1.84,
‘‘Design, Fabrication, and Materials
Code Case Acceptability, ASME Section
III,’’ Revision 39; RG 1.147, ‘‘Inservice
Inspection Code Case Acceptability,
ASME Section XI, Division 1,’’ Revision
20; and RG 1.192, ‘‘Operation and
Maintenance [OM] Code Case
Acceptability, ASME OM Code,’’
Revision 4. The NRC is also
incorporating by reference NUREG–
2228, which provides the procedure for
validating the weld residual stress
analysis methodology associated with
ASME Code Case N–847. This final rule
allows nuclear power plant licensees
and applicants for construction permits,
operating licenses, combined licenses,
standard design certifications, standard
design approvals, and manufacturing
licenses to use the code cases newly
listed in these revised RGs as voluntary
alternatives to engineering standards for
the construction, inservice inspections,
and inservice testing of nuclear power
plant components. In this document, the
11935
NRC also notifies the public of the
availability of RG 1.193, ‘‘ASME Code
Cases Not Approved for Use,’’ Revision
7. This document lists code cases that
the NRC has not approved for generic
use and is not incorporated by reference
into the NRC’s regulations.
The NRC prepared a regulatory
analysis to determine the expected
quantitative costs and benefits of this
final rule, as well as qualitative factors
to be considered in the NRC’s
rulemaking decision. The analysis
concluded that this rule results in net
savings to the industry and the NRC. As
shown in Table 1, the estimated total
net benefits relative to the regulatory
baseline range from approximately
$5.86 million (7-percent net present
value) to $6.67 million (3-percent net
present value).
TABLE 1—COST BENEFIT SUMMARY
Total averted costs
(costs)
Attribute
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Undiscounted
7% Net
present value
3% Net
present value
Industry Implementation ..............................................................................................................
Industry Operation .......................................................................................................................
$0
4,920,000
$0
3,920,000
$0
4,450,000
Total Industry Costs .............................................................................................................
NRC Implementation ...................................................................................................................
NRC Operation ............................................................................................................................
4,920,000
0
2,460,000
3,920,000
0
1,940,000
4,450,000
0
2,220,000
Total NRC Costs ..................................................................................................................
2,460,000
1,940,000
2,220,000
Net .................................................................................................................................
7,380,000
5,860,000
6,670,000
The regulatory analysis also
considered the following qualitative
considerations: (1) Flexibility and
decreased uncertainty for licensees
when making modifications or
preparing to perform inservice
inspection or inservice testing; (2)
consistency with the provisions of the
National Technology Transfer and
Advancement Act of 1995, which
encourages Federal regulatory agencies
to consider adopting voluntary
consensus standards as an alternative to
de novo agency development of
standards affecting an industry; (3)
consistency with the NRC’s policy of
evaluating the latest versions of
consensus standards in terms of their
suitability for endorsement by
regulations and regulatory guides; and
(4) consistency with the NRC’s goal to
harmonize with international standards
to improve regulatory efficiency for both
the NRC and international standards
groups.
The regulatory analysis concludes
that this final rule should be adopted
because it is justified when integrating
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the cost-beneficial quantitative results
and the positive and supporting
nonquantitative considerations in the
decision. For more information, please
see the final regulatory analysis as
indicated in Section XVI, ‘‘Availability
of Documents,’’ of this document.
Table of Contents
I. Background
II. Discussion
III. Opportunities for Public Participation
IV. Public Comment Analysis
V. Section-by-Section Analysis
VI. Regulatory Flexibility Certification
VII. Regulatory Analysis
VIII. Backfitting and Issue Finality
IX. Plain Writing
X. Environmental Assessment and Final
Finding of No Significant Environmental
Impact
XI. Paperwork Reduction Act
XII. Congressional Review Act
XIII. Voluntary Consensus Standards
XIV. Incorporation by ReferenceReasonable Availability to Interested
Parties
XV. Availability of Guidance
XVI. Availability of Documents
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I. Background
The ASME develops and publishes
the ASME BPV Code, which contains
requirements for the design,
construction, and inservice inspection
examination of nuclear power plant
components, and the ASME OM Code,1
which contains requirements for
inservice testing of nuclear power plant
components. In response to BPV and
OM Code user requests, the ASME
develops code cases that provide
voluntary alternatives to BPV and OM
Code requirements under special
circumstances.
The NRC approves the ASME BPV
and OM Codes in § 50.55a, ‘‘Codes and
standards,’’ of title 10 of the Code of
Federal Regulations (10 CFR) through
the process of incorporation by
reference. As such, each provision of the
ASME Codes incorporated by reference
into and mandated by § 50.55a
1 The editions and addenda of the ASME Code for
Operation and Maintenance of Nuclear Power
Plants have had different titles from 2005 to 2017
and are referred to as the ‘‘OM Code’’ collectively
in this rule.
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Federal Register / Vol. 87, No. 42 / Thursday, March 3, 2022 / Rules and Regulations
constitutes a legally-binding NRC
requirement imposed by rule. As noted
previously, the ASME code cases, for
the most part, represent alternative
approaches for complying with
provisions of the ASME BPV and OM
Codes. Accordingly, the NRC
periodically amends § 50.55a to
incorporate by reference the NRC’s RGs
listing approved ASME code cases that
may be used as voluntary alternatives to
the BPV and OM Codes.2
This final rule is the latest in a series
of rules that incorporate by reference
new versions of several RGs identifying
new, revised, and reaffirmed,3 and
unconditionally or conditionally
acceptable ASME code cases that the
NRC approves for use. In developing
these RGs, the NRC reviews the ASME
BPV and OM code cases, determines the
acceptability of each code case, and
publishes its findings in the RGs. The
RGs are revised periodically as new
code cases are published by the ASME.
The NRC incorporates by reference the
RGs listing acceptable and conditionally
acceptable ASME code cases into
§ 50.55a. The NRC published a final rule
dated March 16, 2020, that incorporated
by reference into § 50.55a the most
recent versions of the RGs, which are
RG 1.84, ‘‘Design, Fabrication, and
Materials Code Case Acceptability,
ASME Section III,’’ Revision 38; RG
1.147, ‘‘Inservice Inspection Code Case
Acceptability, ASME Section XI,
Division 1,’’ Revision 19; and RG 1.192,
‘‘Operation and Maintenance Code Case
Acceptability, ASME OM Code,’’
Revision 3.
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II. Discussion
This final rule incorporates by
reference NUREG–2228 and the latest
revisions of the NRC’s RGs that list the
ASME BPV and OM code cases that the
NRC finds to be acceptable, or
acceptable with NRC-specified
conditions (‘‘conditionally acceptable’’).
Regulatory Guide 1.84, Revision 39,
supersedes the incorporation by
reference of Revision 38; RG 1.147,
Revision 20, supersedes the
incorporation by reference of Revision
2 See Federal Register final rule, ‘‘Incorporation
by Reference of ASME BPV and OM Code Cases’’
(68 FR 40469; July 8, 2003).
3 Code Cases are categorized by the ASME as one
of three types: New, revised, or reaffirmed. A new
Code Case provides for a new alternative to specific
the ASME Code provisions or addresses a new
need. The ASME defines a revised Code Case to be
a revision (modification) to an existing Code Case
to address, for example, technological
advancements in examination techniques or to
address NRC conditions imposed in one of the RGs
that have been incorporated by reference into
§ 50.55a. The ASME defines ‘‘reaffirmed’’ as an OM
Code Case that does not have any change to
technical content, but includes editorial changes.
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19; and RG 1.192, Revision 4,
supersedes the incorporation by
reference of Revision 3.
The ASME code cases that are the
subject of this final rule are the new and
revised Section III and Section XI code
cases as listed in Supplements 0
through 7 to the 2015 Edition of the
ASME BPV Code, Supplements 0
through 7 to the 2017 Edition of the
ASME BPV Code, Supplements 0 and 1
to the 2019 Edition of the ASME BPV
Code, and the OM code cases listed in
the 2020 Edition of the ASME OM Code
and on the ASME Codes & Standards
(C&S) Connect website.4
The latest editions and addenda of the
ASME BPV and OM Codes that the NRC
has approved for use are referenced in
§ 50.55a. The ASME also publishes code
cases that provide alternatives to
existing Code requirements that the
ASME developed and approved. This
final rule incorporates by reference the
most recent revisions of RGs 1.84, 1.147,
and 1.192, which allow nuclear power
plant licensees, and applicants for
combined licenses, standard design
certifications, standard design
approvals, and manufacturing licenses
under the regulations that govern
license certifications, to use the code
cases listed in these RGs as suitable
alternatives to the ASME BPV and OM
Codes for the construction, inservice
inspections, and inservice testing of
nuclear power plant components.
Because the NRC is requiring the use of
NUREG–2228 within a condition on
Code Case N–847, the NRC is also
incorporating by reference NUREG–
2228. The ASME publishes the OM
Code Cases and lists the code cases in
the ASME OM Code edition and on the
ASME C&S Connect website. In
contrast, the ASME publishes BPV code
cases in a separate document and at a
different time than the ASME BPV code
editions. This final rule identifies the
code cases by the edition of the ASME
BPV Code or ASME OM Code under
which they were published by the
ASME.
The following general guidance
applies to the use of the ASME code
cases approved in the latest versions of
the RGs that are incorporated by
reference into § 50.55a as part of this
final rule. Specifically, the use of the
code cases listed in the latest versions
4 The ASME included code cases with the
published editions and addenda of the OM Code
through the 2017 Edition. Starting with the 2020
Edition, code cases were not published with the
OM Code; an applicability index for ASME OM
code cases was published. Code cases are available
on the ASME website under the ‘‘O&M CASES’’ tab
in the left-hand column at https://go.asme.org/
OMcommittee.
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of RGs 1.84, 1.147, and 1.192 are
acceptable with the specified conditions
when implementing the editions and
addenda of the ASME BPV and OM
Codes incorporated by reference in
§ 50.55a.
The approval of a code case in the
NRC’s RGs constitutes acceptance of its
technical position for applications that
are not precluded by regulatory or other
requirements or by the
recommendations in these RGs. The
applicant or licensee is responsible for
ensuring that use of the code case does
not conflict with regulatory
requirements or licensee commitments.
The code cases listed in the RGs are
acceptable for use within the limits
specified in the code cases. If the RG
states an NRC condition on the use of
a code case, then the NRC condition
supplements and does not supersede
any condition(s) specified in the code
case, unless otherwise stated in the NRC
condition.
The ASME code cases may be revised
for many reasons (e.g., to incorporate
operational examination and testing
experience and to update material
requirements based on research results).
On occasion, an inaccuracy in an
equation is discovered or an
examination, as practiced, is found not
to be adequate to detect a newly
discovered degradation mechanism.
Therefore, when an applicant or a
licensee initially implements a code
case, § 50.55a requires that the applicant
or the licensee implement the most
recent version of that code case, as
listed in the RGs incorporated by
reference. Code cases superseded by
revision are no longer acceptable for
new applications unless otherwise
indicated.
Section III of the ASME BPV Code
applies to new construction (i.e., the
edition and addenda to be used in the
construction of a plant are selected
based on the date of the construction
permit and are not changed thereafter,
except voluntarily by the applicant or
the licensee). Hence, if a Section III code
case is implemented by an applicant or
a licensee and a later version of the code
case is incorporated by reference into
§ 50.55a and listed in the RG, the
applicant or licensee may use either
version of the code case (subject,
however, to whatever change
requirements apply to its licensing basis
(e.g., § 50.59)).
A licensee’s inservice inspection and
inservice testing programs must be
updated every 10 years to the latest
edition and addenda of the ASME BPV
Code, Section XI, and the OM Code,
respectively, that were incorporated by
reference into § 50.55a and in effect 18
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months prior to the start of the next
inspection and testing interval.
Licensees that were using a code case
prior to the effective date of its revision
may continue to use the previous
version for the remainder of the 120month inservice inspection or inservice
testing interval. This relieves licensees
of the burden of having to update their
inservice inspection or inservice testing
program each time a code case is revised
by the ASME and approved for use by
the NRC. Code cases apply to specific
editions and addenda, and code cases
may be revised if they are no longer
accurate or adequate, so licensees
choosing to continue using a code case
during the subsequent inservice
inspection or inservice testing interval
must implement the latest version
incorporated by reference into § 50.55a
and listed in the RGs.
The ASME may annul code cases that
are no longer required, are determined
to be inaccurate or inadequate, or have
been incorporated into the BPV or OM
Codes. A code case may be revised, for
example, to incorporate user experience.
The older or superseded version of the
code case cannot be applied by the
licensee or applicant unless it was
applied prior to being annulled or
superseded.
If an applicant or a licensee applied a code
case before it was listed as superseded, the
applicant or the licensee may continue to use
the code case until the applicant or the
licensee updates its construction Code of
Record (in the case of an applicant, updates
its application) or until the licensee’s 120month inservice inspection or inservice
testing update interval expires, after which
the continued use of the code case is
prohibited unless NRC authorization is given
11937
under § 50.55a(z). If a code case is
incorporated by reference into § 50.55a and
later a revised version is issued by the ASME
because experience has shown that the
design analysis, construction method,
examination method, or testing method is
inadequate, the NRC will amend § 50.55a and
the relevant RG to remove the approval of the
superseded code case. Applicants and
licensees should not begin to implement
such superseded code cases in advance of the
rulemaking.
A. ASME Code Cases Approved for
Unconditional Use
The code cases discussed in Table I
are new, revised, or reaffirmed code
cases in which the NRC approves for
use without conditions. The table
identifies the regulatory guide listing
the applicable code case that the NRC
approves for use.
TABLE I—ACCEPTABLE CODE CASES
Published with
supplement
Code Case No.
Title
Boiler and Pressure Vessel Code Section III
(Addressed in RG 1.84, Table 1)
N–249–17 ....................
0 (2019 Edition) .............
N–539–1 ......................
N–692–1 ......................
N–721–1 ......................
N–801–3 ......................
N–822–4 ......................
N–855 ..........................
N–856 ..........................
0
6
5
1
7
2
2
N–859 ..........................
5 (2015 Edition) .............
N–863–1 ......................
1 (2017 Edition) .............
N–866 ..........................
N–870–1 ......................
0 (2017 Edition) .............
4 (2017 Edition) .............
N–879 ..........................
1 (2017 Edition) .............
N–884 ..........................
0 (2019 Edition) .............
N–887 ..........................
6 (with errata issued in
3/19E).
0 (2019 Edition) .............
N–891 ..........................
(2017
(2015
(2017
(2017
(2015
(2015
(2015
Edition)
Edition)
Edition)
Edition)
Edition)
Edition)
Edition)
.............
.............
.............
.............
.............
.............
.............
Additional Materials for Subsection NF, Classes 1, 2, 3, and MC Supports Fabricated without Welding, Section III, Division 1.
UNS N08367 in Class 2 and 3 Valves, Section III, Division 1.
Use of Standard Welding Procedures, Section III, Division 1.
Alternative Rules for Linear Piping Supports, Section III, Division 1.
Rules for Repair of N-Stamped Class 1, 2, and 3 Components, Section III, Division 1.
Application of the ASME Certification Mark, Section III, Divisions 1, 2, 3, and 5.
SB–148 C95800 Valves for Class 3 Construction, Section III, Division 1.
SA–494 Grade CW–12MW (UNS N30002) Nickel Alloy Castings for Construction of NPS
21⁄2 and Smaller Flanged Valves for Class 3 Construction, Section III, Division 1.
Construction of ASME B16.9 Wrought Buttwelding Fittings and ASME B16.11 Forged Fittings Made From SB–366 UNS N04400 Material for Section III, Class 3 Construction,
Section III, Division 1.
Post Weld Heat Treatment (PWHT) of Valve Seal Welds for P4 and P5A Materials, Section
III, Division 1.
Alternative Materials for Construction of Section III, Class 2 Vessels, Section III, Division 1.
Rules for the Elimination of External Surface Defects on Class 1, 2, and 3 Piping, Pumps,
or Valves After Component Stamping and Prior to Completion of the N–3 Data Report,
Section III, Division 1.
Use of Micro-Alloyed Carbon Steel Bar in Patented Mechanical Joints and Fittings, Classes
1, 2, and 3, Section III, Division 1.
Procedure to Determine Strain Rate for Use with the Environmental Fatigue Design Curve
Method and the Environmental Fatigue Correction Factor, Fen, Method as Part of an Environmental Fatigue Evaluation for Components Analyzed per the NB–3200 Rules, Section III, Division 1.
Alternatives to the Requirements of NB–4424.2(a), Figure NB–4250–2, and Figure NB–
4250–3, Section III, Division 1.
Alternative Requirements to Appendix XXVI, XXVI–2400, XXVI–4130, and XXVI–4131 for
Inspection and Repair of Indentations for Polyethylene Pipe and Piping Components,
Section III, Division 1.
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Boiler and Pressure Vessel Code Section XI
(Addressed in RG 1.147, Table 1)
N–561–3 ......................
0 (2019 Edition) .............
N–638–10 ....................
1 (2019 Edition) .............
N–653–2 ......................
2 (2015 Edition) .............
N–702–1 ......................
1 (2019 Edition) .............
N–716–2 ......................
0 (2017 Edition) .............
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Alternative Requirements for Wall Thickness Restoration of Class 2 and High Energy Class
3 Carbon Steel Piping, Section XI, Division 1.
Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper
Bead Technique, Section XI, Division 1.
Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping Welds,
Section XI, Division 1.
Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds, Section XI, Division 1.
Alternative Piping Classification and Examination Requirements, Section XI, Division 1.
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TABLE I—ACCEPTABLE CODE CASES—Continued
Code Case No.
Published with
supplement
Title
N–768 ..........................
0 (2019 Edition) .............
N–786–3 ......................
1 (2017 Edition) .............
N–789–3 ......................
1 (2017 Edition) .............
N–809 ..........................
2 (2015 Edition) .............
N–845–1 ......................
N–848–1 ......................
N–851 ..........................
6 (2015 Edition) .............
0 (2017 Edition) .............
0 (2015 Edition) .............
N–858 ..........................
2 (2017 Edition) .............
N–865 ..........................
2 (2017 Edition) .............
N–867 ..........................
N–873 ..........................
N–874 ..........................
0 (2017 Edition) .............
1 (2017 Edition) .............
7 (2017 Edition) .............
N–877 ..........................
2 (2017 Edition) .............
N–882 ..........................
6 (2017 Edition) .............
N–885 ..........................
0 (2019 Edition) .............
N–892 ..........................
0 (2019 Edition) .............
Alternative Volumetric Coverage Requirements for Ultrasonic Examination of Class 1 and 2
Pressure Vessel Weld Joints Greater Than 2 in. (50 mm) in Thickness, Section XI, Division 1.
Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate Energy
Carbon Steel Piping, Section XI, Division 1.
Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section XI, Division 1.
Reference Fatigue Crack Growth Rate Curves for Austenitic Stainless Steels in Pressurized Reactor Water Environments, Section XI, Division 1.
Qualification Requirements for Bolts and Studs, Section XI, Division 1.
Alternative Characterization Rules for Quasi-Laminar Flaws, Section XI, Division 1.
Alternate Method for Establishing the Reference Temperature for Pressure Retaining Materials, Section XI, Division 1.
Alternative Volumetric Coverage Requirements for Ultrasonic Examination of Class 1 Nozzle-to-Vessel Welds, Section XI, Division 1.
Alternative Requirements for Pad Reinforcement of Class 2 and 3 Atmospheric Storage
Tanks, Section XI, Division 1.
Clarification of NDE Practical Examination Requirements, Section XI, Division 1.
Examination Requirements for the Core Makeup Tanks, Section XI, Division 1.
Temporary Acceptance of Leakage Through Brazed Joints of Class 3 Copper, CopperNickel, and Nickel-Copper Moderate Energy Piping, Section XI, Division 1.
Alternative Characterization Rules for Multiple Subsurface Radially Oriented Planar Flaws,
Section XI, Division 1.
Alternative Requirements for Attaching Nonstructural Electrical Connections to Class 2 and
3 Components, Section XI, Division 1.
Alternative Requirements for Table IWB–2500–1, Examination Category B–N–1, Interior of
Reactor Vessel, Category B–N–2, Welded Core Support Structures and Interior Attachments to Reactor Vessels, Category B–N–3, Removable Core Support Structures, Section XI, Division 1.
Alternative Requirement for Form OAR–1, Owner’s Activity Report, Completion Time, Section XI, Division 1.
Operation and Maintenance Code
(Addressed in RG 1.192, Table 1)
OMN–13, Revision 3 ...
2020 Edition ...................
OMN–15, Revision 3 ...
2020 Edition ...................
OMN–17, Revision 1 ...
OMN–18 5 ....................
OMN–22 .......................
OMN–23 .......................
OMN–24 .......................
2020
2020
2020
2020
2020
OMN–25 .......................
OMN–26 .......................
2020 Edition ...................
2020 Edition ...................
OMN–27 .......................
2020 Edition ...................
Edition
Edition
Edition
Edition
Edition
...................
...................
...................
...................
...................
Performance-Based Requirements for Extending Snubber Inservice Visual Examination Interval at LWR Power Plants.
Performance-Based Requirements for Extending the Snubber Operational Readiness Testing Interval at LWR Power Plants.
Alternative Requirements for Testing ASME Class 1 Pressure Relief/Safety Valves.
Alternate Testing Requirements for Pumps Tested Quarterly Within ±20% of Design Flow.
Smooth Running Pumps.
Alternative Requirements for Testing Pressure Isolation Valves.
Alternative Requirements for Testing ASME Class 2 and 3 Pressure Relief Valves (For Relief Valves in a Group of One).
Alternative Requirements for Testing Appendix I Pressure Relief Valves.
Alternate Risk-Informed and Margin Based Rules for Inservice Testing of Motor Operated
Valves.
Alternative Requirements for Testing Category A Valves (Non-PIV/CIV)
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B. ASME Code Cases Approved for Use
With Conditions
5 As a result of a public comment, the NRC agreed
that the condition to require the slightly more
restrictive upper-end values of the acceptable
ranges for flow and differential pressure are not
necessary to provide reasonable assurance that the
implementation of Code Case OMN–18 will
demonstrate the acceptable performance of pumps
within the scope of the ASME OM Code. Therefore,
the NRC deleted the condition proposed and moved
OMN–18 to Table I.
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The NRC determined that certain code
cases, as issued by the ASME, are
generally acceptable for use, but that the
alternative requirements specified in
those code cases must be supplemented
in order to provide an acceptable level
of quality and safety. Accordingly, the
NRC imposes conditions on the use of
these code cases to modify, limit, or
clarify their requirements. The
conditions specify, for each applicable
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code case, the additional activities that
must be performed, the limits on the
activities specified in the code case,
and/or the supplemental information
needed to provide clarity. These ASME
code cases, listed in Table II below, are
included in Table 2 of RG 1.84, RG
1.147, and RG 1.192. This section
provides the NRC’s evaluation of the
code cases and the reasons for the NRC’s
conditions. Notations indicate the
conditions duplicated from previous
versions of the RG.
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11939
TABLE II—CONDITIONALLY ACCEPTABLE CODE CASES
Published with
supplement
Code Case No.
Title
Boiler and Pressure Vessel Code Section III
(Addressed in RG 1.84, Table 2)
N–71–20 ......................
6 (2015 Edition) .............
N–155–3 ......................
N–755–4 ......................
N–779 ..........................
N–852 ..........................
N–883 ..........................
5
1
8
0
5
N–886 ..........................
6 (2017 Edition) .............
(2015
(2017
(2007
(2015
(2017
Edition) .............
Edition) .............
Edition) 6 ...........
Edition) .............
Edition) .............
Additional Materials for Subsection NF, Class 1, 2, 3, and MC Supports Fabricated by
Welding, Section III, Division 1.
Fiberglass Reinforced Thermosetting Resin Pipe, Section III, Division 1.
Use of Polyethylene (PE) Class 3 Plastic Pipe, Section III, Division 1.
Alternative Rules for Simplified Elastic-Plastic Analysis Class 1, Section III, Division 1.
Application of the ASME NPT Stamp, Section III, Divisions 1, 2, 3, and 5.
Construction of Items Prior to the Establishment of a Section III, Division 1 Owner, Section
III, Division 1.
Use of Polyethylene Pipe for Class 3, Section III, Division 1.
Boiler and Pressure Vessel Code Section XI
(Addressed in RG 1.147, Table 2)
N–513–5 ......................
6 (2017 Edition) .............
N–516–5 ......................
N–597–3 ......................
N–705–1 ......................
6 (2015 Edition) .............
5 (2013 Edition) .............
2 (2017 Edition) .............
N–766–3 ......................
2 (2017 Edition) .............
N–778 ..........................
0 (2010 Edition) .............
N–831–1 ......................
7 (2017 Edition) .............
N–847 ..........................
0 (2017 Edition) .............
N–864 ..........................
N–869 ..........................
2 (2017 Edition) .............
6 (2017 Edition) .............
N–876 ..........................
2 (2017 Edition) .............
N–878 ..........................
N–880 ..........................
1 (2017 Edition) .............
2 (2017 Edition) .............
N–889 ..........................
7 (2017 Edition) .............
N–890 ..........................
0 (2019 Edition) .............
Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3
Piping and Gate Valves, Section XI, Division 1.
Underwater Welding, Section XI, Division 1.
Evaluation of Pipe Wall Thinning, Section XI.
Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2
or 3 Vessels and Tanks, Section XI, Division 1.
Nickel Alloy Reactor Coolant Inlay and Onlay for Mitigation of PWR Full Penetration Circumferential Nickel Alloy Dissimilar Metal Welds in Class 1 Items, Section XI, Division 1.
Alternative Requirements for Preparation and Submittal of Inservice Inspection Plans,
Schedules, and Preservice and Inservice Inspection Summary Reports, Section XI, Division 1.
Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe, Section XI, Division 1.
Partial Excavation and Deposition of Weld Metal for Mitigation of Class 1 Items, Section XI,
Division 1.
Reactor Vessel Threads in Flange Examinations, Section XI, Division 1.
Evaluation Criteria for Temporary Acceptance of Flaws in Class 2 or 3 Piping, Section XI,
Division 1.
Austenitic Stainless Steel Cladding and Nickel Base Cladding Using Ambient Temperature
Automatic or Machine Dry Underwater Laser Beam Welding (ULBW) Temper Bead
Technique, Section XI, Division 1.
Alternative to QA Program Requirements of IWA–4142, Section XI, Division 1.
Alternative to Procurement Requirements of IWA–4143 for Small Nonstandard Welded Fittings, Section XI, Division 1.
Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless
Steel in Light-Water Reactor Environments, Section XI, Division 1.
Materials Exempted From G–2110(b) Requirement, Section XI, Division 1.
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Operation and Maintenance Code
(Addressed in RG 1.192, Table 2)
OMN–1, Revision 2 .....
2020 Edition ...................
OMN–3 .........................
2020 Edition ...................
OMN–4 .........................
2020 Edition ...................
OMN–9 .........................
OMN–12 .......................
2020 Edition ...................
2020 Edition ...................
OMN–19 .......................
OMN–20 .......................
2020 Edition ...................
2020 Edition ...................
Alternative Rules for Preservice and Inservice Testing of Active Electric Motor-Operated
Valve Assemblies in Light-Water Reactor Power Plants.
Requirements for Safety Significance Categorization of Components Using Risk Insights for
Inservice Testing of LWR Power Plants.
Requirements for Risk Insights for Inservice Testing of Check Valves at LWR Power
Plants.
Use of a Pump Curve for Testing.
Alternative Requirements for Inservice Testing Using Risk Insights for Pneumatically and
Hydraulically Operated Valve Assemblies in Light-Water Reactor Power Plants (OMCode 1998, Subsection ISTC).
Alternative Upper Limit for the Comprehensive Pump Test.
Inservice Test Frequency.
1. ASME BPV Code, Section III Code
Cases (RG 1.84)
Code Case N–71–20 [Supplement 6,
2015 Edition]
6 Correcting editorial error from proposed rule to
final rule to state correct supplement 8.
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Type: Revised.
Title: Additional Materials for
Subsection NF, Class 1, 2, 3, and MC
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Supports Fabricated by Welding,
Section III, Division 1.
The conditions on Code Case N–71–
20 are the same as the conditions on N–
71–19 that were approved by the NRC
in Revision 38 of RG 1.84. When the
ASME revised N–71, the code case was
not modified in a way that would make
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it possible for the NRC to remove the
conditions. Therefore, the conditions
are retained in Revision 39 of RG 1.84.
Code Case N–155–3 [Supplement 5,
2015 Edition]
Type: Revised.
Title: Fiberglass Reinforced
Thermosetting Resin Pipe, Section III,
Division 1.
The conditions on Code Case N–155–
3 are the same as the conditions on N–
155–2 that were approved by the NRC
in Revision 38 of RG 1.84. When the
ASME revised N–155–2, the code case
was not modified in a way that would
make it possible for the NRC to remove
the conditions. Therefore, the
conditions are retained in Revision 39 of
RG 1.84.
Code Case N–852 [Supplement 0, 2015
Edition]
Code Case N–883 [Supplement 5, 2017
Edition]
Type: New.
Title: Construction of Items Prior to
the Establishment of a Section III,
Division 1 Owner, Section III, Division
1.
This code case allows certificate
holders to construct all items prior to
the establishment of an Owner. Code
Case N–883 was developed to address
international stakeholders and identify
the ASME as a global standard
development organization. The NRC’s
main concern is that without the
designation of an Owner, the NRC
would not be able to provide regulatory
oversight of the ASME certificate holder
manufacturing the items, which is not
consistent with appendix B to 10 CFR
part 50 and the requirements in
§ 50.55(a) for a basic component. During
discussions with the ASME staff on this
code case, it was determined that the
NRC would condition this code case
based on regulatory oversight, as would
other regulatory bodies depending on
each countries’ specific regulations.
This is evident as this code case
specifies that the ‘‘the items have been
constructed by [ASME] Certificate
Holders who are specifically authorized
by the Regulatory Authority having
jurisdiction over the Owner’s facility to
construct items using this Case.’’ The
condition, ‘‘This Code Case may be used
for the construction of items by a holder
of a construction permit, operating
license, or combined license under 10
CFR part 50 or part 52,’’ provides this
specific regulatory authorization thereby
ensuring the appropriate regulatory
oversight. As a result of public
comment, the NRC clarified the
condition on the code case as follows:
‘‘This Code Case may only be used for
the construction of items by a holder of
a construction permit, operating license,
or combined license under 10 CFR part
50 or 10 CFR part 52. This Code Case
may not be used by a holder of a
manufacturing license or standard
design approval or by a design
certification applicant.’’
Type: New.
Title: Application of the ASME NPT
Stamp, Section III, Divisions 1, 2, 3, and
5.
The NRC approved this code case
with a condition in a § 50.55a
rulemaking issued in 2017 (82 FR
Code Case N–886 [Supplement 6, 2017
Edition]
Type: New.
Title: Use of Polyethylene Pipe for
Class 3, Section III, Division 1.
This code case is applicable for the
use of polyethylene pipe in Section III,
Code Case N–755–4 [Supplement 1,
2017 Edition]
Type: Revised.
Title: Use of Polyethylene (PE) Class
3 Plastic Pipe, Section III, Division 1.
This code case is applicable only to
butt fusion joints and the content was
incorporated into Mandatory Appendix
XXVI in the 2015 Edition of Section III
of the ASME Code. The relevant
provisions of Code Case N–755–4 are
the same as those in Mandatory
Appendix XXVI. Therefore, the NRC is
applying the same conditions to Code
Case N–755–4. The NRC has determined
that these conditions are necessary to
ensure structural integrity of the
polyethylene piping and fusion joints
when the polyethylene piping is used in
Class 3 safety-related applications.
Code Case N–779 [Supplement 8, 2007
Edition]
Type: New.
Title: Alternative Rules for Simplified
Elastic-Plastic Analysis Class 1, Section
III, Division 1.
The NRC finds the code case
satisfactory and technically acceptable
for use only with code editions Summer
1979 and later. This code case, as
written, is not acceptable for use with
editions of Section III earlier than the
Summer 1979 Edition, which included
the term Delta T1 in NB–3600 Equation
10, because the code case is based on
equations used in the Summer 1979
Edition and later editions of the Code.
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32934; July 18, 2017), and the
supplement was not modified in a way
that would make it possible for the NRC
to remove the condition. Therefore, the
condition is retained in Revision 39 of
RG 1.84.
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Class 3, Division 1 above ground
applications. This code case refers to
Mandatory Appendix XXVI of Section
III of the ASME Code. The 2015 Edition
of Appendix XXVI contains
requirements for butt fusion joints for
buried piping. The 2017 Edition of
Appendix XXVI contains requirements
for butt fusion and electrofusion joints
for buried piping. Therefore, all the
conditions as noted in Section III of the
2015–2017 Code Edition rule related to
buried piping Mandatory Appendix
XXVI apply to this code case. The same
conditions as buried piping also apply
to above ground application. One
additional condition is needed for above
ground applications related to fire
protection. A condition on fire
protection is needed because
polyethylene material is combustible
and above ground uses are more
susceptible to fire hazards.
The NRC agreed with the public
comments to remove conditions 1, 2,
and 3 because the three conditions are
the same as those for Section III,
Mandatory Appendix XXVI, which was
conditionally accepted by the NRC in
§ 50.55a. It is redundant to specify these
conditions to Code Case N–886.
As a result of public comment, the
NRC clarified condition 4 to state that
for aboveground applications, licensees
must ensure that plant fire protection
program addresses any high-density
polyethylene (HDPE) consistent with
the requirements of 10 CFR 50.48. The
licensee must identify the specific
program to satisfy this objective such as
the plant fire protection program.
Therefore, the condition is retained in
Revision 39 of RG 1.84.
The NRC agreed with the public
comment to remove condition 5 because
the requirement that carbon black
distribution in HDPE pipe to be
homogenous to prevent windows and
delamination is a pipe manufacturing
process issue. The staff determined that
the requirements in Mandatory
Appendix XXVI–2231(b) adequately
address this issue. Code Case N–886 is
only for design, and all materials must
meet the requirements of Appendix
XXVI.
2. ASME BPV Code, Section XI Code
Cases (RG 1.147)
Code Case N–513–5 [Supplement 6,
2017 Edition]
Type: Revised.
Title: Evaluation Criteria for
Temporary Acceptance of Flaws in
Moderate Energy Class 2 or 3 Piping and
Gate Valves, Section XI, Division 1.
Code Case N–513–5 contains
provisions to permit temporary
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acceptance of flaws, in moderate energy
Class 2 or 3 piping, including elbows,
pipe bends, reducers, expanders, branch
tees, and gate valves without performing
a repair/replacement activity for a
limited period. The code case contains
provisions regarding the scope, flaw
characterization, periodic leakage
monitoring, flaw evaluation, and
augmented examinations. The NRC
finds that the provisions of N–513–5 are
acceptable except that the augmented
examination provisions in Section 5 of
the code case require clarification.
When a licensee applies N–513–5 to
disposition a through-wall leak or wall
thinning in a piping system, Section 5
of the code case requires augmented
examinations for flaws and significant
flaws. The augmented examination
requirements in N–513–5 are the same
as in Code Case N–513–3.
In 2018, the NRC found an instance
where a licensee misinterpreted the
provisions in Section 5 of N–513–3 and
did not perform the required augmented
examinations to disposition a throughwall leak in a service water system pipe.
Other licensees have similarly
misinterpreted the augmented
examination provisions in Section 5 of
N–513–3. The NRC found that the issue
stems from the definition of the terms
‘‘flaw’’ and ‘‘significant flaw’’ in
Sections 5(b) and 5(c) of N–513–3,
respectively. The NRC, therefore,
imposes two conditions to define ‘‘flaw’’
and ‘‘significant flaw’’ as those terms are
used in Section 5 of N–513–5. Licensees
would be required to apply these
definitions to Section 5 when using the
code case.
The first condition defines a ‘‘flaw’’ as
a non-through-wall planar or nonplanar
flaw with a wall thickness less than 87.5
percent of the nominal wall thickness of
the pipe or the design minimum wall
thickness. The NRC notes that the pipe
wall thickness at the time of the plant
construction may deviate from the
nominal pipe wall thickness slightly as
part of manufacturing process. The
generally accepted deviation is 12.5
percent of the nominal pipe wall
thickness or the design minimum wall
thickness.
The second condition defines
‘‘significant flaw’’ as any pipe location
that does not satisfy the provisions of
Section 3 of N–513–5 or if any detected
flaw that has a depth greater than 75
percent of the pipe wall thickness. The
NRC staff notes that the criterion of the
75 percent wall thickness criterion
originates from the provisions of IWC/
IWD–3643 of the ASME Code, Section
XI, which prohibits a flaw that exceeds
75 percent of the pipe wall thickness to
remain in service. Under Section 5 of
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N–513–5, a planar flaw that exceeds 75
percent of the pipe wall thickness may
remain in service; however, the licensee
must perform an augmented
examination. The NRC agreed with the
public comment that Condition 2
needed clarification. As a result, the
NRC revised Condition No. 2 as follows:
‘‘For the purposes of section 5 of Code
Case N–513–5, the term ‘‘significant
flaw’’ means any flaw found during
augmented examinations performed per
Section 5 of N–513–5 that has a depth
greater than 75 percent of the pipe wall
thickness or that does not satisfy the
applicable requirements of the flaw
evaluation per Section 3 of N–513–5. If
a significant flaw as defined above is
present, then the licensee must perform
the additional augmented examination
specified in Section 5.’’
Code Case N–516–5 [Supplement 6,
2015 Edition]
Type: Revised.
Title: Underwater Welding, Section
XI, Division 1.
In the rulemaking for the 2009
Addenda through 2013 Editions of the
ASME Code (82 FR 32934; September
18, 2017), the NRC-specified conditions
that should be applied to Section XI,
Article IWA–4660 when performing
underwater welding on irradiated
materials. These conditions provide
guidance on what level of neutron
irradiation and/or helium content
would require review and approval by
the NRC because of the impact of
neutron fluence on weldability. These
conditions provide separate criteria for
three generic classes of material: Ferritic
material, austenitic material other than
P-No. 8 (e.g., nickel-based alloys) and
austenitic P-No. 8 material (e.g.,
stainless steel alloys). These conditions
are currently located in
§ 50.55a(b)(2)(xii)(A) and (B). The
conditions located in
§ 50.55a(b)(2)(xii)(A) and (B) are
identical to the conditions that were
imposed on Code Case N–516–4 that
were approved by the NRC in Revision
19 of RG 1.147. When the ASME revised
N–516, the code case was not modified
in a way that would make it possible for
the NRC to remove the conditions.
Therefore, the conditions are retained in
Revision 20 of RG 1.147 by stating the
provisions of § 50.55a(b)(2)(xii)(A) and
(B) must be met when applying this
code case.
Code Case N–597–3 [Supplement 5,
2013 Edition]
Type: Revised.
Title: Evaluation of Pipe Wall
Thinning, Section XI.
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11941
Based on public comments, the NRC
found that existing Condition 2(b)
references Figure–3622.1(a)(1), which
does not exist in Code Case N–597–3.
The NRC revised Condition 2(b) in the
final rule to reference Figure 3622–1 of
the code case.
Code Case N–705–1 [Supplement 2,
2017 Edition]
Type: Revised.
Title: Evaluation Criteria for
Temporary Acceptance of Degradation
in Moderate Energy Class 2 or 3 Vessels
and Tanks, Section XI, Division 1.
The condition on Code Case N–705–
1 is identical to the condition on N–705
that was approved by the NRC in
Revision 19 of RG 1.147. When the
ASME revised N–705, the code case was
not modified in a way that would make
it possible for the NRC to remove the
condition. Therefore, the condition is
retained in Revision 20 of RG 1.147.
Code Case N–766–3 [Supplement 2,
2017 Edition]
Type: Revised.
Title: Nickel Alloy Reactor Coolant
Inlay and Onlay for Mitigation of
Pressurized Water Reactor (PWR) Full
Penetration Circumferential Nickel
Alloy Dissimilar Metal Welds in Class 1
Items, Section XI, Division 1.
The conditions on Code Case N–766–
3 are identical to the conditions on N–
766–1 that were approved by the NRC
in Revision 19 of RG 1.147. When the
ASME revised N–766, the code case was
not modified in a way that would make
it possible for the NRC to remove the
conditions. Therefore, the conditions
are retained in Revision 20 of RG 1.147.
Code Case N–778 [Supplement 0, 2010
Edition]
Type: New.
Title: Alternative Requirements for
Preparation and Submittal of Inservice
Inspection Plans, Schedules, and
Preservice and Inservice Inspection
Summary Reports, Section XI, Division
1.
Code Case N–778 was originally listed
in Table 2 of Revision 18 of RG 1.147
with two conditions. As a result of
public comments, the NRC revised the
second condition on Code Case N–778
to be consistent with Code Case N–892
by increasing the time period for
submittal of the inservice inspection
summary report to 120 days following
the completion of each refueling outage.
Code Case N–831–1 [Supplement 7,
2017 Edition]
Type: Revised.
Title: Ultrasonic Examination in Lieu
of Radiography for Welds in Ferritic or
Austenitic Pipe, Section XI, Division 1.
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The condition on Code Case N–831–
1 is identical to the condition on N–831
that was approved by the NRC in
Revision 19 of RG 1.147. When ASME
revised N–831, the code case was not
modified in a way that would make it
possible for the NRC to remove the
condition. Therefore, the condition is
retained in Revision 20 of RG 1.147.
Code Case N–847 [Supplement 0, 2017
Edition]
Type: New.
Title: Partial Excavation and
Deposition of Weld Metal for Mitigation
of Class 1 Items, Section XI, Division 1.
The ASME Code Case N–847 provides
guidelines for a repair/mitigation
process for welds. The process,
excavation and weld repair (EWR),
removes susceptible material from the
outside diameter of the pipe, and
replaces it with more resistant weld
material. This technique allows for the
potential of two mitigation methods, the
use of more crack-resistant material and
the potential for compressive stresses on
the inside surface of the repaired/
mitigated weld to arrest or prevent
cracking. Finally, the excavation can be
done 360-degrees around the weld or
only for a partial arc of the weld.
The code case would allow for
application of this process to both BWR
and PWR designs. However, the EWR
process, as defined in this code case,
has certain challenges addressing the
cracking mechanisms in these operating
environments and materials. In
addition, the regulatory requirements or
guidelines related to the code case vary
depending on the design of the reactor.
For PWR designs, the inservice
inspection rules are provided by
§ 50.55a(g)(6)(ii)(F), which mandates the
implementation of a version of ASME
Code Case N–770–5. For BWR designs,
the inservice inspection guidelines are
provided by Generic Letter 88–01, ‘‘NRC
Position on Intergranular Stress
Corrosion Cracking (IGSCC) in BWR
Austenitic Stainless Steel Piping,’’ or
BWRVIP–75–A, ‘‘BWR Vessel and
Internals Project Technical Basis for
Revisions to Generic Letter 88–01
Inspection Schedules.’’ Therefore, the
NRC is imposing six conditions to
ensure the inservice inspection
frequency guidelines of the code case
are consistent with the previous
requirements and guidance, which are
based on the effectiveness of the overall
design of the repair/mitigation to
address the various cracking
mechanisms of these operating reactor
designs.
The first condition is a continuation
of the condition of
§ 50.55a(g)(6)(ii)(F)(16), which requires
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that a partial arc EWR, as described in
Inspection Item O of ASME Code Case
N–770–5, cannot be used without NRC
review and approval for PWR designs.
The NRC notes that the issues addressed
in the final rule incorporating by
reference the 2015 and 2017 Editions of
the ASME BPV Code and the 2015 and
2017 Editions of the ASME OM Code
remain applicable, and further apply to
BWR design application of a partial arc
EWR. These concerns are for the
effectiveness of the repair through a
weld residual stress calculation and
flaw growth analysis to confirm design
of the mitigation for the required
inspection interval, non-destructive
examination uncertainty analysis of the
as-found flaw remaining in the reactor
coolant pressure boundary, and the
potential for further crack initiation or
growth. The NRC requires, through the
first condition, that approval of the use
of this code case is only for the
application of the 360-degree EWR.
The second condition is related to
Figure 1A and Figure 1B of the code
case. The NRC has experience with
relief request submittals, where the
details associated with the configuration
of the prep area, where the defect is
being removed, have shown sharp
bottom edges and steep walls. This
geometry can result in welding issues,
which could result in unfused material,
leading to stress risers, which may
promote cracking. The NRC requires,
through the second condition, that the
intersection points at the interface
between EWR metal and existing base
metal must be rounded to minimize
stress concentration.
The third condition is related to
Section 2(d) of the code case, which
discusses the flaw evaluations required
for the design considerations of the
EWR. In recent testing conducted for the
NRC measurable stress corrosion
cracking (SCC) growth was detected past
the interface between the SCCsusceptible and less susceptible
material. It was demonstrated that the
crack can branch and propagate in a
direction normal to the original
direction along a SCC-susceptible path.
In the Alloy 52M deposited onto Alloy
182 specimens tested, this occurred in
the diluted region of the Alloy 52M
material as well as the weld metal. The
NRC requires, through the third
condition, that flaw analysis include the
potential for crack growth through the
dilution zone including crack
branching. As NRC-approved crack
growth rates are not available for all
material types (e.g., Alloy 690 weld
material), the alternative requirements
for development of crack growth rates
should be consistent with ASME
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Section XI Appendix C, ‘‘Flaw Growth
Rate Due to Stress Corrosion Cracking,’’
C–3220(a). As a result of public
comment, the NRC agrees this condition
should be updated to reference Section
2(d)(1), rather than 2(d)(2) as discussed
in the proposed rule (86 FR 7820,
February 2, 2021), for nickel-based
alloys. The NRC clarified the condition
to state the evaluation in Section 2(d)(1)
of the code case must include
evaluation of crack growth into the
Alloy 690 weld material, including the
dilution zones and allowing change in
flaw growth direction.
The fourth condition is related to
Section 2 of the code case. The NRC is
requiring the use of NUREG–2228,
because it provides a proven method for
validating the weld residual stress
analysis methodology. Because the NRC
requires the use of NUREG–2228 within
this condition on the requirements in
the code case, the NRC is incorporating
by reference NUREG–2228 into
§ 50.55a(a)(3)(iv).
The fifth condition is related to the
longer-term volumetric inspection
frequencies of Table 1, including notes
(1), (3), and (4). These notes provide the
BWR design inspection frequency of
various EWR types based on Generic
Letter 88–01 (1988) as supplemented by
Generic Letter 88–01, Supplement 1
(1992), ‘‘NRC Position on Intergranular
Stress Corrosion Cracking (IGSCC) in
BWR Austenitic Stainless Steel Piping,’’
or BWRVIP–75–A, ‘‘BWR Vessel and
Internals Project Technical Basis for
Revisions to Generic Letter 88–01
Inspection Schedules.’’ The NRC has
concluded that the inspection
requirements for EWRs for BWRs need
to be augmented.
The first volumetric examination
following application of BWR EWR–2A,
EWR–1B, and EWR–2B welds is
performed to verify effectiveness of the
repair/mitigation before the new weld
can be placed in a longer-term
volumetric inspection frequency. The
code case allows licensees the option of
performing this examination during the
first or second refueling outage after
installation. However, based on the
lower operating temperatures of a BWR
(approximately 546 °F to 558 °F), and
hence the potential slow crack growth
rate of the remaining flaw left in service,
the NRC has concluded that the
examination should occur during the
second refueling outage after the EWR
application to provide adequate time for
any potential measurable flaw growth to
occur or in the case of an EWR–2A, for
crack initiation and growth to occur.
The long-term volumetric inspections
for BWRs require modification because:
(a) For EWR–1A EWRs, the augmented
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inspection requirements are consistent
with the conditions of the inspection
frequencies of Code Case N–770–5.
These inspection frequency
requirements were previously
developed by the NRC based on the
capabilities of the EWR process to
address stress corrosion cracking while
providing significant credit for the use
of hydrogen water chemistry/noble
metal chemical addition controls; and
(b) for EWR–1B EWRs, the design that
would allow a crack to be left in service,
should not be allowed to go uninspected
for the remainder of plant life.
Therefore, the NRC requires the longterm volumetric inspection of these
welds at each 10-year inservice
inspection interval. The NRC notes that
this condition is consistent with the
NRC condition established in § 50.55a
for Inspection Item N–1 EWRs (EWR
that meets stress criteria; however, a
crack is present).
The sixth condition is related to Table
1, Note (1), and the option to use an
unspecified alternative to determine
examination frequencies and scope
expansion criteria. Note (1) specifies the
use of NRC Generic Letter 88–01 and
includes BWRVIP–75–A as an example
of an alternative. The NRC has
concluded that NRC Generic Letter 88–
01 (1988), as supplemented by Generic
Letter 88–01, Supplement 1 (1992), or
BWRVIP–75–A, are acceptable, subject
to the fifth condition, to determine
examination frequencies and scope
expansion criteria. However, Note (1)
would allow the use of other, unknown
alternatives and does not provide
criteria to ensure alternatives are
adequate for this purpose. Therefore, to
ensure that licensees use an adequate
standard to determine examination
frequencies and scope expansion
criteria, the sixth condition requires that
licensees must not use an alternative
other than those specified in Note (1).
Code Case N–864 [Supplement 2, 2017
Edition]
Type: New.
Title: Reactor Vessel Threads in
Flange Examinations, Section XI,
Division 1.
Code Case N–864 eliminates the
required ASME Code, Section XI
examination for the reactor vessel
threads-in-flange for all inservice
inspection intervals. The NRC has
previously granted alternatives under
§ 50.55a(z) that eliminate the reactor
pressure vessel threads-in-flange
examinations (ASME Section XI,
Examination Category B–G–1, Item No.
B6.40) for up to two inservice
inspection intervals through the NRC’s
alternative request process. For
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alternatives that requested elimination
of the examination for a second
consecutive 10-year inservice inspection
interval, the NRC has been requesting
additional information on activities
performed to ensure that the condition
of the reactor pressure vessel threads-inflange receives some level of
monitoring. These activities typically
have included care and maintenance of
the reactor vessel threads-in-flange (and
studs) whenever the closure head is
removed. The NRC has limited approval
of such requests to two subsequent
inservice inspection intervals because
the NRC has determined that complete
elimination of the examinations does
not provide adequate protection against
long-term degradation of the threads-inflange. The NRC is imposing conditions
on the use of Code Case N–864 that are
consistent with the limits the NRC has
placed on similar alternatives requests.
The first condition in Code Case N–
864 requires that the reactor pressure
vessel threads-in-flange examinations
(ASME Section XI, Examination
Category B–G–1, Item No. B6.40) must
be performed in at least every third 10year ISI interval. This condition also
limits the application of Code Case N–
864 at facilities that have been
authorized under § 50.55a(z) to use
alternatives that eliminate reactor
pressure vessel threads-in-flange
examinations to ensure that the required
examination is performed at least every
third 10-year inservice inspection
interval.
The second condition in Code Case
N–864 ensures that sufficient
monitoring and maintenance activities
are performed and documented when
the code case is applied. As a result of
public comments, the NRC clarified that
performing and documenting the
facility’s maintenance procedures for
removal, care, and visual inspection of
the reactor head closure studs and
threads in flange during each refueling
outage are sufficient to satisfy the
second condition.
Code Case N–869 [Supplement 6, 2017
Edition]
Type: New.
Title: Evaluation Criteria for
Temporary Acceptance of Flaws in
Class 2 or 3 Piping, Section XI, Division
1.
Code Case N–869 contains provisions
for temporary acceptance of flaws,
including through-wall flaws in Class 2
or 3 piping including elbows, pipe
bends, reducers, and branch tees, whose
maximum operating pressure is greater
than 275 psig and does not exceed 600
psig, without performing a repair/
replacement activity. The code case
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contains provisions regarding the scope,
flaw characterization, periodic leakage
monitoring, flaw evaluation, and
augmented examinations. The NRC
finds that the code case provides
reasonable assurance that structural
integrity of degraded piping will be
maintained until the next scheduled
refueling outage. However, the NRC
finds that the augmented examination
provisions in Section 5 of the code case
are unclear and need additional
clarification.
When a licensee applies N–869 to
disposition a through-wall leak or wall
thinning in a piping system, Section 5
of the code case requires augmented
examinations for flaws and significant
flaws. The augmented examination
requirements in N–869 are the same as
in Code Case N–513–3.
In 2018, the NRC found an instance
where a licensee misinterpreted the
provisions in Section 5 of N–513–3 and
did not perform the required augmented
examinations to disposition a throughwall leak in a service water system pipe.
Other licensees have similarly
misinterpreted the augmented
examination provisions in Section 5 of
N–513–3. The NRC found that the issue
stems from the definition of the terms
‘‘flaw’’ and ‘‘significant flaw’’ in
Sections 5(b) and 5(c) of N–513–3,
respectively. The NRC, therefore,
imposes two conditions to define ‘‘flaw’’
and ‘‘significant flaw’’ as those terms are
used in Section 5 of N–869. Licensees
would be required to apply these
definitions to Section 5 when using the
code case.
The first condition defines a ‘‘flaw’’ as
a non-through-wall planar or nonplanar
flaw with a wall thickness less than 87.5
percent of the nominal wall thickness of
the pipe or the design minimum wall
thickness. The NRC notes that the pipe
wall thickness at the time of the plant
construction may deviate from the
nominal pipe wall thickness slightly as
part of manufacturing process. The
generally accepted deviation is 12.5
percent of the nominal pipe wall
thickness or the design minimum wall
thickness.
The second condition defines
‘‘significant flaw’’ as any pipe location
that does not satisfy the provisions of
Section 3 of N–869 or if any detected
flaw that has a depth greater than 75
percent of the pipe wall thickness. The
NRC staff notes that the 75 percent wall
thickness criterion originates from the
provisions of IWC/IWD–3643 of the
ASME Code, Section XI, which prohibit
a flaw that exceeds 75 percent of the
pipe wall thickness to remain in service.
Under Section 5 of N–869, a planar flaw
that exceeds 75 percent of the pipe wall
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thickness may remain in service;
however, the licensee needs to perform
an augmented examination.
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Code Case N–876 [Supplement 2, 2017
Edition]
Type: New.
Title: Austenitic Stainless Steel
Cladding and Nickel Base Cladding
Using Ambient Temperature Automatic
or Machine Dry Underwater Laser Beam
Welding (ULBW) Temper Bead
Technique, Section XI, Division 1.
Some irradiated stainless steel reactor
vessel internal components are
susceptible to experiencing irradiation
assisted stress corrosion cracking. Code
Case N–876 provides guidelines for
repair welding the irradiated stainless
steel components inside the reactor
vessel. Code Case N–876 provides an
alternative to the cladding temper bead
repair rules of Section XI, IWA–4400,
which requires preheat and postweld
heat treatment. This alternative
establishes new rules governing ambient
temperature temper bead cladding
repairs using the ULBW process.
The NRC is imposing two conditions
on this code case. The first condition
that must be applied when performing
ULBW on irradiated materials provides
guidance on what level of neutron
irradiation and/or helium content
would require review and approval by
the NRC because of the impact of
neutron fluence on weldability. The
second condition limits the depth of the
cladding repair due to concerns with the
fracture toughness of the base metal.
The technical basis for imposing
conditions on the welding of irradiated
materials are that neutrons can generate
helium atoms within the metal lattice
through transmutation of various
isotopes of boron and/or nickel. At high
temperatures, such as occurs during
welding, these helium atoms rapidly
diffuse though the metal lattice,
coalescing and forming helium bubbles
at the grain boundaries. In sufficient
concentration, these helium bubbles can
cause grain boundary cracking that
occurs in the fusion zones and heat
affected zones during the heat-up/
cooldown cycle.
The first condition applies conditions
already applicable to Code Case N–516–
5 ‘‘Underwater Welding Section XI,
Division 1,’’ that the provisions of
§ 50.55a(b)(2)(xii)(A) and (B) must be
met. This regulation provides limits on
specific levels of neutron irradiation
and/or helium content, above which
welding is prohibited without prior
NRC review and approval. The NRC is
imposing the same condition to uses of
Code Case N–876.
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The second condition is necessary
because the code case does not require
impact testing of the base metal heat
affected zone (HAZ) to verify adequate
fracture toughness. The code case
allows the depth of the repair cavity
into the ferritic base metal to be up to
1⁄4″. This would allow welding directly
to the base metal; thus, it will affect the
fracture toughness of the base metal in
the HAZ. Therefore, the NRC is
imposing a condition restricting the use
of the code case to repairs where at least
1⁄8″ of cladding remains. The basis for
the 1⁄8″ limit is that this amount of
austenitic material between the ferritic
base metal and the first weld layer has
generally been considered to sufficiently
limit the heat input to the base metal
such that deleterious effects on the
fracture toughness will not occur;
therefore, impact testing of the base
metal is not necessary. The NRC notes
that Code Case N–803, which is
approved without conditions, allows
repair of ferritic base material using
nonferritic weld filler material based on
welding procedure qualifications
performed using tensile tests, side
bends, and impact tests, and could be
used to perform a cladding repair in
which excavation into the base metal is
required.
Code Case N–878 [Supplement 1, 2017
Edition]
Type: New.
Title: Alternative to QA Program
Requirements of IWA–4142, Section XI,
Division 1.
Code Case N–878 provides
alternatives to the quality assurance
requirements in IWA–4142 for
procurement of Class 1, 2, or 3 nonwelded fittings. This code case
addresses the testing and certification of
material used in the manufacture of
non-welded fittings, but does not
address how the licensee must ensure
that the procured non-welded fittings
meet the design and testing
requirements of the ASME Code,
Section III, NB/NC/ND–3671.7 for Class
1, 2, or 3 applications. Verification that
the Section III requirements for the
design and testing of these non-welded
fittings have been met prior to use is
essential in ensuring the structural
integrity of these Class 1, 2 and 3
systems is maintained. Therefore, the
NRC is imposing conditions for the
licensee to verify the design and testing
activities associated with qualification
of non-welded fittings required by
Section III, NB/NC/ND–3671.7 that are
performed by the fabricator.
The first condition states for ASME
Section III items, the Licensee must
review the fabricator’s design
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documentation and methods to ensure
the fittings design is in compliance with
the Licensee’s design specifications, and
ASME Section III NB/NC/ND–3671.7
requirements; and either (1) supervise
and monitor the performance
qualification tests of the fittings to
ensure the design is in compliance with
the Licensee’s design specifications and
ASME Section III NB/NC/ND–3671.7, or
(2) the Licensee or Repair/Replacement
Organization conducts qualification
tests of the fittings or conducts design
analyses to ensure the design is in
compliance with the Licensee’s design
specifications and ASME Section III NB/
NC/ND–3671.7. In response to public
comments, the NRC clarified that for
ASME Section III items, this condition
applies only for those licensees that
implemented ASME Code, Section III
design requirements for their original
construction code and/or the licensees
that have upgraded their original design
requirements to ASME Code, Section III.
The second condition states that the
Licensees must give the Authorized
Nuclear Inservice Inspector an
opportunity to review the design report
prior to installation.
Code Case N–880 [Supplement 2, 2017
Edition]
Type: New.
Title: Alternative to Procurement
Requirements of IWA–4143 for Small
Nonstandard Welded Fittings, Section
XI, Division 1.
Code Case N–880 provides
alternatives to the material procurement
requirements of IWA–4142 and IWA–
4143 for small nonstandard welded
fittings. This code case does not address
how the licensee must ensure the
procured welded fittings meet the
design and testing requirements of the
ASME Code, Section III, NB/NC/ND–
3671.7 for Class 1, 2, or 3 applications.
Verification that the Section III
requirements for the design and testing
of these welded fittings have been met
prior to use is essential in ensuring the
structural integrity of these Class 1, 2
and 3 systems is maintained. Therefore,
the NRC is imposing conditions
requiring the licensee to verify the
design and testing activities associated
with qualification of welded fittings
required by Section III, NB/NC/ND–
3671.7 that are performed by the
fabricator.
The first condition states for ASME
Section III items, the Licensee must
review the fabricator’s design
documentation and methods to ensure
the fittings design is in compliance with
the Licensee’s design specifications, and
ASME Section III NB/NC/ND–3671.7
requirements; and either: (1) Supervise
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and monitor the performance
qualification tests of the fittings to
ensure the design is in compliance with
the Licensee’s design specifications and
ASME Section III NB/NC/ND–3671.7, or
(2) the Licensee or Repair/Replacement
Organization conducts qualification
tests of the fittings or conducts design
analyses to ensure the design is in
compliance with the Licensee’s design
specifications and ASME Section III NB/
NC/ND–3671.7. In response to public
comments, the NRC clarified that for
ASME Section III items, this condition
applies only for those licensees that
implemented ASME Code, Section III
design requirements for their original
construction code and/or the licensees
that have upgraded their original design
requirements to ASME Code, Section III.
The second condition states that the
Licensees must give the Authorized
Nuclear Inservice Inspector an
opportunity to review the design report
prior to installation.
Code Case N–889 [Supplement 7, 2017
Edition]
Type: New.
Title: Reference Stress Corrosion
Crack Growth Rate Curves for Irradiated
Austenitic Stainless Steel in Light-Water
Reactor Environments, Section XI,
Division 1.
Code Case N–889 provides a new
crack growth rate (CGR) law for
irradiation-assisted stress corrosion
cracking. The code case is applicable to
wrought austenitic stainless steels and
associated weld metals, as well as cast
austenitic stainless steels. The proposed
CGR law requires the user to first
calculate irradiated yield stress from the
dose to the material. There are two yield
stress models: One for Molybdenum
bearing stainless steels and one for
stainless steels without Molybdenum.
Once irradiated yield stress has been
determined, the user calculates the CGR
as a function of applied crack driving
force and temperature.
The staff identified three concerns
with the technical basis of this code
case. The first concern relates to the
limited CGR data at dose levels greater
than 20 displacements per atom (dpa).
The proposed CGR law indicates that
the irradiated yield stress (and,
consequently, the CGR) increases with
fluence up to a dose of 20 dpa, at which
point the irradiated yield’s stress ceases
to increase appreciably with further
dose accumulation. While the data at
dose levels greater than 20 dpa does
show a plateau behavior in the CGR, the
staff’s analyses of that data suggests that
areas of high CGR were averaged over
the industry calculation of CGR, which
increases the uncertainty in the high
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dose CGRs. Therefore, due to the limited
data and the associated high uncertainty
at high fluence, the staff’s confidence in
CGRs at dose levels greater than 20 dpa
is low.
The second concern is the effects of
uncertainty in the irradiated yield
strength value for an individual
material-heat. This topic is discussed in
Section 4.7 of the technical basis report
for Code Case N–889. The NRC also
conducted separate analyses. While the
results of the NRC’s findings are
generally consistent with the results in
Section 4.7, the interpretation of their
significance is not consistent. For
materials with yield strengths greater
than 600 MPa (i.e., more highlyirradiated materials), the expected CGR
for a material with a yield strength in
the 95th percentile is less than two
times the CGR predicted by the code
case, which is not a significant
difference. However, for materials with
yield strength values less than 250 MPa
(i.e., unirradiated or minimally
irradiated materials), the expected CGR
for a material in the 95th percentile can
be more than five times greater than the
CGR predicted by the code case. Hence,
the NRC’s concern is that the CGRs for
individual low yield strength materials,
or materials with low fluence, could be
significantly underpredicted by the code
case.
The final concern is related to the
data used in the development of the
irradiated yield stress model. The
methodology for addressing cold work
in this model was developed in MRP–
135, Revision 1, while the model itself
was developed in MRP–211, Revision 0.
The database underlying the model
included hundreds of yield strength
measurements on initially annealed and
cold-worked Types 304, 316, and 347/
348 stainless steel materials. However,
most of the data were for annealed Type
304 and cold-worked Type 316 stainless
steels. Revision 1 of MRP–211 contained
additional yield strength data, including
significantly more data for cold-worked
Types 304 and 347 stainless steel. The
authors of the code case, as documented
in Section 4.5 of the Additional Basis
Report dated February 5, 2018,
evaluated the code case yield stress
model with some of this additional data
and found agreement between the
model and the additional data.
However, the code case authors
excluded new data for cold-worked
Type 304 and 347 stainless steel
materials. Therefore, the technical basis
document for Code Case N–889 does not
directly address whether cold-worked
Type 304 and 347 (non-Molybdenum
bearing) materials are adequately
predicted by the irradiated yield
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strength model in the code case. The
NRC is imposing three conditions on
this code case.
The first condition states that this
code case may not be applied for
neutron exposures greater than 20 dpa.
This condition addresses the NRC
concern that there is sparse data with
high uncertainty beyond 20 dpa. Given
that the predicted CGR saturates at
higher fluence, this condition prevents
potential underprediction of the CGR in
this fluence regime.
The second condition states that at
dose levels below 0.75 dpa, the user
must use the higher of the Code Case N–
889 or the Section XI, Nonmandatory
Appendix C, C–8520 CGR predictions.
This condition addresses the NRC
concern related to possible
underprediction of CGR in Code Case
N–889 for materials with calculated
irradiated yield strength less than 250
MPa.
The final condition states that the
irradiated yield stress model for coldworked Molybdenum bearing materials
must be used for cold-worked nonMolybdenum bearing stainless steels
(including Type 204 and 247 stainless
steels). This condition addresses the
NRC concern that data for cold-worked
non-Molybdenum bearing steels were
not appropriately considered during
development of Code Case N–889. The
NRC performed its own evaluation of
cold-worked Type 304 and 347 stainless
steels in the MRP–211 database and
found that the yield strength was better
predicted by the code case’s
Molybdenum bearing model than with
the code case’s non-Molybdenum
bearing model.
Code Case N–890 [Supplement 0, 2019
Edition]
Type: New.
Title: Materials Exempted From G–
2110(b) Requirements, Section XI,
Division 1.
Code Case N–890 provides an
alternative to Section XI, G–2110(b)
which removes the requirement of,
‘‘obtaining fracture toughness data for at
least three heats,’’ for using the static
fracture toughness curve (Klc) curve for
specific materials with a minimum
specified yield strength at room
temperature between 50 kilopound per
square inch (ksi) and 90 ksi. Code Case
N–890 would allow the toughness of
four ferritic steels (SA–508 Grade 2
Class 2, SA–508 Grade 3 Class 2, SA–
533 Type A Class 2 and SA–533 Type
B Class 2) with specified minimum
yield strength greater than 50 ksi to be
characterized by Figure G–2110–1 (i.e.,
the Section XI Klc curve).
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The NRC identified one technical
concern when reviewing the technical
basis of this code case. The technical
basis provided appropriate data to
justify use of the Klc curve for several
materials listed in the code case.
However, for SA–533 Type B, Class 2
materials, the NRC observed that in the
technical basis document, there is no
fracture toughness data associated with
the weld and heat affected zone to
support exclusion of the fracture
toughness testing requirements for these
materials.
As such, the imposed NRC condition
requires the user to comply with the
provisions of Section III, NB–2300 and
Section III, G–2110(b) to demonstrate
the applicability of the ASME Klc curve
to SA–533 Type B, Class 2 material.
These provisions require the user to
generate the necessary toughness data to
demonstrate that the ASME KIC curve is
a conservative representation of the
actual material toughness.
3. ASME Operation and Maintenance
Code Cases (RG 1.192)
Code Case OMN–1, Revision 2 [2020
Edition]
Type: Reaffirmed.
Title: Alternative Rules for Preservice
and Inservice Testing of Active Electric
Motor-Operated Valve Assemblies in
Light-Water Reactor Power Plants.
The conditions on Code Case OMN–
1, Revision 2 [2020 Edition] are
identical to the conditions on OMN–1,
Revision 2 [2017 Edition] that were
approved by the NRC in Revision 3 of
RG 1.192. The OMN–1, Revision 2 was
reaffirmed by the ASME in the 2020
Edition with no change to the code case.
Therefore, the conditions are retained in
Revision 4 of RG 1.192.
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Code Case OMN–3 [2020 Edition]
Type: Reaffirmed.
Title: Requirements for Safety
Significance Categorization of
Components Using Risk Insights for
Inservice Testing of LWR Power Plants.
The conditions on Code Case OMN–
3 [2020 Edition] are identical to the
conditions on OMN–3 [2017 Edition]
that were approved by the NRC in
Revision 3 of RG 1.192. The OMN–3
was reaffirmed by the ASME in the 2020
Edition with no change to the code case.
Therefore, the conditions are retained in
Revision 4 of RG 1.192.
Code Case OMN–4 [2020 Edition]
Type: Reaffirmed.
Title: Requirements for Risk Insights
for Inservice Testing of Check Valves at
LWR Power Plants.
The conditions on Code Case OMN–
4 [2020 Edition] are identical to the
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conditions on OMN–4 [2017 Edition]
that were approved by the NRC in
Revision 3 of RG 1.192. The OMN–4
was reaffirmed by the ASME in the 2020
Edition with no change to the code case.
Therefore, the conditions are retained in
Revision 4 of RG 1.192.
Code Case OMN–9 [2020 Edition]
Type: Reaffirmed.
Title: Use of a Pump Curve for
Testing.
The conditions on Code Case OMN–
9 [2020 Edition] are identical to the
conditions on OMN–9 [2017 Edition]
that were approved by the NRC in
Revision 3 of RG 1.192. The OMN–9
was reaffirmed by the ASME in the 2020
Edition with no change to the code case.
Therefore, the conditions are retained in
Revision 4 of RG 1.192.
Code Case OMN–12 [2020 Edition]
Type: Reaffirmed.
Title: Alternative Requirements for
Inservice Testing Using Risk Insights for
Pneumatically and Hydraulically
Operated Valve Assemblies in LightWater Reactor Power Plants (OM-Code
1998, Subsection ISTC).
The conditions on Code Case OMN–
12 [2020 Edition] are identical to the
conditions on OMN–12 [2017 Edition]
that were approved by the NRC in
Revision 3 of RG 1.192. The OMN–12
was reaffirmed by the ASME in the 2020
Edition with no change to the code case.
Therefore, the conditions are retained in
Revision 4 of RG 1.192.
Code Case OMN–19 [2020 Edition]
Type: Reaffirmed.
Title: Alternative Upper Limit for the
Comprehensive Pump Test.
The conditions on Code Case OMN–
19 [2020 Edition] are identical to the
conditions on OMN–19 [2017 Edition]
that were approved by the NRC in
Revision 3 of RG 1.192. The OMN–19
was reaffirmed by the ASME in the 2020
Edition with no change to the code case.
Therefore, the conditions are retained in
Revision 4 of RG 1.192.
Code Case OMN–20 [2020 Edition]
Type: Reaffirmed.
Title: Inservice Test Frequency.
The conditions on Code Case OMN–
20 [2020 Edition] are identical to the
conditions on OMN–20 [2017 Edition]
that were approved by the NRC in
Revision 3 of RG 1.192. The OMN–20
was reaffirmed by the ASME in the 2020
Edition with no change to the code case.
Therefore, the conditions are retained in
Revision 4 of RG 1.192.
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C. ASME Code Cases Not Approved for
Use (RG 1.193)
The ASME code cases that are
currently issued by the ASME, but not
approved for generic use by the NRC,
are listed in RG 1.193, ‘‘ASME Code
Cases not Approved for Use.’’ In
addition to the ASME code cases that
the NRC has found to be technically or
programmatically unacceptable, RG
1.193 includes code cases on reactor
designs for high-temperature gas-cooled
reactors and liquid metal reactors,
reactor designs not currently licensed by
the NRC, and certain requirements in
Section III, Division 2, for submerged
spent fuel waste casks, that are not
endorsed by the NRC. RG 1.193
complements RGs 1.84, 1.147, and
1.192. It should be noted that the NRC
is not adopting any of the code cases
listed in RG 1.193.
III. Opportunities for Public
Participation
The proposed rule and draft RGs were
published in the Federal Register on
February 2, 2021 (86 FR 7820), for a 60day comment period. The public
comment period closed on April 5,
2021.
IV. Public Comment Analysis
The NRC published the proposed rule
and draft regulatory guides for public
comment in the Federal Register. The
NRC received 13 comment submissions.
A comment submission is a
communication or document submitted
to the NRC by an individual or entity,
with one or more individual comments
addressing a subject or issue. Private
citizens provided five comment
submissions, nuclear industry
organizations provided five comment
submissions, a foreign government
entity provided one comment
submission, an anonymous commenter
provided one comment submission, and
a science advocacy group provided one
comment submission.
The comment submissions generally
addressed the code cases and their
proposed conditions, with five comment
submissions objecting to incorporation
of a code case with no conditions in this
rulemaking activity. The NRC received
a number of comments that were
outside the scope of this rulemaking,
such as comments that discuss code
cases annulled after the publication of
the supplements being considered in
this rulemaking. The latter group out of
scope comments will be considered in
a future rulemaking.
The public comment submittals are
available from the Federal e-Rulemaking
website at https://www.regulations.gov
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under Docket ID NRC–2017–0025. The
NRC prepared a summary and analysis
of public comments received on the
2020 proposed rule and draft regulatory
guides, which is available as indicated
in the ‘‘Availability of Documents’’
section of this document. Responses to
the public comments, including a
summary of how the final rule text or
guidance changed as a result of the
public comments, can be found in the
public comment analysis.
For more information about the
associated guidance documents, see the
‘‘Availability of Guidance’’ section of
this document.
V. Section-by-Section Analysis
The following paragraphs in § 50.55a
are revised:
Paragraph (b)(1)(ii), Table 1
This final rule revises the reference to
table 1 in the text of the paragraph, and
designates the table and revises the
heading of the table to conform to Office
of the Federal Register (OFR)
codification requirements.
Paragraph (b)(2)(xv)(K)(4), Table 2
This final rule designates the table
and revises the heading of the table to
conform to OFR codification
requirements.
Paragraph (b)(3)(iv), Table 3
This final rule revises the last
sentence to update the contact
information for the National Archives
and Records Administration.
This final rule designates the table
and revises the heading of the table to
conform to OFR codification
requirements, and capitalizes the word
‘‘(Years)’’ in two of the three column
headings.
Paragraph (a)(1) Introductory Text
VI. Regulatory Flexibility Certification
This final rule corrects a printing
error by removing the line break after
‘‘telephone:’’.
As required by the Regulatory
Flexibility Act (5 U.S.C. 605(b)), the
Commission certifies that this rule, if
adopted, will not have a significant
economic impact on a substantial
number of small entities. This final rule
affects only the licensing and operation
of nuclear power plants. The companies
that own these plants do not fall within
the scope of the definition of ‘‘small
entities’’ set forth in the Regulatory
Flexibility Act or the size standards
established by the NRC (§ 2.810).
Paragraph (a) Introductory Text
Paragraph (a)(3) Introductory Text
This final rule adds a reference to new
paragraph (a)(3)(iv), which indicates
that NUREG–2228 is acceptable as
specified in the conditions when
implementing code cases listed in
certain NRC regulatory guides.
Paragraph (a)(3)(i)
This final rule revises the reference to
‘‘NRC Regulatory Guide 1.84, Revision
38,’’ by removing ‘‘Revision 38’’ and
adding in its place ‘‘Revision 39’’ and
changes the month and year for the
document’s revision date.
Paragraph (a)(3)(ii)
This final rule revises the reference to
‘‘NRC Regulatory Guide 1.147, Revision
19’’ by removing ‘‘Revision 19’’ and
adding in its place ‘‘Revision 20’’ and
changes the month and year for the
document’s revision date.
Paragraph (a)(3)(iii)
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Validation Procedure,’’ Published July
2020 (including Errata September 22,
2021), which is referenced in RG 1.147,
Revision 20.
This final rule revises the reference to
‘‘NRC Regulatory Guide 1.192, Revision
3’’ by removing ‘‘Revision 3’’ and
adding in its place ‘‘Revision 4’’ and
changes the month and year for the
document’s revision date.
Paragraph (a)(3)(iv)
This final rule adds new paragraph
(a)(3)(iv) to reference NUREG–2228,
‘‘Weld Residual Stress Finite Element
Analysis Validation: Part II—Proposed
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VII. Regulatory Analysis
The NRC has prepared a regulatory
analysis on this regulation. The analysis
examines the costs and benefits of the
alternatives considered by the NRC. The
NRC did not receive public comments
on the draft regulatory analysis. The
final regulatory analysis is available as
indicated in the ‘‘Availability of
Documents’’ section of this document.
VIII. Backfitting and Issue Finality
The provisions in this final rule allow
licensees and applicants to voluntarily
apply NRC-approved code cases,
sometimes with NRC-specified
conditions. The approved code cases are
listed in three RGs that are incorporated
by reference into § 50.55a. An
applicant’s or a licensee’s voluntary
application of an approved code case
does not constitute backfitting, because
there is no imposition of a new
requirement or new position.
Similarly, voluntary application of an
approved code case by a 10 CFR part 52
applicant or licensee does not represent
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NRC imposition of a requirement or
action, and therefore is not inconsistent
with any issue finality provision in 10
CFR part 52. For these reasons, the NRC
finds that this final rule does not
involve any provisions requiring the
preparation of a backfit analysis or
documentation demonstrating that one
or more of the issue finality criteria in
10 CFR part 52 are met.
IX. Plain Writing
The Plain Writing Act of 2010 (Pub.
L. 111–274) requires Federal agencies to
write documents in a clear, concise, and
well-organized manner. The NRC has
written this document to be consistent
with the Plain Writing Act as well as the
Presidential Memorandum, ‘‘Plain
Language in Government Writing,’’
published June 10, 1998 (63 FR 31885).
X. Environmental Assessment and Final
Finding of No Significant
Environmental Impact
The Commission has determined
under the National Environmental
Policy Act of 1969, as amended, and the
Commission’s regulations in subpart A
of 10 CFR part 51, that this rule, if
adopted, would not be a major Federal
action significantly affecting the quality
of the human environment; therefore, an
environmental impact statement is not
required.
The determination of this
environmental assessment is that there
will be no significant effect on the
quality of the human environment from
this action. The NRC did not receive
public comments regarding any aspect
of this environmental assessment.
As voluntary alternatives to the ASME
Code, NRC-approved code cases provide
an equivalent level of safety. Therefore,
the probability or consequences of
accidents is not changed. There are also
no significant, non-radiological impacts
associated with this action because no
changes would be made affecting nonradiological plant effluents and because
no changes would be made in activities
that would adversely affect the
environment. The determination of this
environmental assessment is that there
will be no significant offsite impact to
the public from this action.
XI. Paperwork Reduction Act
This final rule amends collections of
information subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501
et seq.). The collections of information
were approved by the Office of
Management and Budget, approval
number 3150–0011.
Because the rule will reduce the
burden for existing information
collections, the public burden for the
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information collections is expected to be
decreased by 230 hours per response.
This reduction includes the time for
reviewing instructions, searching
existing data sources, gathering and
maintaining the data needed, and
completing and reviewing the
information collection.
The information collection is being
conducted to document the plans for
and the results of inservice inspection
and inservice testing programs. The
records are generally historical in nature
and provide data on which future
activities can be based. Information will
be used by the NRC to determine if
ASME BPV and OM Code provisions for
construction, inservice inspection,
repairs, and inservice testing are being
properly implemented in accordance
with § 50.55a of the NRC regulations, or
whether specific enforcement actions
are necessary. Responses to this
collection of information are mandatory
under § 50.55a.
You may submit comments on any
aspect of the information collections,
including suggestions for reducing the
burden, by the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2017–0025.
• Mail comments to: FOIA, Library,
and Information Collections Branch,
Office of the Chief Information Officer,
Mail Stop: T–6 A10M, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001 or to the OMB reviewer
at: OMB Office of Information and
Regulatory Affairs (3150–0011) Attn:
Desk Officer for the Nuclear Regulatory
Commission, 725 17th Street NW,
Washington, DC 20503; email: oira_
submission@omb.eop.gov.
Public Protection Notification
The NRC may not conduct or sponsor,
and a person is not required to respond
to, a collection of information unless the
document requesting or requiring the
collection displays a currently valid
OMB control number.
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XII. Congressional Review Act
This final rule is a rule as defined in
the Congressional Review Act (5 U.S.C.
801–808). However, the Office of
Management and Budget has not found
it to be a major rule as defined in the
Congressional Review Act.
XIII. Voluntary Consensus Standards
The National Technology Transfer
and Advancement Act of 1995, Public
Law 104–113, requires that Federal
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agencies use technical standards that are
developed or adopted by voluntary
consensus standards bodies unless
using such a standard is inconsistent
with applicable law or is otherwise
impractical. In this final rule, the NRC
is continuing to use the ASME BPV and
OM code cases, which are ASMEapproved voluntary alternatives to
compliance with various provisions of
the ASME BPV and OM Codes. The
NRC’s approval of the ASME code cases
is accomplished by amending the NRC’s
regulations to incorporate by reference
the latest revisions of the following,
which are the subject of this
rulemaking, into § 50.55a: RG 1.84,
Revision 39; RG 1.147, Revision 20; RG
1.192, Revision 4; and NUREG–2228.
The RGs list the ASME code cases that
the NRC has approved for use. The
ASME code cases are national
consensus standards as defined in the
National Technology Transfer and
Advancement Act of 1995 and OMB
Circular A–119. The ASME code cases
constitute voluntary consensus
standards, in which all interested
parties (including the NRC and
licensees of nuclear power plants)
participate.
XIV. Incorporation by ReferenceReasonable Availability to Interested
Parties
The NRC is incorporating by reference
three NRC RGs that list new and revised
ASME code cases that the NRC has
approved as voluntary alternatives to
certain provisions of NRC-required
editions and addenda of the ASME BPV
Code and the ASME OM Code. These
regulatory guides are RG 1.84, Revision
39; RG 1.147, Revision 20; and RG
1.192, Revision 4. The NRC is also
incorporating by reference NUREG–
2228, which is referenced in RG 1.147,
Revision 20. As described in this
document, this report pertains to a
condition on Code Case N–847.
The NRC is required by law to obtain
approval for incorporation by reference
from the OFR. The OFR’s requirements
for incorporation by reference are set
forth in 1 CFR part 51. The discussion
in this section complies with the
requirement for final rules as set forth
in 1 CFR 51.5(b)(2).
The NRC considers ‘‘interested
parties’’ to include all potential NRC
stakeholders, not only the individuals
and entities regulated or otherwise
subject to the NRC’s regulatory
oversight. These NRC stakeholders are
not a homogenous group, so the
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considerations for determining
‘‘reasonable availability’’ vary by class
of interested parties. The NRC identified
six classes of interested parties with
regard to the material to be incorporated
by reference in an NRC rule:
• Individuals and small entities
regulated or otherwise subject to the
NRC’s regulatory oversight. This class
includes applicants and potential
applicants for licenses and other NRC
regulatory approvals, and who are
subject to the material to be
incorporated by reference. In this
context, ‘‘small entities’’ has the same
meaning as set out in § 2.810.
• Large entities otherwise subject to
the NRC’s regulatory oversight. This
class includes applicants and potential
applicants for licenses and other NRC
regulatory approvals, and who are
subject to the material to be
incorporated by reference. In this
context, a ‘‘large entity’’ is one that does
not qualify as a ‘‘small entity’’ under
§ 2.810.
• Non-governmental organizations
with institutional interests in the
matters regulated by the NRC.
• Other Federal agencies, states, local
governmental bodies (within the
meaning of § 2.315(c)).
• Federally-recognized and Staterecognized Indian tribes.
• Members of the general public (i.e.,
individual, unaffiliated members of the
public who are not regulated or
otherwise subject to the NRC’s
regulatory oversight) who need access to
the materials that the NRC proposes to
incorporate by reference in order to
participate in the rulemaking.
The NUREG–2228 and three RGs that
the NRC is incorporating by reference in
this final rule are available without cost
and can be read online or downloaded
online. The NUREG–2228 and three RGs
can be viewed, by appointment, at the
NRC Technical Library, which is located
at Two White Flint North, 11545
Rockville Pike, Rockville, Maryland
20852; telephone: 301–415–7000; email:
Library.Resource@nrc.gov.
Because access to NUREG–2228 and
the three final regulatory guides is
available in various forms at no cost, the
NRC determines that NUREG–2228 and
the three final regulatory guides, RG
1.84, Revision 39; RG 1.147, Revision
20; and RG 1.192, Revision 4, once
approved by the OFR for incorporation
by reference, are reasonably available to
all interested parties.
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TABLE III—REGULATORY GUIDES INCORPORATED BY REFERENCE IN 10 CFR 50.55A
ADAMS Accession No./
Federal Register
citation
Document title
RG 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39 ....................................
RG 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20 .......................................
RG 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4 ...............................................
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TABLE IV—RELATED DOCUMENTS INCORPORATED BY REFERENCE IN 10 CFR 50.55A
ADAMS Accession No./
Federal Register
citation
Document title
NUREG–2228, ‘‘Weld Residual Stress Finite Element Analysis Validation: Part II—Proposed Validation Procedure,’’ July
2020 ...........................................................................................................................................................................................
XV. Availability of Guidance
The NRC is issuing revised guidance,
RG 1.193, ‘‘ASME Code Cases Not
Approved for Use,’’ Revision 7, for the
implementation of the requirements in
this final rule. The guidance is available
as indicated in Section XVI,
‘‘Availability of Documents,’’ of this
document. You may access information
and comment submissions related to the
guidance by searching on https://
www.regulations.gov under Docket ID
NRC–2017–0025.
The regulatory guide lists code cases
that the NRC has not approved for
generic use and will not be incorporated
by reference into the NRC’s regulations.
XVI. Availability of Documents
The documents identified in the
following table are available to
interested persons through one or more
of the following methods, as indicated.
ADAMS Accession No./web link/
Federal Register
citation
Document
RG 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, December 2021 ........
RG 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, December 2021 ...........
RG 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, December 2021 ...................
RG 1.193, ASME Code Cases Not Approved for Use, Revision 7 ..............................................................................................
NUREG–2228, ‘‘Weld Residual Stress Finite Element Analysis Validation: Part II–Proposed Validation Procedure,’’ July
2020 ...........................................................................................................................................................................................
Rulemaking–Proposed Rule–Draft Regulatory Analysis for the American Society of Mechanical Engineers Code Cases, RG
1.84, Rev 39; RG 1.147, Rev 20; RG 1.192 Rev 4 ..................................................................................................................
Rulemaking–Final Rule–Final Regulatory Analysis for the American Society of Mechanical Engineers Code Cases, RG 1.84,
Rev 39; RG 1.147, Rev 20; RG 1.192 Rev 4 ............................................................................................................................
NRC Responses to Public Comments ..........................................................................................................................................
Proposed Rule–Approval of American Society of Mechanical Engineers Code Cases RG 1.84, Rev 39; RG 1.147, Rev 20;
RG 1.192 Rev 4 .........................................................................................................................................................................
Proposed Rule–Approval of American Society of Mechanical Engineers Code Cases RG 1.84, Rev 39; RG 1.147, Rev 20;
RG 1.192 Rev 4 .........................................................................................................................................................................
Final Rule–Approval of American Society of Mechanical Engineers Code Cases RG 1.84, Rev 38; RG 1.147, Rev 19; RG
1.192 Rev 3 ................................................................................................................................................................................
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List of Subjects in 10 CFR Part 50
Antitrust, Classified information,
Criminal penalties, Fire protection,
Incorporation by reference,
Intergovernmental relations, Nuclear
power plants and reactors, Radiation
protection, Reactor siting criteria,
Reporting and recordkeeping
requirements.
For the reasons set out in the
preamble and under the authority of the
Atomic Energy Act of 1954, as amended;
the Energy Reorganization Act of 1974,
as amended; and 5 U.S.C. 552 and 553,
the NRC is adopting the following
amendments to 10 CFR part 50:
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86 FR 7820
85 FR 14736
PART 50—DOMESTIC LICENSING OF
PRODUCTION AND UTILIZATION
FACILITIES
3504 note; Sec. 109, Pub. L. 96–295, 94 Stat.
783.
1. The authority citation for part 50
continues to read as follows:
■
■
Authority: Atomic Energy Act of 1954,
secs. 11, 101, 102, 103, 104, 105, 108, 122,
147, 149, 161, 181, 182, 183, 184, 185, 186,
187, 189, 223, 234 (42 U.S.C. 2014, 2131,
2132, 2133, 2134, 2135, 2138, 2152, 2167,
2169, 2201, 2231, 2232, 2233, 2234, 2235,
2236, 2237, 2239, 2273, 2282); Energy
Reorganization Act of 1974, secs. 201, 202,
206, 211 (42 U.S.C. 5841, 5842, 5846, 5851);
Nuclear Waste Policy Act of 1982, sec. 306
(42 U.S.C. 10226); National Environmental
Policy Act of 1969 (42 U.S.C. 4332); 44 U.S.C.
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2. In § 50.55a:
a. Revise the last sentence of
paragraph (a) introductory text and
paragraphs (a)(1) introductory text and
(a)(3) introductory text;
■ b. In paragraph (a)(3)(i):
■ i. Remove the text ‘‘Revision 38’’ and
add in its place the text ‘‘Revision 39’’;
and
■ ii. Remove the text ‘‘dated October
2019’’ and add in its place the text
‘‘issued December 2021’’;
■ c. In paragraph (a)(3)(ii):
■
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i. Remove the text ‘‘Revision 19’’ and
add in its place the text ‘‘Revision 20’’;
and
■ ii. Remove the text ‘‘dated October
2019’’ and add in its place the text
‘‘issued December 2021’’;
■ d. In paragraph (a)(3)(iii):
■ i. Remove the text ‘‘Revision 3’’ and
add in its place the text ‘‘Revision 4’’;
and
■ ii. Remove the text ‘‘dated October
2019’’ and add in its place the text
‘‘issued December 2021’’;
■ e. Add paragraph (a)(3)(iv);
■ f. In paragraph (b)(1)(ii), remove the
text ‘‘Table I of this section’’ and add in
its place the text ‘‘table 1 to this
paragraph (b)(1)(ii)’’;
■ g. Designate the table immediately
following paragraph (b)(1)(ii) as table 1
to paragraph (b)(1)(ii) and revise the
heading of the newly designated table;
■ h. Designate the table immediately
following paragraph (b)(2)(xv)(K)(4) as
table 2 to paragraph (b)(2)(xv)(K)(4) and
revise the heading of the newly
designated table; and
■ i. Designate the table immediately
following paragraph (b)(3)(iv) as table 3
to paragraph (b)(3)(iv) and revise the
heading and column headings of the
newly designated table.
■
The revisions and addition read as
follows:
§ 50.55a
Codes and standards.
(a) * * * For information on the
availability of this material at NARA,
email fr.inspection@nara.gov or go to
www.archives.gov/federal-register/cfr/
ibr-locations.html.
(1) American Society of Mechanical
Engineers (ASME), Three Park Avenue,
New York, NY 10016; telephone: 1–
800–843–2763; https://www.asme.org/
Codes/.
*
*
*
*
*
(3) U.S. Nuclear Regulatory
Commission (NRC) Public Document
Room, 11555 Rockville Pike, Rockville,
Maryland 20852; telephone: 1–800–
397–4209; email: pdr.resource@nrc.gov;
https://www.nrc.gov/reading-rm/doccollections/reg-guides/. The use of code
cases listed in the NRC regulatory
guides in paragraphs (a)(3)(i) through
(iii) of this section is acceptable with the
specified conditions in those guides
when implementing the editions and
addenda of the ASME BPV Code and
ASME OM Code incorporated by
reference in paragraph (a)(1) of this
section. The NRC report in paragraph
(a)(3)(iv) of this section is acceptable as
specified in the conditions when
implementing code cases listed in the
NRC regulatory guides in paragraphs
(a)(3)(i) through (iii) of this section.
*
*
*
*
*
(iv) NUREG–2228. NUREG–2228,
‘‘Weld Residual Stress Finite Element
Analysis Validation: Part II—Proposed
Validation Procedure,’’ Published July
2020 (including Errata September 22,
2021), which is referenced in RG 1.147,
Revision 20.
*
*
*
*
*
(b) * * *
(1) * * *
(ii) * * *
Table 1 to Paragraph (b)(1)(ii)—
Prohibited Code Provisions
*
*
*
*
*
(2) * * *
(xv) * * *
(K) * * *
(4) * * *
Table 2 to Paragraph (b)(2)(xv)(K)(4)—
Table VIII: S7–1—Modified
*
*
*
*
*
(3) * * *
(iv) * * *
TABLE 3 TO PARAGRAPH (b)(3)(iv)—MAXIMUM INTERVALS FOR USE WHEN APPLYING INTERVAL EXTENSIONS
Maximum interval between activities of
member valves in the groups
(years)
Group size
*
*
*
*
*
*
*
*
Dated: January 25, 2022.
For the Nuclear Regulatory Commission.
Andrea D. Veil,
Director, Office of Nuclear Reactor
Regulation.
[FR Doc. 2022–04374 Filed 3–2–22; 8:45 am]
BILLING CODE 7590–01–P
FEDERAL ELECTION COMMISSION
11 CFR Part 111
khammond on DSKJM1Z7X2PROD with RULES
[Notice 2022–04]
Agency Procedure Concerning the
Treatment of Foreign State
Respondents at the Initiation of the
Enforcement Process
Federal Election Commission.
Adoption of Agency procedure.
AGENCY:
ACTION:
The Federal Election
Commission is adopting a procedure
concerning the enforcement process in
situations where the respondent to a
SUMMARY:
VerDate Sep<11>2014
16:19 Mar 02, 2022
Jkt 256001
*
Maximum interval between activities of each
valve in the group
(years)
*
complaint is a foreign state, a political
subdivision of a foreign state, a head of
state or other foreign official acting in
his or her official capacity, or an agency
or instrumentality of a foreign state.
DATES: The procedure is adopted as of
March 3, 2022.
FOR FURTHER INFORMATION CONTACT: Mr.
Robert Mark Knop, Assistant General
Counsel, 1050 First Street NE,
Washington, DC 20463, (202) 694 1650
or (800) 424 9530.
SUPPLEMENTARY INFORMATION: This
procedure requires the Commission to
adopt a supplemental notification
process in matters involving foreign
state respondents.
In all enforcement matters in which a
foreign state, political subdivision of a
foreign state, a head of state or other
foreign official acting in his or her
official capacity, or any agency or
instrumentality of a foreign state is
identified as a respondent, the Office of
General Counsel (‘‘OGC’’), prior to
issuing the notification letters required
PO 00000
Frm 00018
Fmt 4700
Sfmt 4700
*
*
by 52 U.S.C. 30109(a)(1), will notify the
Office of the Legal Adviser at the
Department of State (‘‘Department’’) of
the receipt of the complaint and of the
Commission’s statutory notification
obligations. This procedure does not
alter the Commission’s statutory
obligation to issue notification letters to
respondents within the period required
by 52 U.S.C. 30109(a)(1).
In such matters, OGC will provide a
simultaneous report to the Commission
concerning the notification to the
Department and will promptly inform
the Commission of any subsequent
communications between OGC and the
Department.
Within forty-five days of receiving a
complaint naming a foreign state
respondent, OGC will make a
recommendation to the Commission as
to whether consultation with the
Department is appropriate to obtain its
views concerning any legal or factual
question presented by the matter.
This notification represents a general
statement announcing the general
E:\FR\FM\03MRR1.SGM
03MRR1
Agencies
[Federal Register Volume 87, Number 42 (Thursday, March 3, 2022)]
[Rules and Regulations]
[Pages 11934-11950]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2022-04374]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Part 50
[NRC-2017-0025]
RIN 3150-AJ94
Approval of American Society of Mechanical Engineers' Code Cases
AGENCY: Nuclear Regulatory Commission.
ACTION: Final rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its
regulations to incorporate by reference revisions of three regulatory
guides to approve new, revised, and reaffirmed code cases published by
the American Society of Mechanical Engineers. The NRC is also
incorporating by reference one NRC NUREG associated with a condition on
one of the regulatory guides. This action allows nuclear power plant
licensees and applicants for construction permits, operating licenses,
combined licenses, standard design certifications, standard design
approvals, and manufacturing licenses to use the code cases listed in
these regulatory guides as voluntary alternatives to engineering
standards for the construction, inservice inspection, and inservice
testing of nuclear power plant components. These engineering standards
are set forth in the American Society of Mechanical Engineers' Boiler
and Pressure Vessel Codes and American Society of Mechanical Engineers'
Operation and Maintenance Codes, which are currently incorporated by
reference into the NRC's regulations. Further, this final rule
announces the availability of a related regulatory guide, not
incorporated by reference into the NRC's regulations, that lists code
cases that the NRC has not approved for use.
DATES: This final rule is effective on April 4, 2022. The incorporation
by reference of certain publications listed in the regulation is
approved by the Director of the Federal Register as of April 4, 2022.
ADDRESSES: Please refer to Docket ID NRC-2017-0025 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-2017-0025. Address
questions about NRC dockets to Dawn Forder; telephone: 301-415-3407;
email: [email protected]. For technical questions, contact the
individuals listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
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]. For the convenience of the reader,
instructions about obtaining materials referenced in this document are
provided in the ``Availability of Documents'' section.
NRC's PDR: You may examine and purchase copies of public
documents, by appointment, at the NRC's 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.
Technical Library: The Technical Library, which is located
at Two White Flint North, 11545 Rockville Pike, Rockville, Maryland
20852, is open by appointment only. Interested parties may make
appointments to examine documents by contacting the NRC Technical
Library by email at [email protected] between 8:00 a.m. and 4:00
p.m. (ET), Monday through Friday, except Federal holidays.
FOR FURTHER INFORMATION CONTACT: Martha Barillas, Office of Nuclear
Material Safety and Safeguards; telephone: 301-415-2760, email:
[email protected]; or Bruce Lin, Office of Nuclear Regulatory
Research, telephone: 301-415-2446; email: [email protected]. Both are
staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.
SUPPLEMENTARY INFORMATION:
Executive Summary
A. Need for the Regulatory Action
The purpose of this regulatory action is to incorporate by
reference into the NRC's regulations the latest revisions of three
regulatory guides (RGs). This regulatory action is also incorporating
by reference, NUREG-2228, ``Weld Residual Stress Finite Element
Analysis Validation: Part II--Proposed Validation Procedure,'' that is
associated with a condition in one of the regulatory guides. The three
RGs identify new,
[[Page 11935]]
revised, and reaffirmed code cases published by the American Society of
Mechanical Engineers (ASME), which the NRC has determined are
acceptable for use as voluntary alternatives to compliance with certain
provisions of the ASME Boiler and Pressure Vessel Code (BPV Code) and
the ASME Code for Operation and Maintenance of Nuclear Power Plants,
Division 1, OM Code: Section IST (OM Code), currently incorporated by
reference into the NRC's regulations.
B. Major Provisions
The three RGs that the NRC is incorporating by reference are RG
1.84, ``Design, Fabrication, and Materials Code Case Acceptability,
ASME Section III,'' Revision 39; RG 1.147, ``Inservice Inspection Code
Case Acceptability, ASME Section XI, Division 1,'' Revision 20; and RG
1.192, ``Operation and Maintenance [OM] Code Case Acceptability, ASME
OM Code,'' Revision 4. The NRC is also incorporating by reference
NUREG-2228, which provides the procedure for validating the weld
residual stress analysis methodology associated with ASME Code Case N-
847. This final rule allows nuclear power plant licensees and
applicants for construction permits, operating licenses, combined
licenses, standard design certifications, standard design approvals,
and manufacturing licenses to use the code cases newly listed in these
revised RGs as voluntary alternatives to engineering standards for the
construction, inservice inspections, and inservice testing of nuclear
power plant components. In this document, the NRC also notifies the
public of the availability of RG 1.193, ``ASME Code Cases Not Approved
for Use,'' Revision 7. This document lists code cases that the NRC has
not approved for generic use and is not incorporated by reference into
the NRC's regulations.
The NRC prepared a regulatory analysis to determine the expected
quantitative costs and benefits of this final rule, as well as
qualitative factors to be considered in the NRC's rulemaking decision.
The analysis concluded that this rule results in net savings to the
industry and the NRC. As shown in Table 1, the estimated total net
benefits relative to the regulatory baseline range from approximately
$5.86 million (7-percent net present value) to $6.67 million (3-percent
net present value).
Table 1--Cost Benefit Summary
----------------------------------------------------------------------------------------------------------------
Total averted costs (costs)
-----------------------------------------------
Attribute 7% Net present 3% Net present
Undiscounted value value
----------------------------------------------------------------------------------------------------------------
Industry Implementation......................................... $0 $0 $0
Industry Operation.............................................. 4,920,000 3,920,000 4,450,000
-----------------------------------------------
Total Industry Costs........................................ 4,920,000 3,920,000 4,450,000
NRC Implementation.............................................. 0 0 0
NRC Operation................................................... 2,460,000 1,940,000 2,220,000
-----------------------------------------------
Total NRC Costs............................................. 2,460,000 1,940,000 2,220,000
-----------------------------------------------
Net..................................................... 7,380,000 5,860,000 6,670,000
----------------------------------------------------------------------------------------------------------------
The regulatory analysis also considered the following qualitative
considerations: (1) Flexibility and decreased uncertainty for licensees
when making modifications or preparing to perform inservice inspection
or inservice testing; (2) consistency with the provisions of the
National Technology Transfer and Advancement Act of 1995, which
encourages Federal regulatory agencies to consider adopting voluntary
consensus standards as an alternative to de novo agency development of
standards affecting an industry; (3) consistency with the NRC's policy
of evaluating the latest versions of consensus standards in terms of
their suitability for endorsement by regulations and regulatory guides;
and (4) consistency with the NRC's goal to harmonize with international
standards to improve regulatory efficiency for both the NRC and
international standards groups.
The regulatory analysis concludes that this final rule should be
adopted because it is justified when integrating the cost-beneficial
quantitative results and the positive and supporting nonquantitative
considerations in the decision. For more information, please see the
final regulatory analysis as indicated in Section XVI, ``Availability
of Documents,'' of this document.
Table of Contents
I. Background
II. Discussion
III. Opportunities for Public Participation
IV. Public Comment Analysis
V. Section-by-Section Analysis
VI. Regulatory Flexibility Certification
VII. Regulatory Analysis
VIII. Backfitting and Issue Finality
IX. Plain Writing
X. Environmental Assessment and Final Finding of No Significant
Environmental Impact
XI. Paperwork Reduction Act
XII. Congressional Review Act
XIII. Voluntary Consensus Standards
XIV. Incorporation by Reference-Reasonable Availability to
Interested Parties
XV. Availability of Guidance
XVI. Availability of Documents
I. Background
The ASME develops and publishes the ASME BPV Code, which contains
requirements for the design, construction, and inservice inspection
examination of nuclear power plant components, and the ASME OM Code,\1\
which contains requirements for inservice testing of nuclear power
plant components. In response to BPV and OM Code user requests, the
ASME develops code cases that provide voluntary alternatives to BPV and
OM Code requirements under special circumstances.
---------------------------------------------------------------------------
\1\ The editions and addenda of the ASME Code for Operation and
Maintenance of Nuclear Power Plants have had different titles from
2005 to 2017 and are referred to as the ``OM Code'' collectively in
this rule.
---------------------------------------------------------------------------
The NRC approves the ASME BPV and OM Codes in Sec. 50.55a, ``Codes
and standards,'' of title 10 of the Code of Federal Regulations (10
CFR) through the process of incorporation by reference. As such, each
provision of the ASME Codes incorporated by reference into and mandated
by Sec. 50.55a
[[Page 11936]]
constitutes a legally-binding NRC requirement imposed by rule. As noted
previously, the ASME code cases, for the most part, represent
alternative approaches for complying with provisions of the ASME BPV
and OM Codes. Accordingly, the NRC periodically amends Sec. 50.55a to
incorporate by reference the NRC's RGs listing approved ASME code cases
that may be used as voluntary alternatives to the BPV and OM Codes.\2\
---------------------------------------------------------------------------
\2\ See Federal Register final rule, ``Incorporation by
Reference of ASME BPV and OM Code Cases'' (68 FR 40469; July 8,
2003).
---------------------------------------------------------------------------
This final rule is the latest in a series of rules that incorporate
by reference new versions of several RGs identifying new, revised, and
reaffirmed,\3\ and unconditionally or conditionally acceptable ASME
code cases that the NRC approves for use. In developing these RGs, the
NRC reviews the ASME BPV and OM code cases, determines the
acceptability of each code case, and publishes its findings in the RGs.
The RGs are revised periodically as new code cases are published by the
ASME. The NRC incorporates by reference the RGs listing acceptable and
conditionally acceptable ASME code cases into Sec. 50.55a. The NRC
published a final rule dated March 16, 2020, that incorporated by
reference into Sec. 50.55a the most recent versions of the RGs, which
are RG 1.84, ``Design, Fabrication, and Materials Code Case
Acceptability, ASME Section III,'' Revision 38; RG 1.147, ``Inservice
Inspection Code Case Acceptability, ASME Section XI, Division 1,''
Revision 19; and RG 1.192, ``Operation and Maintenance Code Case
Acceptability, ASME OM Code,'' Revision 3.
---------------------------------------------------------------------------
\3\ Code Cases are categorized by the ASME as one of three
types: New, revised, or reaffirmed. A new Code Case provides for a
new alternative to specific the ASME Code provisions or addresses a
new need. The ASME defines a revised Code Case to be a revision
(modification) to an existing Code Case to address, for example,
technological advancements in examination techniques or to address
NRC conditions imposed in one of the RGs that have been incorporated
by reference into Sec. 50.55a. The ASME defines ``reaffirmed'' as
an OM Code Case that does not have any change to technical content,
but includes editorial changes.
---------------------------------------------------------------------------
II. Discussion
This final rule incorporates by reference NUREG-2228 and the latest
revisions of the NRC's RGs that list the ASME BPV and OM code cases
that the NRC finds to be acceptable, or acceptable with NRC-specified
conditions (``conditionally acceptable''). Regulatory Guide 1.84,
Revision 39, supersedes the incorporation by reference of Revision 38;
RG 1.147, Revision 20, supersedes the incorporation by reference of
Revision 19; and RG 1.192, Revision 4, supersedes the incorporation by
reference of Revision 3.
The ASME code cases that are the subject of this final rule are the
new and revised Section III and Section XI code cases as listed in
Supplements 0 through 7 to the 2015 Edition of the ASME BPV Code,
Supplements 0 through 7 to the 2017 Edition of the ASME BPV Code,
Supplements 0 and 1 to the 2019 Edition of the ASME BPV Code, and the
OM code cases listed in the 2020 Edition of the ASME OM Code and on the
ASME Codes & Standards (C&S) Connect website.\4\
---------------------------------------------------------------------------
\4\ The ASME included code cases with the published editions and
addenda of the OM Code through the 2017 Edition. Starting with the
2020 Edition, code cases were not published with the OM Code; an
applicability index for ASME OM code cases was published. Code cases
are available on the ASME website under the ``O&M CASES'' tab in the
left-hand column at https://go.asme.org/OMcommittee.
---------------------------------------------------------------------------
The latest editions and addenda of the ASME BPV and OM Codes that
the NRC has approved for use are referenced in Sec. 50.55a. The ASME
also publishes code cases that provide alternatives to existing Code
requirements that the ASME developed and approved. This final rule
incorporates by reference the most recent revisions of RGs 1.84, 1.147,
and 1.192, which allow nuclear power plant licensees, and applicants
for combined licenses, standard design certifications, standard design
approvals, and manufacturing licenses under the regulations that govern
license certifications, to use the code cases listed in these RGs as
suitable alternatives to the ASME BPV and OM Codes for the
construction, inservice inspections, and inservice testing of nuclear
power plant components. Because the NRC is requiring the use of NUREG-
2228 within a condition on Code Case N-847, the NRC is also
incorporating by reference NUREG-2228. The ASME publishes the OM Code
Cases and lists the code cases in the ASME OM Code edition and on the
ASME C&S Connect website. In contrast, the ASME publishes BPV code
cases in a separate document and at a different time than the ASME BPV
code editions. This final rule identifies the code cases by the edition
of the ASME BPV Code or ASME OM Code under which they were published by
the ASME.
The following general guidance applies to the use of the ASME code
cases approved in the latest versions of the RGs that are incorporated
by reference into Sec. 50.55a as part of this final rule.
Specifically, the use of the code cases listed in the latest versions
of RGs 1.84, 1.147, and 1.192 are acceptable with the specified
conditions when implementing the editions and addenda of the ASME BPV
and OM Codes incorporated by reference in Sec. 50.55a.
The approval of a code case in the NRC's RGs constitutes acceptance
of its technical position for applications that are not precluded by
regulatory or other requirements or by the recommendations in these
RGs. The applicant or licensee is responsible for ensuring that use of
the code case does not conflict with regulatory requirements or
licensee commitments. The code cases listed in the RGs are acceptable
for use within the limits specified in the code cases. If the RG states
an NRC condition on the use of a code case, then the NRC condition
supplements and does not supersede any condition(s) specified in the
code case, unless otherwise stated in the NRC condition.
The ASME code cases may be revised for many reasons (e.g., to
incorporate operational examination and testing experience and to
update material requirements based on research results). On occasion,
an inaccuracy in an equation is discovered or an examination, as
practiced, is found not to be adequate to detect a newly discovered
degradation mechanism.
Therefore, when an applicant or a licensee initially implements a
code case, Sec. 50.55a requires that the applicant or the licensee
implement the most recent version of that code case, as listed in the
RGs incorporated by reference. Code cases superseded by revision are no
longer acceptable for new applications unless otherwise indicated.
Section III of the ASME BPV Code applies to new construction (i.e.,
the edition and addenda to be used in the construction of a plant are
selected based on the date of the construction permit and are not
changed thereafter, except voluntarily by the applicant or the
licensee). Hence, if a Section III code case is implemented by an
applicant or a licensee and a later version of the code case is
incorporated by reference into Sec. 50.55a and listed in the RG, the
applicant or licensee may use either version of the code case (subject,
however, to whatever change requirements apply to its licensing basis
(e.g., Sec. 50.59)).
A licensee's inservice inspection and inservice testing programs
must be updated every 10 years to the latest edition and addenda of the
ASME BPV Code, Section XI, and the OM Code, respectively, that were
incorporated by reference into Sec. 50.55a and in effect 18
[[Page 11937]]
months prior to the start of the next inspection and testing interval.
Licensees that were using a code case prior to the effective date of
its revision may continue to use the previous version for the remainder
of the 120-month inservice inspection or inservice testing interval.
This relieves licensees of the burden of having to update their
inservice inspection or inservice testing program each time a code case
is revised by the ASME and approved for use by the NRC. Code cases
apply to specific editions and addenda, and code cases may be revised
if they are no longer accurate or adequate, so licensees choosing to
continue using a code case during the subsequent inservice inspection
or inservice testing interval must implement the latest version
incorporated by reference into Sec. 50.55a and listed in the RGs.
The ASME may annul code cases that are no longer required, are
determined to be inaccurate or inadequate, or have been incorporated
into the BPV or OM Codes. A code case may be revised, for example, to
incorporate user experience. The older or superseded version of the
code case cannot be applied by the licensee or applicant unless it was
applied prior to being annulled or superseded.
If an applicant or a licensee applied a code case before it was
listed as superseded, the applicant or the licensee may continue to
use the code case until the applicant or the licensee updates its
construction Code of Record (in the case of an applicant, updates
its application) or until the licensee's 120-month inservice
inspection or inservice testing update interval expires, after which
the continued use of the code case is prohibited unless NRC
authorization is given under Sec. 50.55a(z). If a code case is
incorporated by reference into Sec. 50.55a and later a revised
version is issued by the ASME because experience has shown that the
design analysis, construction method, examination method, or testing
method is inadequate, the NRC will amend Sec. 50.55a and the
relevant RG to remove the approval of the superseded code case.
Applicants and licensees should not begin to implement such
superseded code cases in advance of the rulemaking.
A. ASME Code Cases Approved for Unconditional Use
The code cases discussed in Table I are new, revised, or reaffirmed
code cases in which the NRC approves for use without conditions. The
table identifies the regulatory guide listing the applicable code case
that the NRC approves for use.
Table I--Acceptable Code Cases
----------------------------------------------------------------------------------------------------------------
Code Case No. Published with supplement Title
----------------------------------------------------------------------------------------------------------------
Boiler and Pressure Vessel Code Section III
(Addressed in RG 1.84, Table 1)
----------------------------------------------------------------------------------------------------------------
N-249-17.............................. 0 (2019 Edition)........................ Additional Materials for
Subsection NF, Classes 1, 2,
3, and MC Supports Fabricated
without Welding, Section III,
Division 1.
N-539-1............................... 0 (2017 Edition)........................ UNS N08367 in Class 2 and 3
Valves, Section III, Division
1.
N-692-1............................... 6 (2015 Edition)........................ Use of Standard Welding
Procedures, Section III,
Division 1.
N-721-1............................... 5 (2017 Edition)........................ Alternative Rules for Linear
Piping Supports, Section III,
Division 1.
N-801-3............................... 1 (2017 Edition)........................ Rules for Repair of N-Stamped
Class 1, 2, and 3 Components,
Section III, Division 1.
N-822-4............................... 7 (2015 Edition)........................ Application of the ASME
Certification Mark, Section
III, Divisions 1, 2, 3, and
5.
N-855................................. 2 (2015 Edition)........................ SB-148 C95800 Valves for Class
3 Construction, Section III,
Division 1.
N-856................................. 2 (2015 Edition)........................ SA-494 Grade CW-12MW (UNS
N30002) Nickel Alloy Castings
for Construction of NPS 2\1/
2\ and Smaller Flanged Valves
for Class 3 Construction,
Section III, Division 1.
N-859................................. 5 (2015 Edition)........................ Construction of ASME B16.9
Wrought Buttwelding Fittings
and ASME B16.11 Forged
Fittings Made From SB-366 UNS
N04400 Material for Section
III, Class 3 Construction,
Section III, Division 1.
N-863-1............................... 1 (2017 Edition)........................ Post Weld Heat Treatment
(PWHT) of Valve Seal Welds
for P4 and P5A Materials,
Section III, Division 1.
N-866................................. 0 (2017 Edition)........................ Alternative Materials for
Construction of Section III,
Class 2 Vessels, Section III,
Division 1.
N-870-1............................... 4 (2017 Edition)........................ Rules for the Elimination of
External Surface Defects on
Class 1, 2, and 3 Piping,
Pumps, or Valves After
Component Stamping and Prior
to Completion of the N-3 Data
Report, Section III, Division
1.
N-879................................. 1 (2017 Edition)........................ Use of Micro-Alloyed Carbon
Steel Bar in Patented
Mechanical Joints and
Fittings, Classes 1, 2, and
3, Section III, Division 1.
N-884................................. 0 (2019 Edition)........................ Procedure to Determine Strain
Rate for Use with the
Environmental Fatigue Design
Curve Method and the
Environmental Fatigue
Correction Factor, Fen,
Method as Part of an
Environmental Fatigue
Evaluation for Components
Analyzed per the NB-3200
Rules, Section III, Division
1.
N-887................................. 6 (with errata issued in 3/19E)......... Alternatives to the
Requirements of NB-4424.2(a),
Figure NB-4250-2, and Figure
NB-4250-3, Section III,
Division 1.
N-891................................. 0 (2019 Edition)........................ Alternative Requirements to
Appendix XXVI, XXVI-2400,
XXVI-4130, and XXVI-4131 for
Inspection and Repair of
Indentations for Polyethylene
Pipe and Piping Components,
Section III, Division 1.
----------------------------------------------------------------------------------------------------------------
Boiler and Pressure Vessel Code Section XI
(Addressed in RG 1.147, Table 1)
----------------------------------------------------------------------------------------------------------------
N-561-3............................... 0 (2019 Edition)........................ Alternative Requirements for
Wall Thickness Restoration of
Class 2 and High Energy Class
3 Carbon Steel Piping,
Section XI, Division 1.
N-638-10.............................. 1 (2019 Edition)........................ Similar and Dissimilar Metal
Welding Using Ambient
Temperature Machine GTAW
Temper Bead Technique,
Section XI, Division 1.
N-653-2............................... 2 (2015 Edition)........................ Qualification Requirements for
Full Structural Overlaid
Wrought Austenitic Piping
Welds, Section XI, Division
1.
N-702-1............................... 1 (2019 Edition)........................ Alternative Requirements for
Boiling Water Reactor (BWR)
Nozzle Inner Radius and
Nozzle-to-Shell Welds,
Section XI, Division 1.
N-716-2............................... 0 (2017 Edition)........................ Alternative Piping
Classification and
Examination Requirements,
Section XI, Division 1.
[[Page 11938]]
N-768................................. 0 (2019 Edition)........................ Alternative Volumetric
Coverage Requirements for
Ultrasonic Examination of
Class 1 and 2 Pressure Vessel
Weld Joints Greater Than 2
in. (50 mm) in Thickness,
Section XI, Division 1.
N-786-3............................... 1 (2017 Edition)........................ Alternative Requirements for
Sleeve Reinforcement of Class
2 and 3 Moderate Energy
Carbon Steel Piping, Section
XI, Division 1.
N-789-3............................... 1 (2017 Edition)........................ Alternative Requirements for
Pad Reinforcement of Class 2
and 3 Moderate Energy Carbon
Steel Piping for Raw Water
Service, Section XI, Division
1.
N-809................................. 2 (2015 Edition)........................ Reference Fatigue Crack Growth
Rate Curves for Austenitic
Stainless Steels in
Pressurized Reactor Water
Environments, Section XI,
Division 1.
N-845-1............................... 6 (2015 Edition)........................ Qualification Requirements for
Bolts and Studs, Section XI,
Division 1.
N-848-1............................... 0 (2017 Edition)........................ Alternative Characterization
Rules for Quasi-Laminar
Flaws, Section XI, Division
1.
N-851................................. 0 (2015 Edition)........................ Alternate Method for
Establishing the Reference
Temperature for Pressure
Retaining Materials, Section
XI, Division 1.
N-858................................. 2 (2017 Edition)........................ Alternative Volumetric
Coverage Requirements for
Ultrasonic Examination of
Class 1 Nozzle-to-Vessel
Welds, Section XI, Division
1.
N-865................................. 2 (2017 Edition)........................ Alternative Requirements for
Pad Reinforcement of Class 2
and 3 Atmospheric Storage
Tanks, Section XI, Division
1.
N-867................................. 0 (2017 Edition)........................ Clarification of NDE Practical
Examination Requirements,
Section XI, Division 1.
N-873................................. 1 (2017 Edition)........................ Examination Requirements for
the Core Makeup Tanks,
Section XI, Division 1.
N-874................................. 7 (2017 Edition)........................ Temporary Acceptance of
Leakage Through Brazed Joints
of Class 3 Copper, Copper-
Nickel, and Nickel-Copper
Moderate Energy Piping,
Section XI, Division 1.
N-877................................. 2 (2017 Edition)........................ Alternative Characterization
Rules for Multiple Subsurface
Radially Oriented Planar
Flaws, Section XI, Division
1.
N-882................................. 6 (2017 Edition)........................ Alternative Requirements for
Attaching Nonstructural
Electrical Connections to
Class 2 and 3 Components,
Section XI, Division 1.
N-885................................. 0 (2019 Edition)........................ Alternative Requirements for
Table IWB-2500-1, Examination
Category B-N-1, Interior of
Reactor Vessel, Category B-N-
2, Welded Core Support
Structures and Interior
Attachments to Reactor
Vessels, Category B-N-3,
Removable Core Support
Structures, Section XI,
Division 1.
N-892................................. 0 (2019 Edition)........................ Alternative Requirement for
Form OAR-1, Owner's Activity
Report, Completion Time,
Section XI, Division 1.
----------------------------------------------------------------------------------------------------------------
Operation and Maintenance Code
(Addressed in RG 1.192, Table 1)
----------------------------------------------------------------------------------------------------------------
OMN-13, Revision 3.................... 2020 Edition............................ Performance-Based Requirements
for Extending Snubber
Inservice Visual Examination
Interval at LWR Power Plants.
OMN-15, Revision 3.................... 2020 Edition............................ Performance-Based Requirements
for Extending the Snubber
Operational Readiness Testing
Interval at LWR Power Plants.
OMN-17, Revision 1.................... 2020 Edition............................ Alternative Requirements for
Testing ASME Class 1 Pressure
Relief/Safety Valves.
OMN-18 \5\............................ 2020 Edition............................ Alternate Testing Requirements
for Pumps Tested Quarterly
Within 20% of
Design Flow.
OMN-22................................ 2020 Edition............................ Smooth Running Pumps.
OMN-23................................ 2020 Edition............................ Alternative Requirements for
Testing Pressure Isolation
Valves.
OMN-24................................ 2020 Edition............................ Alternative Requirements for
Testing ASME Class 2 and 3
Pressure Relief Valves (For
Relief Valves in a Group of
One).
OMN-25................................ 2020 Edition............................ Alternative Requirements for
Testing Appendix I Pressure
Relief Valves.
OMN-26................................ 2020 Edition............................ Alternate Risk-Informed and
Margin Based Rules for
Inservice Testing of Motor
Operated Valves.
OMN-27................................ 2020 Edition............................ Alternative Requirements for
Testing Category A Valves
(Non-PIV/CIV)
----------------------------------------------------------------------------------------------------------------
---------------------------------------------------------------------------
\5\ As a result of a public comment, the NRC agreed that the
condition to require the slightly more restrictive upper-end values
of the acceptable ranges for flow and differential pressure are not
necessary to provide reasonable assurance that the implementation of
Code Case OMN-18 will demonstrate the acceptable performance of
pumps within the scope of the ASME OM Code. Therefore, the NRC
deleted the condition proposed and moved OMN-18 to Table I.
---------------------------------------------------------------------------
B. ASME Code Cases Approved for Use With Conditions
The NRC determined that certain code cases, as issued by the ASME,
are generally acceptable for use, but that the alternative requirements
specified in those code cases must be supplemented in order to provide
an acceptable level of quality and safety. Accordingly, the NRC imposes
conditions on the use of these code cases to modify, limit, or clarify
their requirements. The conditions specify, for each applicable code
case, the additional activities that must be performed, the limits on
the activities specified in the code case, and/or the supplemental
information needed to provide clarity. These ASME code cases, listed in
Table II below, are included in Table 2 of RG 1.84, RG 1.147, and RG
1.192. This section provides the NRC's evaluation of the code cases and
the reasons for the NRC's conditions. Notations indicate the conditions
duplicated from previous versions of the RG.
[[Page 11939]]
Table II--Conditionally Acceptable Code Cases
----------------------------------------------------------------------------------------------------------------
Code Case No. Published with supplement Title
----------------------------------------------------------------------------------------------------------------
Boiler and Pressure Vessel Code Section III
(Addressed in RG 1.84, Table 2)
----------------------------------------------------------------------------------------------------------------
N-71-20............................... 6 (2015 Edition)........................ Additional Materials for
Subsection NF, Class 1, 2, 3,
and MC Supports Fabricated by
Welding, Section III,
Division 1.
N-155-3............................... 5 (2015 Edition)........................ Fiberglass Reinforced
Thermosetting Resin Pipe,
Section III, Division 1.
N-755-4............................... 1 (2017 Edition)........................ Use of Polyethylene (PE) Class
3 Plastic Pipe, Section III,
Division 1.
N-779................................. 8 (2007 Edition) \6\.................... Alternative Rules for
Simplified Elastic-Plastic
Analysis Class 1, Section
III, Division 1.
N-852................................. 0 (2015 Edition)........................ Application of the ASME NPT
Stamp, Section III, Divisions
1, 2, 3, and 5.
N-883................................. 5 (2017 Edition)........................ Construction of Items Prior to
the Establishment of a
Section III, Division 1
Owner, Section III, Division
1.
N-886................................. 6 (2017 Edition)........................ Use of Polyethylene Pipe for
Class 3, Section III,
Division 1.
----------------------------------------------------------------------------------------------------------------
Boiler and Pressure Vessel Code Section XI
(Addressed in RG 1.147, Table 2)
----------------------------------------------------------------------------------------------------------------
N-513-5............................... 6 (2017 Edition)........................ Evaluation Criteria for
Temporary Acceptance of Flaws
in Moderate Energy Class 2 or
3 Piping and Gate Valves,
Section XI, Division 1.
N-516-5............................... 6 (2015 Edition)........................ Underwater Welding, Section
XI, Division 1.
N-597-3............................... 5 (2013 Edition)........................ Evaluation of Pipe Wall
Thinning, Section XI.
N-705-1............................... 2 (2017 Edition)........................ Evaluation Criteria for
Temporary Acceptance of
Degradation in Moderate
Energy Class 2 or 3 Vessels
and Tanks, Section XI,
Division 1.
N-766-3............................... 2 (2017 Edition)........................ Nickel Alloy Reactor Coolant
Inlay and Onlay for
Mitigation of PWR Full
Penetration Circumferential
Nickel Alloy Dissimilar Metal
Welds in Class 1 Items,
Section XI, Division 1.
N-778................................. 0 (2010 Edition)........................ Alternative Requirements for
Preparation and Submittal of
Inservice Inspection Plans,
Schedules, and Preservice and
Inservice Inspection Summary
Reports, Section XI, Division
1.
N-831-1............................... 7 (2017 Edition)........................ Ultrasonic Examination in Lieu
of Radiography for Welds in
Ferritic or Austenitic Pipe,
Section XI, Division 1.
N-847................................. 0 (2017 Edition)........................ Partial Excavation and
Deposition of Weld Metal for
Mitigation of Class 1 Items,
Section XI, Division 1.
N-864................................. 2 (2017 Edition)........................ Reactor Vessel Threads in
Flange Examinations, Section
XI, Division 1.
N-869................................. 6 (2017 Edition)........................ Evaluation Criteria for
Temporary Acceptance of Flaws
in Class 2 or 3 Piping,
Section XI, Division 1.
N-876................................. 2 (2017 Edition)........................ Austenitic Stainless Steel
Cladding and Nickel Base
Cladding Using Ambient
Temperature Automatic or
Machine Dry Underwater Laser
Beam Welding (ULBW) Temper
Bead Technique, Section XI,
Division 1.
N-878................................. 1 (2017 Edition)........................ Alternative to QA Program
Requirements of IWA-4142,
Section XI, Division 1.
N-880................................. 2 (2017 Edition)........................ Alternative to Procurement
Requirements of IWA-4143 for
Small Nonstandard Welded
Fittings, Section XI,
Division 1.
N-889................................. 7 (2017 Edition)........................ Reference Stress Corrosion
Crack Growth Rate Curves for
Irradiated Austenitic
Stainless Steel in Light-
Water Reactor Environments,
Section XI, Division 1.
N-890................................. 0 (2019 Edition)........................ Materials Exempted From G-
2110(b) Requirement, Section
XI, Division 1.
----------------------------------------------------------------------------------------------------------------
Operation and Maintenance Code
(Addressed in RG 1.192, Table 2)
----------------------------------------------------------------------------------------------------------------
OMN-1, Revision 2..................... 2020 Edition............................ Alternative Rules for
Preservice and Inservice
Testing of Active Electric
Motor-Operated Valve
Assemblies in Light-Water
Reactor Power Plants.
OMN-3................................. 2020 Edition............................ Requirements for Safety
Significance Categorization
of Components Using Risk
Insights for Inservice
Testing of LWR Power Plants.
OMN-4................................. 2020 Edition............................ Requirements for Risk Insights
for Inservice Testing of
Check Valves at LWR Power
Plants.
OMN-9................................. 2020 Edition............................ Use of a Pump Curve for
Testing.
OMN-12................................ 2020 Edition............................ Alternative Requirements for
Inservice Testing Using Risk
Insights for Pneumatically
and Hydraulically Operated
Valve Assemblies in Light-
Water Reactor Power Plants
(OM-Code 1998, Subsection
ISTC).
OMN-19................................ 2020 Edition............................ Alternative Upper Limit for
the Comprehensive Pump Test.
OMN-20................................ 2020 Edition............................ Inservice Test Frequency.
----------------------------------------------------------------------------------------------------------------
---------------------------------------------------------------------------
\6\ Correcting editorial error from proposed rule to final rule
to state correct supplement 8.
---------------------------------------------------------------------------
1. ASME BPV Code, Section III Code Cases (RG 1.84)
Code Case N-71-20 [Supplement 6, 2015 Edition]
Type: Revised.
Title: Additional Materials for Subsection NF, Class 1, 2, 3, and
MC Supports Fabricated by Welding, Section III, Division 1.
The conditions on Code Case N-71-20 are the same as the conditions
on N-71-19 that were approved by the NRC in Revision 38 of RG 1.84.
When the ASME revised N-71, the code case was not modified in a way
that would make
[[Page 11940]]
it possible for the NRC to remove the conditions. Therefore, the
conditions are retained in Revision 39 of RG 1.84.
Code Case N-155-3 [Supplement 5, 2015 Edition]
Type: Revised.
Title: Fiberglass Reinforced Thermosetting Resin Pipe, Section III,
Division 1.
The conditions on Code Case N-155-3 are the same as the conditions
on N-155-2 that were approved by the NRC in Revision 38 of RG 1.84.
When the ASME revised N-155-2, the code case was not modified in a way
that would make it possible for the NRC to remove the conditions.
Therefore, the conditions are retained in Revision 39 of RG 1.84.
Code Case N-755-4 [Supplement 1, 2017 Edition]
Type: Revised.
Title: Use of Polyethylene (PE) Class 3 Plastic Pipe, Section III,
Division 1.
This code case is applicable only to butt fusion joints and the
content was incorporated into Mandatory Appendix XXVI in the 2015
Edition of Section III of the ASME Code. The relevant provisions of
Code Case N-755-4 are the same as those in Mandatory Appendix XXVI.
Therefore, the NRC is applying the same conditions to Code Case N-755-
4. The NRC has determined that these conditions are necessary to ensure
structural integrity of the polyethylene piping and fusion joints when
the polyethylene piping is used in Class 3 safety-related applications.
Code Case N-779 [Supplement 8, 2007 Edition]
Type: New.
Title: Alternative Rules for Simplified Elastic-Plastic Analysis
Class 1, Section III, Division 1.
The NRC finds the code case satisfactory and technically acceptable
for use only with code editions Summer 1979 and later. This code case,
as written, is not acceptable for use with editions of Section III
earlier than the Summer 1979 Edition, which included the term Delta T1
in NB-3600 Equation 10, because the code case is based on equations
used in the Summer 1979 Edition and later editions of the Code.
Code Case N-852 [Supplement 0, 2015 Edition]
Type: New.
Title: Application of the ASME NPT Stamp, Section III, Divisions 1,
2, 3, and 5.
The NRC approved this code case with a condition in a Sec. 50.55a
rulemaking issued in 2017 (82 FR 32934; July 18, 2017), and the
supplement was not modified in a way that would make it possible for
the NRC to remove the condition. Therefore, the condition is retained
in Revision 39 of RG 1.84.
Code Case N-883 [Supplement 5, 2017 Edition]
Type: New.
Title: Construction of Items Prior to the Establishment of a
Section III, Division 1 Owner, Section III, Division 1.
This code case allows certificate holders to construct all items
prior to the establishment of an Owner. Code Case N-883 was developed
to address international stakeholders and identify the ASME as a global
standard development organization. The NRC's main concern is that
without the designation of an Owner, the NRC would not be able to
provide regulatory oversight of the ASME certificate holder
manufacturing the items, which is not consistent with appendix B to 10
CFR part 50 and the requirements in Sec. 50.55(a) for a basic
component. During discussions with the ASME staff on this code case, it
was determined that the NRC would condition this code case based on
regulatory oversight, as would other regulatory bodies depending on
each countries' specific regulations. This is evident as this code case
specifies that the ``the items have been constructed by [ASME]
Certificate Holders who are specifically authorized by the Regulatory
Authority having jurisdiction over the Owner's facility to construct
items using this Case.'' The condition, ``This Code Case may be used
for the construction of items by a holder of a construction permit,
operating license, or combined license under 10 CFR part 50 or part
52,'' provides this specific regulatory authorization thereby ensuring
the appropriate regulatory oversight. As a result of public comment,
the NRC clarified the condition on the code case as follows: ``This
Code Case may only be used for the construction of items by a holder of
a construction permit, operating license, or combined license under 10
CFR part 50 or 10 CFR part 52. This Code Case may not be used by a
holder of a manufacturing license or standard design approval or by a
design certification applicant.''
Code Case N-886 [Supplement 6, 2017 Edition]
Type: New.
Title: Use of Polyethylene Pipe for Class 3, Section III, Division
1.
This code case is applicable for the use of polyethylene pipe in
Section III, Class 3, Division 1 above ground applications. This code
case refers to Mandatory Appendix XXVI of Section III of the ASME Code.
The 2015 Edition of Appendix XXVI contains requirements for butt fusion
joints for buried piping. The 2017 Edition of Appendix XXVI contains
requirements for butt fusion and electrofusion joints for buried
piping. Therefore, all the conditions as noted in Section III of the
2015-2017 Code Edition rule related to buried piping Mandatory Appendix
XXVI apply to this code case. The same conditions as buried piping also
apply to above ground application. One additional condition is needed
for above ground applications related to fire protection. A condition
on fire protection is needed because polyethylene material is
combustible and above ground uses are more susceptible to fire hazards.
The NRC agreed with the public comments to remove conditions 1, 2,
and 3 because the three conditions are the same as those for Section
III, Mandatory Appendix XXVI, which was conditionally accepted by the
NRC in Sec. 50.55a. It is redundant to specify these conditions to
Code Case N-886.
As a result of public comment, the NRC clarified condition 4 to
state that for aboveground applications, licensees must ensure that
plant fire protection program addresses any high-density polyethylene
(HDPE) consistent with the requirements of 10 CFR 50.48. The licensee
must identify the specific program to satisfy this objective such as
the plant fire protection program. Therefore, the condition is retained
in Revision 39 of RG 1.84.
The NRC agreed with the public comment to remove condition 5
because the requirement that carbon black distribution in HDPE pipe to
be homogenous to prevent windows and delamination is a pipe
manufacturing process issue. The staff determined that the requirements
in Mandatory Appendix XXVI-2231(b) adequately address this issue. Code
Case N-886 is only for design, and all materials must meet the
requirements of Appendix XXVI.
2. ASME BPV Code, Section XI Code Cases (RG 1.147)
Code Case N-513-5 [Supplement 6, 2017 Edition]
Type: Revised.
Title: Evaluation Criteria for Temporary Acceptance of Flaws in
Moderate Energy Class 2 or 3 Piping and Gate Valves, Section XI,
Division 1.
Code Case N-513-5 contains provisions to permit temporary
[[Page 11941]]
acceptance of flaws, in moderate energy Class 2 or 3 piping, including
elbows, pipe bends, reducers, expanders, branch tees, and gate valves
without performing a repair/replacement activity for a limited period.
The code case contains provisions regarding the scope, flaw
characterization, periodic leakage monitoring, flaw evaluation, and
augmented examinations. The NRC finds that the provisions of N-513-5
are acceptable except that the augmented examination provisions in
Section 5 of the code case require clarification.
When a licensee applies N-513-5 to disposition a through-wall leak
or wall thinning in a piping system, Section 5 of the code case
requires augmented examinations for flaws and significant flaws. The
augmented examination requirements in N-513-5 are the same as in Code
Case N-513-3.
In 2018, the NRC found an instance where a licensee misinterpreted
the provisions in Section 5 of N-513-3 and did not perform the required
augmented examinations to disposition a through-wall leak in a service
water system pipe. Other licensees have similarly misinterpreted the
augmented examination provisions in Section 5 of N-513-3. The NRC found
that the issue stems from the definition of the terms ``flaw'' and
``significant flaw'' in Sections 5(b) and 5(c) of N-513-3,
respectively. The NRC, therefore, imposes two conditions to define
``flaw'' and ``significant flaw'' as those terms are used in Section 5
of N-513-5. Licensees would be required to apply these definitions to
Section 5 when using the code case.
The first condition defines a ``flaw'' as a non-through-wall planar
or nonplanar flaw with a wall thickness less than 87.5 percent of the
nominal wall thickness of the pipe or the design minimum wall
thickness. The NRC notes that the pipe wall thickness at the time of
the plant construction may deviate from the nominal pipe wall thickness
slightly as part of manufacturing process. The generally accepted
deviation is 12.5 percent of the nominal pipe wall thickness or the
design minimum wall thickness.
The second condition defines ``significant flaw'' as any pipe
location that does not satisfy the provisions of Section 3 of N-513-5
or if any detected flaw that has a depth greater than 75 percent of the
pipe wall thickness. The NRC staff notes that the criterion of the 75
percent wall thickness criterion originates from the provisions of IWC/
IWD-3643 of the ASME Code, Section XI, which prohibits a flaw that
exceeds 75 percent of the pipe wall thickness to remain in service.
Under Section 5 of N-513-5, a planar flaw that exceeds 75 percent of
the pipe wall thickness may remain in service; however, the licensee
must perform an augmented examination. The NRC agreed with the public
comment that Condition 2 needed clarification. As a result, the NRC
revised Condition No. 2 as follows: ``For the purposes of section 5 of
Code Case N-513-5, the term ``significant flaw'' means any flaw found
during augmented examinations performed per Section 5 of N-513-5 that
has a depth greater than 75 percent of the pipe wall thickness or that
does not satisfy the applicable requirements of the flaw evaluation per
Section 3 of N-513-5. If a significant flaw as defined above is
present, then the licensee must perform the additional augmented
examination specified in Section 5.''
Code Case N-516-5 [Supplement 6, 2015 Edition]
Type: Revised.
Title: Underwater Welding, Section XI, Division 1.
In the rulemaking for the 2009 Addenda through 2013 Editions of the
ASME Code (82 FR 32934; September 18, 2017), the NRC-specified
conditions that should be applied to Section XI, Article IWA-4660 when
performing underwater welding on irradiated materials. These conditions
provide guidance on what level of neutron irradiation and/or helium
content would require review and approval by the NRC because of the
impact of neutron fluence on weldability. These conditions provide
separate criteria for three generic classes of material: Ferritic
material, austenitic material other than P-No. 8 (e.g., nickel-based
alloys) and austenitic P-No. 8 material (e.g., stainless steel alloys).
These conditions are currently located in Sec. 50.55a(b)(2)(xii)(A)
and (B). The conditions located in Sec. 50.55a(b)(2)(xii)(A) and (B)
are identical to the conditions that were imposed on Code Case N-516-4
that were approved by the NRC in Revision 19 of RG 1.147. When the ASME
revised N-516, the code case was not modified in a way that would make
it possible for the NRC to remove the conditions. Therefore, the
conditions are retained in Revision 20 of RG 1.147 by stating the
provisions of Sec. 50.55a(b)(2)(xii)(A) and (B) must be met when
applying this code case.
Code Case N-597-3 [Supplement 5, 2013 Edition]
Type: Revised.
Title: Evaluation of Pipe Wall Thinning, Section XI.
Based on public comments, the NRC found that existing Condition
2(b) references Figure-3622.1(a)(1), which does not exist in Code Case
N-597-3. The NRC revised Condition 2(b) in the final rule to reference
Figure 3622-1 of the code case.
Code Case N-705-1 [Supplement 2, 2017 Edition]
Type: Revised.
Title: Evaluation Criteria for Temporary Acceptance of Degradation
in Moderate Energy Class 2 or 3 Vessels and Tanks, Section XI, Division
1.
The condition on Code Case N-705-1 is identical to the condition on
N-705 that was approved by the NRC in Revision 19 of RG 1.147. When the
ASME revised N-705, the code case was not modified in a way that would
make it possible for the NRC to remove the condition. Therefore, the
condition is retained in Revision 20 of RG 1.147.
Code Case N-766-3 [Supplement 2, 2017 Edition]
Type: Revised.
Title: Nickel Alloy Reactor Coolant Inlay and Onlay for Mitigation
of Pressurized Water Reactor (PWR) Full Penetration Circumferential
Nickel Alloy Dissimilar Metal Welds in Class 1 Items, Section XI,
Division 1.
The conditions on Code Case N-766-3 are identical to the conditions
on N-766-1 that were approved by the NRC in Revision 19 of RG 1.147.
When the ASME revised N-766, the code case was not modified in a way
that would make it possible for the NRC to remove the conditions.
Therefore, the conditions are retained in Revision 20 of RG 1.147.
Code Case N-778 [Supplement 0, 2010 Edition]
Type: New.
Title: Alternative Requirements for Preparation and Submittal of
Inservice Inspection Plans, Schedules, and Preservice and Inservice
Inspection Summary Reports, Section XI, Division 1.
Code Case N-778 was originally listed in Table 2 of Revision 18 of
RG 1.147 with two conditions. As a result of public comments, the NRC
revised the second condition on Code Case N-778 to be consistent with
Code Case N-892 by increasing the time period for submittal of the
inservice inspection summary report to 120 days following the
completion of each refueling outage.
Code Case N-831-1 [Supplement 7, 2017 Edition]
Type: Revised.
Title: Ultrasonic Examination in Lieu of Radiography for Welds in
Ferritic or Austenitic Pipe, Section XI, Division 1.
[[Page 11942]]
The condition on Code Case N-831-1 is identical to the condition on
N-831 that was approved by the NRC in Revision 19 of RG 1.147. When
ASME revised N-831, the code case was not modified in a way that would
make it possible for the NRC to remove the condition. Therefore, the
condition is retained in Revision 20 of RG 1.147.
Code Case N-847 [Supplement 0, 2017 Edition]
Type: New.
Title: Partial Excavation and Deposition of Weld Metal for
Mitigation of Class 1 Items, Section XI, Division 1.
The ASME Code Case N-847 provides guidelines for a repair/
mitigation process for welds. The process, excavation and weld repair
(EWR), removes susceptible material from the outside diameter of the
pipe, and replaces it with more resistant weld material. This technique
allows for the potential of two mitigation methods, the use of more
crack-resistant material and the potential for compressive stresses on
the inside surface of the repaired/mitigated weld to arrest or prevent
cracking. Finally, the excavation can be done 360-degrees around the
weld or only for a partial arc of the weld.
The code case would allow for application of this process to both
BWR and PWR designs. However, the EWR process, as defined in this code
case, has certain challenges addressing the cracking mechanisms in
these operating environments and materials. In addition, the regulatory
requirements or guidelines related to the code case vary depending on
the design of the reactor. For PWR designs, the inservice inspection
rules are provided by Sec. 50.55a(g)(6)(ii)(F), which mandates the
implementation of a version of ASME Code Case N-770-5. For BWR designs,
the inservice inspection guidelines are provided by Generic Letter 88-
01, ``NRC Position on Intergranular Stress Corrosion Cracking (IGSCC)
in BWR Austenitic Stainless Steel Piping,'' or BWRVIP-75-A, ``BWR
Vessel and Internals Project Technical Basis for Revisions to Generic
Letter 88-01 Inspection Schedules.'' Therefore, the NRC is imposing six
conditions to ensure the inservice inspection frequency guidelines of
the code case are consistent with the previous requirements and
guidance, which are based on the effectiveness of the overall design of
the repair/mitigation to address the various cracking mechanisms of
these operating reactor designs.
The first condition is a continuation of the condition of Sec.
50.55a(g)(6)(ii)(F)(16), which requires that a partial arc EWR, as
described in Inspection Item O of ASME Code Case N-770-5, cannot be
used without NRC review and approval for PWR designs. The NRC notes
that the issues addressed in the final rule incorporating by reference
the 2015 and 2017 Editions of the ASME BPV Code and the 2015 and 2017
Editions of the ASME OM Code remain applicable, and further apply to
BWR design application of a partial arc EWR. These concerns are for the
effectiveness of the repair through a weld residual stress calculation
and flaw growth analysis to confirm design of the mitigation for the
required inspection interval, non-destructive examination uncertainty
analysis of the as-found flaw remaining in the reactor coolant pressure
boundary, and the potential for further crack initiation or growth. The
NRC requires, through the first condition, that approval of the use of
this code case is only for the application of the 360-degree EWR.
The second condition is related to Figure 1A and Figure 1B of the
code case. The NRC has experience with relief request submittals, where
the details associated with the configuration of the prep area, where
the defect is being removed, have shown sharp bottom edges and steep
walls. This geometry can result in welding issues, which could result
in unfused material, leading to stress risers, which may promote
cracking. The NRC requires, through the second condition, that the
intersection points at the interface between EWR metal and existing
base metal must be rounded to minimize stress concentration.
The third condition is related to Section 2(d) of the code case,
which discusses the flaw evaluations required for the design
considerations of the EWR. In recent testing conducted for the NRC
measurable stress corrosion cracking (SCC) growth was detected past the
interface between the SCC-susceptible and less susceptible material. It
was demonstrated that the crack can branch and propagate in a direction
normal to the original direction along a SCC-susceptible path. In the
Alloy 52M deposited onto Alloy 182 specimens tested, this occurred in
the diluted region of the Alloy 52M material as well as the weld metal.
The NRC requires, through the third condition, that flaw analysis
include the potential for crack growth through the dilution zone
including crack branching. As NRC-approved crack growth rates are not
available for all material types (e.g., Alloy 690 weld material), the
alternative requirements for development of crack growth rates should
be consistent with ASME Section XI Appendix C, ``Flaw Growth Rate Due
to Stress Corrosion Cracking,'' C-3220(a). As a result of public
comment, the NRC agrees this condition should be updated to reference
Section 2(d)(1), rather than 2(d)(2) as discussed in the proposed rule
(86 FR 7820, February 2, 2021), for nickel-based alloys. The NRC
clarified the condition to state the evaluation in Section 2(d)(1) of
the code case must include evaluation of crack growth into the Alloy
690 weld material, including the dilution zones and allowing change in
flaw growth direction.
The fourth condition is related to Section 2 of the code case. The
NRC is requiring the use of NUREG-2228, because it provides a proven
method for validating the weld residual stress analysis methodology.
Because the NRC requires the use of NUREG-2228 within this condition on
the requirements in the code case, the NRC is incorporating by
reference NUREG-2228 into Sec. 50.55a(a)(3)(iv).
The fifth condition is related to the longer-term volumetric
inspection frequencies of Table 1, including notes (1), (3), and (4).
These notes provide the BWR design inspection frequency of various EWR
types based on Generic Letter 88-01 (1988) as supplemented by Generic
Letter 88-01, Supplement 1 (1992), ``NRC Position on Intergranular
Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel
Piping,'' or BWRVIP-75-A, ``BWR Vessel and Internals Project Technical
Basis for Revisions to Generic Letter 88-01 Inspection Schedules.'' The
NRC has concluded that the inspection requirements for EWRs for BWRs
need to be augmented.
The first volumetric examination following application of BWR EWR-
2A, EWR-1B, and EWR-2B welds is performed to verify effectiveness of
the repair/mitigation before the new weld can be placed in a longer-
term volumetric inspection frequency. The code case allows licensees
the option of performing this examination during the first or second
refueling outage after installation. However, based on the lower
operating temperatures of a BWR (approximately 546 [deg]F to 558
[deg]F), and hence the potential slow crack growth rate of the
remaining flaw left in service, the NRC has concluded that the
examination should occur during the second refueling outage after the
EWR application to provide adequate time for any potential measurable
flaw growth to occur or in the case of an EWR-2A, for crack initiation
and growth to occur.
The long-term volumetric inspections for BWRs require modification
because: (a) For EWR-1A EWRs, the augmented
[[Page 11943]]
inspection requirements are consistent with the conditions of the
inspection frequencies of Code Case N-770-5. These inspection frequency
requirements were previously developed by the NRC based on the
capabilities of the EWR process to address stress corrosion cracking
while providing significant credit for the use of hydrogen water
chemistry/noble metal chemical addition controls; and (b) for EWR-1B
EWRs, the design that would allow a crack to be left in service, should
not be allowed to go uninspected for the remainder of plant life.
Therefore, the NRC requires the long-term volumetric inspection of
these welds at each 10-year inservice inspection interval. The NRC
notes that this condition is consistent with the NRC condition
established in Sec. 50.55a for Inspection Item N-1 EWRs (EWR that
meets stress criteria; however, a crack is present).
The sixth condition is related to Table 1, Note (1), and the option
to use an unspecified alternative to determine examination frequencies
and scope expansion criteria. Note (1) specifies the use of NRC Generic
Letter 88-01 and includes BWRVIP-75-A as an example of an alternative.
The NRC has concluded that NRC Generic Letter 88-01 (1988), as
supplemented by Generic Letter 88-01, Supplement 1 (1992), or BWRVIP-
75-A, are acceptable, subject to the fifth condition, to determine
examination frequencies and scope expansion criteria. However, Note (1)
would allow the use of other, unknown alternatives and does not provide
criteria to ensure alternatives are adequate for this purpose.
Therefore, to ensure that licensees use an adequate standard to
determine examination frequencies and scope expansion criteria, the
sixth condition requires that licensees must not use an alternative
other than those specified in Note (1).
Code Case N-864 [Supplement 2, 2017 Edition]
Type: New.
Title: Reactor Vessel Threads in Flange Examinations, Section XI,
Division 1.
Code Case N-864 eliminates the required ASME Code, Section XI
examination for the reactor vessel threads-in-flange for all inservice
inspection intervals. The NRC has previously granted alternatives under
Sec. 50.55a(z) that eliminate the reactor pressure vessel threads-in-
flange examinations (ASME Section XI, Examination Category B-G-1, Item
No. B6.40) for up to two inservice inspection intervals through the
NRC's alternative request process. For alternatives that requested
elimination of the examination for a second consecutive 10-year
inservice inspection interval, the NRC has been requesting additional
information on activities performed to ensure that the condition of the
reactor pressure vessel threads-in-flange receives some level of
monitoring. These activities typically have included care and
maintenance of the reactor vessel threads-in-flange (and studs)
whenever the closure head is removed. The NRC has limited approval of
such requests to two subsequent inservice inspection intervals because
the NRC has determined that complete elimination of the examinations
does not provide adequate protection against long-term degradation of
the threads-in-flange. The NRC is imposing conditions on the use of
Code Case N-864 that are consistent with the limits the NRC has placed
on similar alternatives requests.
The first condition in Code Case N-864 requires that the reactor
pressure vessel threads-in-flange examinations (ASME Section XI,
Examination Category B-G-1, Item No. B6.40) must be performed in at
least every third 10-year ISI interval. This condition also limits the
application of Code Case N-864 at facilities that have been authorized
under Sec. 50.55a(z) to use alternatives that eliminate reactor
pressure vessel threads-in-flange examinations to ensure that the
required examination is performed at least every third 10-year
inservice inspection interval.
The second condition in Code Case N-864 ensures that sufficient
monitoring and maintenance activities are performed and documented when
the code case is applied. As a result of public comments, the NRC
clarified that performing and documenting the facility's maintenance
procedures for removal, care, and visual inspection of the reactor head
closure studs and threads in flange during each refueling outage are
sufficient to satisfy the second condition.
Code Case N-869 [Supplement 6, 2017 Edition]
Type: New.
Title: Evaluation Criteria for Temporary Acceptance of Flaws in
Class 2 or 3 Piping, Section XI, Division 1.
Code Case N-869 contains provisions for temporary acceptance of
flaws, including through-wall flaws in Class 2 or 3 piping including
elbows, pipe bends, reducers, and branch tees, whose maximum operating
pressure is greater than 275 psig and does not exceed 600 psig, without
performing a repair/replacement activity. The code case contains
provisions regarding the scope, flaw characterization, periodic leakage
monitoring, flaw evaluation, and augmented examinations. The NRC finds
that the code case provides reasonable assurance that structural
integrity of degraded piping will be maintained until the next
scheduled refueling outage. However, the NRC finds that the augmented
examination provisions in Section 5 of the code case are unclear and
need additional clarification.
When a licensee applies N-869 to disposition a through-wall leak or
wall thinning in a piping system, Section 5 of the code case requires
augmented examinations for flaws and significant flaws. The augmented
examination requirements in N-869 are the same as in Code Case N-513-3.
In 2018, the NRC found an instance where a licensee misinterpreted
the provisions in Section 5 of N-513-3 and did not perform the required
augmented examinations to disposition a through-wall leak in a service
water system pipe. Other licensees have similarly misinterpreted the
augmented examination provisions in Section 5 of N-513-3. The NRC found
that the issue stems from the definition of the terms ``flaw'' and
``significant flaw'' in Sections 5(b) and 5(c) of N-513-3,
respectively. The NRC, therefore, imposes two conditions to define
``flaw'' and ``significant flaw'' as those terms are used in Section 5
of N-869. Licensees would be required to apply these definitions to
Section 5 when using the code case.
The first condition defines a ``flaw'' as a non-through-wall planar
or nonplanar flaw with a wall thickness less than 87.5 percent of the
nominal wall thickness of the pipe or the design minimum wall
thickness. The NRC notes that the pipe wall thickness at the time of
the plant construction may deviate from the nominal pipe wall thickness
slightly as part of manufacturing process. The generally accepted
deviation is 12.5 percent of the nominal pipe wall thickness or the
design minimum wall thickness.
The second condition defines ``significant flaw'' as any pipe
location that does not satisfy the provisions of Section 3 of N-869 or
if any detected flaw that has a depth greater than 75 percent of the
pipe wall thickness. The NRC staff notes that the 75 percent wall
thickness criterion originates from the provisions of IWC/IWD-3643 of
the ASME Code, Section XI, which prohibit a flaw that exceeds 75
percent of the pipe wall thickness to remain in service. Under Section
5 of N-869, a planar flaw that exceeds 75 percent of the pipe wall
[[Page 11944]]
thickness may remain in service; however, the licensee needs to perform
an augmented examination.
Code Case N-876 [Supplement 2, 2017 Edition]
Type: New.
Title: Austenitic Stainless Steel Cladding and Nickel Base Cladding
Using Ambient Temperature Automatic or Machine Dry Underwater Laser
Beam Welding (ULBW) Temper Bead Technique, Section XI, Division 1.
Some irradiated stainless steel reactor vessel internal components
are susceptible to experiencing irradiation assisted stress corrosion
cracking. Code Case N-876 provides guidelines for repair welding the
irradiated stainless steel components inside the reactor vessel. Code
Case N-876 provides an alternative to the cladding temper bead repair
rules of Section XI, IWA-4400, which requires preheat and postweld heat
treatment. This alternative establishes new rules governing ambient
temperature temper bead cladding repairs using the ULBW process.
The NRC is imposing two conditions on this code case. The first
condition that must be applied when performing ULBW on irradiated
materials provides guidance on what level of neutron irradiation and/or
helium content would require review and approval by the NRC because of
the impact of neutron fluence on weldability. The second condition
limits the depth of the cladding repair due to concerns with the
fracture toughness of the base metal.
The technical basis for imposing conditions on the welding of
irradiated materials are that neutrons can generate helium atoms within
the metal lattice through transmutation of various isotopes of boron
and/or nickel. At high temperatures, such as occurs during welding,
these helium atoms rapidly diffuse though the metal lattice, coalescing
and forming helium bubbles at the grain boundaries. In sufficient
concentration, these helium bubbles can cause grain boundary cracking
that occurs in the fusion zones and heat affected zones during the
heat-up/cooldown cycle.
The first condition applies conditions already applicable to Code
Case N-516-5 ``Underwater Welding Section XI, Division 1,'' that the
provisions of Sec. 50.55a(b)(2)(xii)(A) and (B) must be met. This
regulation provides limits on specific levels of neutron irradiation
and/or helium content, above which welding is prohibited without prior
NRC review and approval. The NRC is imposing the same condition to uses
of Code Case N-876.
The second condition is necessary because the code case does not
require impact testing of the base metal heat affected zone (HAZ) to
verify adequate fracture toughness. The code case allows the depth of
the repair cavity into the ferritic base metal to be up to \1/4\''.
This would allow welding directly to the base metal; thus, it will
affect the fracture toughness of the base metal in the HAZ. Therefore,
the NRC is imposing a condition restricting the use of the code case to
repairs where at least \1/8\'' of cladding remains. The basis for the
\1/8\'' limit is that this amount of austenitic material between the
ferritic base metal and the first weld layer has generally been
considered to sufficiently limit the heat input to the base metal such
that deleterious effects on the fracture toughness will not occur;
therefore, impact testing of the base metal is not necessary. The NRC
notes that Code Case N-803, which is approved without conditions,
allows repair of ferritic base material using nonferritic weld filler
material based on welding procedure qualifications performed using
tensile tests, side bends, and impact tests, and could be used to
perform a cladding repair in which excavation into the base metal is
required.
Code Case N-878 [Supplement 1, 2017 Edition]
Type: New.
Title: Alternative to QA Program Requirements of IWA-4142, Section
XI, Division 1.
Code Case N-878 provides alternatives to the quality assurance
requirements in IWA-4142 for procurement of Class 1, 2, or 3 non-welded
fittings. This code case addresses the testing and certification of
material used in the manufacture of non-welded fittings, but does not
address how the licensee must ensure that the procured non-welded
fittings meet the design and testing requirements of the ASME Code,
Section III, NB/NC/ND-3671.7 for Class 1, 2, or 3 applications.
Verification that the Section III requirements for the design and
testing of these non-welded fittings have been met prior to use is
essential in ensuring the structural integrity of these Class 1, 2 and
3 systems is maintained. Therefore, the NRC is imposing conditions for
the licensee to verify the design and testing activities associated
with qualification of non-welded fittings required by Section III, NB/
NC/ND-3671.7 that are performed by the fabricator.
The first condition states for ASME Section III items, the Licensee
must review the fabricator's design documentation and methods to ensure
the fittings design is in compliance with the Licensee's design
specifications, and ASME Section III NB/NC/ND-3671.7 requirements; and
either (1) supervise and monitor the performance qualification tests of
the fittings to ensure the design is in compliance with the Licensee's
design specifications and ASME Section III NB/NC/ND-3671.7, or (2) the
Licensee or Repair/Replacement Organization conducts qualification
tests of the fittings or conducts design analyses to ensure the design
is in compliance with the Licensee's design specifications and ASME
Section III NB/NC/ND-3671.7. In response to public comments, the NRC
clarified that for ASME Section III items, this condition applies only
for those licensees that implemented ASME Code, Section III design
requirements for their original construction code and/or the licensees
that have upgraded their original design requirements to ASME Code,
Section III.
The second condition states that the Licensees must give the
Authorized Nuclear Inservice Inspector an opportunity to review the
design report prior to installation.
Code Case N-880 [Supplement 2, 2017 Edition]
Type: New.
Title: Alternative to Procurement Requirements of IWA-4143 for
Small Nonstandard Welded Fittings, Section XI, Division 1.
Code Case N-880 provides alternatives to the material procurement
requirements of IWA-4142 and IWA-4143 for small nonstandard welded
fittings. This code case does not address how the licensee must ensure
the procured welded fittings meet the design and testing requirements
of the ASME Code, Section III, NB/NC/ND-3671.7 for Class 1, 2, or 3
applications. Verification that the Section III requirements for the
design and testing of these welded fittings have been met prior to use
is essential in ensuring the structural integrity of these Class 1, 2
and 3 systems is maintained. Therefore, the NRC is imposing conditions
requiring the licensee to verify the design and testing activities
associated with qualification of welded fittings required by Section
III, NB/NC/ND-3671.7 that are performed by the fabricator.
The first condition states for ASME Section III items, the Licensee
must review the fabricator's design documentation and methods to ensure
the fittings design is in compliance with the Licensee's design
specifications, and ASME Section III NB/NC/ND-3671.7 requirements; and
either: (1) Supervise
[[Page 11945]]
and monitor the performance qualification tests of the fittings to
ensure the design is in compliance with the Licensee's design
specifications and ASME Section III NB/NC/ND-3671.7, or (2) the
Licensee or Repair/Replacement Organization conducts qualification
tests of the fittings or conducts design analyses to ensure the design
is in compliance with the Licensee's design specifications and ASME
Section III NB/NC/ND-3671.7. In response to public comments, the NRC
clarified that for ASME Section III items, this condition applies only
for those licensees that implemented ASME Code, Section III design
requirements for their original construction code and/or the licensees
that have upgraded their original design requirements to ASME Code,
Section III.
The second condition states that the Licensees must give the
Authorized Nuclear Inservice Inspector an opportunity to review the
design report prior to installation.
Code Case N-889 [Supplement 7, 2017 Edition]
Type: New.
Title: Reference Stress Corrosion Crack Growth Rate Curves for
Irradiated Austenitic Stainless Steel in Light-Water Reactor
Environments, Section XI, Division 1.
Code Case N-889 provides a new crack growth rate (CGR) law for
irradiation-assisted stress corrosion cracking. The code case is
applicable to wrought austenitic stainless steels and associated weld
metals, as well as cast austenitic stainless steels. The proposed CGR
law requires the user to first calculate irradiated yield stress from
the dose to the material. There are two yield stress models: One for
Molybdenum bearing stainless steels and one for stainless steels
without Molybdenum. Once irradiated yield stress has been determined,
the user calculates the CGR as a function of applied crack driving
force and temperature.
The staff identified three concerns with the technical basis of
this code case. The first concern relates to the limited CGR data at
dose levels greater than 20 displacements per atom (dpa). The proposed
CGR law indicates that the irradiated yield stress (and, consequently,
the CGR) increases with fluence up to a dose of 20 dpa, at which point
the irradiated yield's stress ceases to increase appreciably with
further dose accumulation. While the data at dose levels greater than
20 dpa does show a plateau behavior in the CGR, the staff's analyses of
that data suggests that areas of high CGR were averaged over the
industry calculation of CGR, which increases the uncertainty in the
high dose CGRs. Therefore, due to the limited data and the associated
high uncertainty at high fluence, the staff's confidence in CGRs at
dose levels greater than 20 dpa is low.
The second concern is the effects of uncertainty in the irradiated
yield strength value for an individual material-heat. This topic is
discussed in Section 4.7 of the technical basis report for Code Case N-
889. The NRC also conducted separate analyses. While the results of the
NRC's findings are generally consistent with the results in Section
4.7, the interpretation of their significance is not consistent. For
materials with yield strengths greater than 600 MPa (i.e., more highly-
irradiated materials), the expected CGR for a material with a yield
strength in the 95th percentile is less than two times the CGR
predicted by the code case, which is not a significant difference.
However, for materials with yield strength values less than 250 MPa
(i.e., unirradiated or minimally irradiated materials), the expected
CGR for a material in the 95th percentile can be more than five times
greater than the CGR predicted by the code case. Hence, the NRC's
concern is that the CGRs for individual low yield strength materials,
or materials with low fluence, could be significantly underpredicted by
the code case.
The final concern is related to the data used in the development of
the irradiated yield stress model. The methodology for addressing cold
work in this model was developed in MRP-135, Revision 1, while the
model itself was developed in MRP-211, Revision 0. The database
underlying the model included hundreds of yield strength measurements
on initially annealed and cold-worked Types 304, 316, and 347/348
stainless steel materials. However, most of the data were for annealed
Type 304 and cold-worked Type 316 stainless steels. Revision 1 of MRP-
211 contained additional yield strength data, including significantly
more data for cold-worked Types 304 and 347 stainless steel. The
authors of the code case, as documented in Section 4.5 of the
Additional Basis Report dated February 5, 2018, evaluated the code case
yield stress model with some of this additional data and found
agreement between the model and the additional data. However, the code
case authors excluded new data for cold-worked Type 304 and 347
stainless steel materials. Therefore, the technical basis document for
Code Case N-889 does not directly address whether cold-worked Type 304
and 347 (non-Molybdenum bearing) materials are adequately predicted by
the irradiated yield strength model in the code case. The NRC is
imposing three conditions on this code case.
The first condition states that this code case may not be applied
for neutron exposures greater than 20 dpa. This condition addresses the
NRC concern that there is sparse data with high uncertainty beyond 20
dpa. Given that the predicted CGR saturates at higher fluence, this
condition prevents potential underprediction of the CGR in this fluence
regime.
The second condition states that at dose levels below 0.75 dpa, the
user must use the higher of the Code Case N-889 or the Section XI,
Nonmandatory Appendix C, C-8520 CGR predictions. This condition
addresses the NRC concern related to possible underprediction of CGR in
Code Case N-889 for materials with calculated irradiated yield strength
less than 250 MPa.
The final condition states that the irradiated yield stress model
for cold-worked Molybdenum bearing materials must be used for cold-
worked non-Molybdenum bearing stainless steels (including Type 204 and
247 stainless steels). This condition addresses the NRC concern that
data for cold-worked non-Molybdenum bearing steels were not
appropriately considered during development of Code Case N-889. The NRC
performed its own evaluation of cold-worked Type 304 and 347 stainless
steels in the MRP-211 database and found that the yield strength was
better predicted by the code case's Molybdenum bearing model than with
the code case's non-Molybdenum bearing model.
Code Case N-890 [Supplement 0, 2019 Edition]
Type: New.
Title: Materials Exempted From G-2110(b) Requirements, Section XI,
Division 1.
Code Case N-890 provides an alternative to Section XI, G-2110(b)
which removes the requirement of, ``obtaining fracture toughness data
for at least three heats,'' for using the static fracture toughness
curve (Klc) curve for specific materials with a minimum
specified yield strength at room temperature between 50 kilopound per
square inch (ksi) and 90 ksi. Code Case N-890 would allow the toughness
of four ferritic steels (SA-508 Grade 2 Class 2, SA-508 Grade 3 Class
2, SA-533 Type A Class 2 and SA-533 Type B Class 2) with specified
minimum yield strength greater than 50 ksi to be characterized by
Figure G-2110-1 (i.e., the Section XI Klc curve).
[[Page 11946]]
The NRC identified one technical concern when reviewing the
technical basis of this code case. The technical basis provided
appropriate data to justify use of the Klc curve for several
materials listed in the code case. However, for SA-533 Type B, Class 2
materials, the NRC observed that in the technical basis document, there
is no fracture toughness data associated with the weld and heat
affected zone to support exclusion of the fracture toughness testing
requirements for these materials.
As such, the imposed NRC condition requires the user to comply with
the provisions of Section III, NB-2300 and Section III, G-2110(b) to
demonstrate the applicability of the ASME Klc curve to SA-
533 Type B, Class 2 material. These provisions require the user to
generate the necessary toughness data to demonstrate that the ASME
KIC curve is a conservative representation of the actual
material toughness.
3. ASME Operation and Maintenance Code Cases (RG 1.192)
Code Case OMN-1, Revision 2 [2020 Edition]
Type: Reaffirmed.
Title: Alternative Rules for Preservice and Inservice Testing of
Active Electric Motor-Operated Valve Assemblies in Light-Water Reactor
Power Plants.
The conditions on Code Case OMN-1, Revision 2 [2020 Edition] are
identical to the conditions on OMN-1, Revision 2 [2017 Edition] that
were approved by the NRC in Revision 3 of RG 1.192. The OMN-1, Revision
2 was reaffirmed by the ASME in the 2020 Edition with no change to the
code case. Therefore, the conditions are retained in Revision 4 of RG
1.192.
Code Case OMN-3 [2020 Edition]
Type: Reaffirmed.
Title: Requirements for Safety Significance Categorization of
Components Using Risk Insights for Inservice Testing of LWR Power
Plants.
The conditions on Code Case OMN-3 [2020 Edition] are identical to
the conditions on OMN-3 [2017 Edition] that were approved by the NRC in
Revision 3 of RG 1.192. The OMN-3 was reaffirmed by the ASME in the
2020 Edition with no change to the code case. Therefore, the conditions
are retained in Revision 4 of RG 1.192.
Code Case OMN-4 [2020 Edition]
Type: Reaffirmed.
Title: Requirements for Risk Insights for Inservice Testing of
Check Valves at LWR Power Plants.
The conditions on Code Case OMN-4 [2020 Edition] are identical to
the conditions on OMN-4 [2017 Edition] that were approved by the NRC in
Revision 3 of RG 1.192. The OMN-4 was reaffirmed by the ASME in the
2020 Edition with no change to the code case. Therefore, the conditions
are retained in Revision 4 of RG 1.192.
Code Case OMN-9 [2020 Edition]
Type: Reaffirmed.
Title: Use of a Pump Curve for Testing.
The conditions on Code Case OMN-9 [2020 Edition] are identical to
the conditions on OMN-9 [2017 Edition] that were approved by the NRC in
Revision 3 of RG 1.192. The OMN-9 was reaffirmed by the ASME in the
2020 Edition with no change to the code case. Therefore, the conditions
are retained in Revision 4 of RG 1.192.
Code Case OMN-12 [2020 Edition]
Type: Reaffirmed.
Title: Alternative Requirements for Inservice Testing Using Risk
Insights for Pneumatically and Hydraulically Operated Valve Assemblies
in Light-Water Reactor Power Plants (OM-Code 1998, Subsection ISTC).
The conditions on Code Case OMN-12 [2020 Edition] are identical to
the conditions on OMN-12 [2017 Edition] that were approved by the NRC
in Revision 3 of RG 1.192. The OMN-12 was reaffirmed by the ASME in the
2020 Edition with no change to the code case. Therefore, the conditions
are retained in Revision 4 of RG 1.192.
Code Case OMN-19 [2020 Edition]
Type: Reaffirmed.
Title: Alternative Upper Limit for the Comprehensive Pump Test.
The conditions on Code Case OMN-19 [2020 Edition] are identical to
the conditions on OMN-19 [2017 Edition] that were approved by the NRC
in Revision 3 of RG 1.192. The OMN-19 was reaffirmed by the ASME in the
2020 Edition with no change to the code case. Therefore, the conditions
are retained in Revision 4 of RG 1.192.
Code Case OMN-20 [2020 Edition]
Type: Reaffirmed.
Title: Inservice Test Frequency.
The conditions on Code Case OMN-20 [2020 Edition] are identical to
the conditions on OMN-20 [2017 Edition] that were approved by the NRC
in Revision 3 of RG 1.192. The OMN-20 was reaffirmed by the ASME in the
2020 Edition with no change to the code case. Therefore, the conditions
are retained in Revision 4 of RG 1.192.
C. ASME Code Cases Not Approved for Use (RG 1.193)
The ASME code cases that are currently issued by the ASME, but not
approved for generic use by the NRC, are listed in RG 1.193, ``ASME
Code Cases not Approved for Use.'' In addition to the ASME code cases
that the NRC has found to be technically or programmatically
unacceptable, RG 1.193 includes code cases on reactor designs for high-
temperature gas-cooled reactors and liquid metal reactors, reactor
designs not currently licensed by the NRC, and certain requirements in
Section III, Division 2, for submerged spent fuel waste casks, that are
not endorsed by the NRC. RG 1.193 complements RGs 1.84, 1.147, and
1.192. It should be noted that the NRC is not adopting any of the code
cases listed in RG 1.193.
III. Opportunities for Public Participation
The proposed rule and draft RGs were published in the Federal
Register on February 2, 2021 (86 FR 7820), for a 60-day comment period.
The public comment period closed on April 5, 2021.
IV. Public Comment Analysis
The NRC published the proposed rule and draft regulatory guides for
public comment in the Federal Register. The NRC received 13 comment
submissions. A comment submission is a communication or document
submitted to the NRC by an individual or entity, with one or more
individual comments addressing a subject or issue. Private citizens
provided five comment submissions, nuclear industry organizations
provided five comment submissions, a foreign government entity provided
one comment submission, an anonymous commenter provided one comment
submission, and a science advocacy group provided one comment
submission.
The comment submissions generally addressed the code cases and
their proposed conditions, with five comment submissions objecting to
incorporation of a code case with no conditions in this rulemaking
activity. The NRC received a number of comments that were outside the
scope of this rulemaking, such as comments that discuss code cases
annulled after the publication of the supplements being considered in
this rulemaking. The latter group out of scope comments will be
considered in a future rulemaking.
The public comment submittals are available from the Federal e-
Rulemaking website at https://www.regulations.gov
[[Page 11947]]
under Docket ID NRC-2017-0025. The NRC prepared a summary and analysis
of public comments received on the 2020 proposed rule and draft
regulatory guides, which is available as indicated in the
``Availability of Documents'' section of this document. Responses to
the public comments, including a summary of how the final rule text or
guidance changed as a result of the public comments, can be found in
the public comment analysis.
For more information about the associated guidance documents, see
the ``Availability of Guidance'' section of this document.
V. Section-by-Section Analysis
The following paragraphs in Sec. 50.55a are revised:
Paragraph (a) Introductory Text
This final rule revises the last sentence to update the contact
information for the National Archives and Records Administration.
Paragraph (a)(1) Introductory Text
This final rule corrects a printing error by removing the line
break after ``telephone:''.
Paragraph (a)(3) Introductory Text
This final rule adds a reference to new paragraph (a)(3)(iv), which
indicates that NUREG-2228 is acceptable as specified in the conditions
when implementing code cases listed in certain NRC regulatory guides.
Paragraph (a)(3)(i)
This final rule revises the reference to ``NRC Regulatory Guide
1.84, Revision 38,'' by removing ``Revision 38'' and adding in its
place ``Revision 39'' and changes the month and year for the document's
revision date.
Paragraph (a)(3)(ii)
This final rule revises the reference to ``NRC Regulatory Guide
1.147, Revision 19'' by removing ``Revision 19'' and adding in its
place ``Revision 20'' and changes the month and year for the document's
revision date.
Paragraph (a)(3)(iii)
This final rule revises the reference to ``NRC Regulatory Guide
1.192, Revision 3'' by removing ``Revision 3'' and adding in its place
``Revision 4'' and changes the month and year for the document's
revision date.
Paragraph (a)(3)(iv)
This final rule adds new paragraph (a)(3)(iv) to reference NUREG-
2228, ``Weld Residual Stress Finite Element Analysis Validation: Part
II--Proposed Validation Procedure,'' Published July 2020 (including
Errata September 22, 2021), which is referenced in RG 1.147, Revision
20.
Paragraph (b)(1)(ii), Table 1
This final rule revises the reference to table 1 in the text of the
paragraph, and designates the table and revises the heading of the
table to conform to Office of the Federal Register (OFR) codification
requirements.
Paragraph (b)(2)(xv)(K)(4), Table 2
This final rule designates the table and revises the heading of the
table to conform to OFR codification requirements.
Paragraph (b)(3)(iv), Table 3
This final rule designates the table and revises the heading of the
table to conform to OFR codification requirements, and capitalizes the
word ``(Years)'' in two of the three column headings.
VI. Regulatory Flexibility Certification
As required by the Regulatory Flexibility Act (5 U.S.C. 605(b)),
the Commission certifies that this rule, if adopted, will not have a
significant economic impact on a substantial number of small entities.
This final rule affects only the licensing and operation of nuclear
power plants. The companies that own these plants do not fall within
the scope of the definition of ``small entities'' set forth in the
Regulatory Flexibility Act or the size standards established by the NRC
(Sec. 2.810).
VII. Regulatory Analysis
The NRC has prepared a regulatory analysis on this regulation. The
analysis examines the costs and benefits of the alternatives considered
by the NRC. The NRC did not receive public comments on the draft
regulatory analysis. The final regulatory analysis is available as
indicated in the ``Availability of Documents'' section of this
document.
VIII. Backfitting and Issue Finality
The provisions in this final rule allow licensees and applicants to
voluntarily apply NRC-approved code cases, sometimes with NRC-specified
conditions. The approved code cases are listed in three RGs that are
incorporated by reference into Sec. 50.55a. An applicant's or a
licensee's voluntary application of an approved code case does not
constitute backfitting, because there is no imposition of a new
requirement or new position.
Similarly, voluntary application of an approved code case by a 10
CFR part 52 applicant or licensee does not represent NRC imposition of
a requirement or action, and therefore is not inconsistent with any
issue finality provision in 10 CFR part 52. For these reasons, the NRC
finds that this final rule does not involve any provisions requiring
the preparation of a backfit analysis or documentation demonstrating
that one or more of the issue finality criteria in 10 CFR part 52 are
met.
IX. Plain Writing
The Plain Writing Act of 2010 (Pub. L. 111-274) requires Federal
agencies to write documents in a clear, concise, and well-organized
manner. The NRC has written this document to be consistent with the
Plain Writing Act as well as the Presidential Memorandum, ``Plain
Language in Government Writing,'' published June 10, 1998 (63 FR
31885).
X. Environmental Assessment and Final Finding of No Significant
Environmental Impact
The Commission has determined under the National Environmental
Policy Act of 1969, as amended, and the Commission's regulations in
subpart A of 10 CFR part 51, that this rule, if adopted, would not be a
major Federal action significantly affecting the quality of the human
environment; therefore, an environmental impact statement is not
required.
The determination of this environmental assessment is that there
will be no significant effect on the quality of the human environment
from this action. The NRC did not receive public comments regarding any
aspect of this environmental assessment.
As voluntary alternatives to the ASME Code, NRC-approved code cases
provide an equivalent level of safety. Therefore, the probability or
consequences of accidents is not changed. There are also no
significant, non-radiological impacts associated with this action
because no changes would be made affecting non-radiological plant
effluents and because no changes would be made in activities that would
adversely affect the environment. The determination of this
environmental assessment is that there will be no significant offsite
impact to the public from this action.
XI. Paperwork Reduction Act
This final rule amends collections of information subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The
collections of information were approved by the Office of Management
and Budget, approval number 3150-0011.
Because the rule will reduce the burden for existing information
collections, the public burden for the
[[Page 11948]]
information collections is expected to be decreased by 230 hours per
response. This reduction includes the time for reviewing instructions,
searching existing data sources, gathering and maintaining the data
needed, and completing and reviewing the information collection.
The information collection is being conducted to document the plans
for and the results of inservice inspection and inservice testing
programs. The records are generally historical in nature and provide
data on which future activities can be based. Information will be used
by the NRC to determine if ASME BPV and OM Code provisions for
construction, inservice inspection, repairs, and inservice testing are
being properly implemented in accordance with Sec. 50.55a of the NRC
regulations, or whether specific enforcement actions are necessary.
Responses to this collection of information are mandatory under Sec.
50.55a.
You may submit comments on any aspect of the information
collections, including suggestions for reducing the burden, by the
following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0025.
Mail comments to: FOIA, Library, and Information
Collections Branch, Office of the Chief Information Officer, Mail Stop:
T-6 A10M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001
or to the OMB reviewer at: OMB Office of Information and Regulatory
Affairs (3150-0011) Attn: Desk Officer for the Nuclear Regulatory
Commission, 725 17th Street NW, Washington, DC 20503; email:
[email protected].
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to
respond to, a collection of information unless the document requesting
or requiring the collection displays a currently valid OMB control
number.
XII. Congressional Review Act
This final rule is a rule as defined in the Congressional Review
Act (5 U.S.C. 801-808). However, the Office of Management and Budget
has not found it to be a major rule as defined in the Congressional
Review Act.
XIII. Voluntary Consensus Standards
The National Technology Transfer and Advancement Act of 1995,
Public Law 104-113, requires that Federal agencies use technical
standards that are developed or adopted by voluntary consensus
standards bodies unless using such a standard is inconsistent with
applicable law or is otherwise impractical. In this final rule, the NRC
is continuing to use the ASME BPV and OM code cases, which are ASME-
approved voluntary alternatives to compliance with various provisions
of the ASME BPV and OM Codes. The NRC's approval of the ASME code cases
is accomplished by amending the NRC's regulations to incorporate by
reference the latest revisions of the following, which are the subject
of this rulemaking, into Sec. 50.55a: RG 1.84, Revision 39; RG 1.147,
Revision 20; RG 1.192, Revision 4; and NUREG-2228. The RGs list the
ASME code cases that the NRC has approved for use. The ASME code cases
are national consensus standards as defined in the National Technology
Transfer and Advancement Act of 1995 and OMB Circular A-119. The ASME
code cases constitute voluntary consensus standards, in which all
interested parties (including the NRC and licensees of nuclear power
plants) participate.
XIV. Incorporation by Reference-Reasonable Availability to Interested
Parties
The NRC is incorporating by reference three NRC RGs that list new
and revised ASME code cases that the NRC has approved as voluntary
alternatives to certain provisions of NRC-required editions and addenda
of the ASME BPV Code and the ASME OM Code. These regulatory guides are
RG 1.84, Revision 39; RG 1.147, Revision 20; and RG 1.192, Revision 4.
The NRC is also incorporating by reference NUREG-2228, which is
referenced in RG 1.147, Revision 20. As described in this document,
this report pertains to a condition on Code Case N-847.
The NRC is required by law to obtain approval for incorporation by
reference from the OFR. The OFR's requirements for incorporation by
reference are set forth in 1 CFR part 51. The discussion in this
section complies with the requirement for final rules as set forth in 1
CFR 51.5(b)(2).
The NRC considers ``interested parties'' to include all potential
NRC stakeholders, not only the individuals and entities regulated or
otherwise subject to the NRC's regulatory oversight. These NRC
stakeholders are not a homogenous group, so the considerations for
determining ``reasonable availability'' vary by class of interested
parties. The NRC identified six classes of interested parties with
regard to the material to be incorporated by reference in an NRC rule:
Individuals and small entities regulated or otherwise
subject to the NRC's regulatory oversight. This class includes
applicants and potential applicants for licenses and other NRC
regulatory approvals, and who are subject to the material to be
incorporated by reference. In this context, ``small entities'' has the
same meaning as set out in Sec. 2.810.
Large entities otherwise subject to the NRC's regulatory
oversight. This class includes applicants and potential applicants for
licenses and other NRC regulatory approvals, and who are subject to the
material to be incorporated by reference. In this context, a ``large
entity'' is one that does not qualify as a ``small entity'' under Sec.
2.810.
Non-governmental organizations with institutional
interests in the matters regulated by the NRC.
Other Federal agencies, states, local governmental bodies
(within the meaning of Sec. 2.315(c)).
Federally-recognized and State-recognized Indian tribes.
Members of the general public (i.e., individual,
unaffiliated members of the public who are not regulated or otherwise
subject to the NRC's regulatory oversight) who need access to the
materials that the NRC proposes to incorporate by reference in order to
participate in the rulemaking.
The NUREG-2228 and three RGs that the NRC is incorporating by
reference in this final rule are available without cost and can be read
online or downloaded online. The NUREG-2228 and three RGs can be
viewed, by appointment, at the NRC Technical Library, which is located
at Two White Flint North, 11545 Rockville Pike, Rockville, Maryland
20852; telephone: 301-415-7000; email: [email protected].
Because access to NUREG-2228 and the three final regulatory guides
is available in various forms at no cost, the NRC determines that
NUREG-2228 and the three final regulatory guides, RG 1.84, Revision 39;
RG 1.147, Revision 20; and RG 1.192, Revision 4, once approved by the
OFR for incorporation by reference, are reasonably available to all
interested parties.
[[Page 11949]]
Table III--Regulatory Guides Incorporated by Reference in 10 CFR 50.55a
------------------------------------------------------------------------
ADAMS Accession
Document title No./ Federal
Register citation
------------------------------------------------------------------------
RG 1.84, Design, Fabrication, and Materials Code Case ML21181A225
Acceptability, ASME Section III, Revision 39........
RG 1.147, Inservice Inspection Code Case ML21181A222
Acceptability, ASME Section XI, Division 1, Revision
20..................................................
RG 1.192, Operation and Maintenance Code Case ML21181A223
Acceptability, ASME OM Code, Revision 4.............
------------------------------------------------------------------------
Table IV--Related Documents Incorporated by Reference in 10 CFR 50.55a
------------------------------------------------------------------------
ADAMS Accession
Document title No./ Federal
Register citation
------------------------------------------------------------------------
NUREG-2228, ``Weld Residual Stress Finite Element ML20212L592
Analysis Validation: Part II--Proposed Validation
Procedure,'' July 2020..............................
------------------------------------------------------------------------
XV. Availability of Guidance
The NRC is issuing revised guidance, RG 1.193, ``ASME Code Cases
Not Approved for Use,'' Revision 7, for the implementation of the
requirements in this final rule. The guidance is available as indicated
in Section XVI, ``Availability of Documents,'' of this document. You
may access information and comment submissions related to the guidance
by searching on https://www.regulations.gov under Docket ID NRC-2017-
0025.
The regulatory guide lists code cases that the NRC has not approved
for generic use and will not be incorporated by reference into the
NRC's regulations.
XVI. Availability of Documents
The documents identified in the following table are available to
interested persons through one or more of the following methods, as
indicated.
------------------------------------------------------------------------
ADAMS Accession
No./web link/
Document Federal Register
citation
------------------------------------------------------------------------
RG 1.84, Design, Fabrication, and Materials Code Case ML21181A225
Acceptability, ASME Section III, Revision 39,
December 2021.......................................
RG 1.147, Inservice Inspection Code Case ML21181A222
Acceptability, ASME Section XI, Division 1, Revision
20, December 2021...................................
RG 1.192, Operation and Maintenance Code Case ML21181A223
Acceptability, ASME OM Code, Revision 4, December
2021................................................
RG 1.193, ASME Code Cases Not Approved for Use, ML21181A224
Revision 7..........................................
NUREG-2228, ``Weld Residual Stress Finite Element ML20212L592
Analysis Validation: Part II-Proposed Validation
Procedure,'' July 2020..............................
Rulemaking-Proposed Rule-Draft Regulatory Analysis ML20133K152
for the American Society of Mechanical Engineers
Code Cases, RG 1.84, Rev 39; RG 1.147, Rev 20; RG
1.192 Rev 4.........................................
Rulemaking-Final Rule-Final Regulatory Analysis for ML21196A096
the American Society of Mechanical Engineers Code
Cases, RG 1.84, Rev 39; RG 1.147, Rev 20; RG 1.192
Rev 4...............................................
NRC Responses to Public Comments..................... ML21196A100
Proposed Rule-Approval of American Society of ML20132A241
Mechanical Engineers Code Cases RG 1.84, Rev 39; RG
1.147, Rev 20; RG 1.192 Rev 4.......................
Proposed Rule-Approval of American Society of 86 FR 7820
Mechanical Engineers Code Cases RG 1.84, Rev 39; RG
1.147, Rev 20; RG 1.192 Rev 4.......................
Final Rule-Approval of American Society of Mechanical 85 FR 14736
Engineers Code Cases RG 1.84, Rev 38; RG 1.147, Rev
19; RG 1.192 Rev 3..................................
------------------------------------------------------------------------
List of Subjects in 10 CFR Part 50
Antitrust, Classified information, Criminal penalties, Fire
protection, Incorporation by reference, Intergovernmental relations,
Nuclear power plants and reactors, Radiation protection, Reactor siting
criteria, Reporting and recordkeeping requirements.
For the reasons set out in the preamble and under the authority of
the Atomic Energy Act of 1954, as amended; the Energy Reorganization
Act of 1974, as amended; and 5 U.S.C. 552 and 553, the NRC is adopting
the following amendments to 10 CFR part 50:
PART 50--DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION
FACILITIES
0
1. The authority citation for part 50 continues to read as follows:
Authority: Atomic Energy Act of 1954, secs. 11, 101, 102, 103,
104, 105, 108, 122, 147, 149, 161, 181, 182, 183, 184, 185, 186,
187, 189, 223, 234 (42 U.S.C. 2014, 2131, 2132, 2133, 2134, 2135,
2138, 2152, 2167, 2169, 2201, 2231, 2232, 2233, 2234, 2235, 2236,
2237, 2239, 2273, 2282); Energy Reorganization Act of 1974, secs.
201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); Nuclear Waste
Policy Act of 1982, sec. 306 (42 U.S.C. 10226); National
Environmental Policy Act of 1969 (42 U.S.C. 4332); 44 U.S.C. 3504
note; Sec. 109, Pub. L. 96-295, 94 Stat. 783.
0
2. In Sec. 50.55a:
0
a. Revise the last sentence of paragraph (a) introductory text and
paragraphs (a)(1) introductory text and (a)(3) introductory text;
0
b. In paragraph (a)(3)(i):
0
i. Remove the text ``Revision 38'' and add in its place the text
``Revision 39''; and
0
ii. Remove the text ``dated October 2019'' and add in its place the
text ``issued December 2021'';
0
c. In paragraph (a)(3)(ii):
[[Page 11950]]
0
i. Remove the text ``Revision 19'' and add in its place the text
``Revision 20''; and
0
ii. Remove the text ``dated October 2019'' and add in its place the
text ``issued December 2021'';
0
d. In paragraph (a)(3)(iii):
0
i. Remove the text ``Revision 3'' and add in its place the text
``Revision 4''; and
0
ii. Remove the text ``dated October 2019'' and add in its place the
text ``issued December 2021'';
0
e. Add paragraph (a)(3)(iv);
0
f. In paragraph (b)(1)(ii), remove the text ``Table I of this section''
and add in its place the text ``table 1 to this paragraph (b)(1)(ii)'';
0
g. Designate the table immediately following paragraph (b)(1)(ii) as
table 1 to paragraph (b)(1)(ii) and revise the heading of the newly
designated table;
0
h. Designate the table immediately following paragraph (b)(2)(xv)(K)(4)
as table 2 to paragraph (b)(2)(xv)(K)(4) and revise the heading of the
newly designated table; and
0
i. Designate the table immediately following paragraph (b)(3)(iv) as
table 3 to paragraph (b)(3)(iv) and revise the heading and column
headings of the newly designated table.
The revisions and addition read as follows:
Sec. 50.55a Codes and standards.
(a) * * * For information on the availability of this material at
NARA, email [email protected] or go to www.archives.gov/federal-register/cfr/ibr-locations.html.
(1) American Society of Mechanical Engineers (ASME), Three Park
Avenue, New York, NY 10016; telephone: 1-800-843-2763; https://www.asme.org/Codes/.
* * * * *
(3) U.S. Nuclear Regulatory Commission (NRC) Public Document Room,
11555 Rockville Pike, Rockville, Maryland 20852; telephone: 1-800-397-
4209; email: [email protected]; https://www.nrc.gov/reading-rm/doc-collections/reg-guides/. The use of code cases listed in the NRC
regulatory guides in paragraphs (a)(3)(i) through (iii) of this section
is acceptable with the specified conditions in those guides when
implementing the editions and addenda of the ASME BPV Code and ASME OM
Code incorporated by reference in paragraph (a)(1) of this section. The
NRC report in paragraph (a)(3)(iv) of this section is acceptable as
specified in the conditions when implementing code cases listed in the
NRC regulatory guides in paragraphs (a)(3)(i) through (iii) of this
section.
* * * * *
(iv) NUREG-2228. NUREG-2228, ``Weld Residual Stress Finite Element
Analysis Validation: Part II--Proposed Validation Procedure,''
Published July 2020 (including Errata September 22, 2021), which is
referenced in RG 1.147, Revision 20.
* * * * *
(b) * * *
(1) * * *
(ii) * * *
Table 1 to Paragraph (b)(1)(ii)--Prohibited Code Provisions
* * * * *
(2) * * *
(xv) * * *
(K) * * *
(4) * * *
Table 2 to Paragraph (b)(2)(xv)(K)(4)--Table VIII: S7-1--Modified
* * * * *
(3) * * *
(iv) * * *
Table 3 to Paragraph (b)(3)(iv)--Maximum Intervals for Use When Applying
Interval Extensions
------------------------------------------------------------------------
Maximum interval Maximum interval
between activities between activities
Group size of member valves in of each valve in the
the groups (years) group (years)
------------------------------------------------------------------------
* * * * * * *
------------------------------------------------------------------------
* * * * *
Dated: January 25, 2022.
For the Nuclear Regulatory Commission.
Andrea D. Veil,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 2022-04374 Filed 3-2-22; 8:45 am]
BILLING CODE 7590-01-P