[Federal Register Volume 87, Number 207 (Thursday, October 27, 2022)]
[Rules and Regulations]
[Pages 65128-65157]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2022-23226]



[[Page 65127]]

Vol. 87

Thursday,

No. 207

October 27, 2022

Part II





 Nuclear Regulatory Commission





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10 CFR Part 50





American Society of Mechanical Engineers 2019-2020 Code Editions; Final 
Rule

  Federal Register / Vol. 87 , No. 207 / Thursday, October 27, 2022 / 
Rules and Regulations  

[[Page 65128]]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 50

[NRC-2018-0290]
RIN 3150-AK22


American Society of Mechanical Engineers 2019-2020 Code Editions

AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its 
regulations to incorporate by reference the 2019 Edition of the 
American Society of Mechanical Engineers Boiler and Pressure Vessel 
Code, Section III, Division 1, and Section XI, Division 1, and the 2020 
Edition of the American Society of Mechanical Engineers Operation and 
Maintenance of Nuclear Power Plants, Division 1: OM Code: Section IST, 
for nuclear power plants. The NRC is also incorporating by reference 
the American Society of Mechanical Engineers OM Code Case OMN-28, 
``Alternative Valve Position Verification Approach to Satisfy ISTC-3700 
for Valves Not Susceptible to Stem-Disk Separation''; the 2011 Addenda 
to ASME NQA-1-2008, ``Quality Assurance Requirements for Nuclear 
Facility Applications'' (ASME NQA-1b-2011); and the 2012 and 2015 
Editions of ASME NQA-1, ``Quality Assurance Requirements for Nuclear 
Facility Applications.'' This action is in accordance with the NRC's 
policy to periodically update the regulations to incorporate by 
reference new editions of the American Society of Mechanical Engineers 
Codes and is intended to maintain the safety of nuclear power plants 
and to make NRC activities more effective and efficient.

DATES: This final rule is effective on November 28, 2022. The 
incorporation by reference of certain publications listed in the 
regulation is approved by the Director of the Federal Register as of 
November 28, 2022.

ADDRESSES: Please refer to Docket ID NRC-2018-0290 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-2018-0290. 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, at 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 Public Document Room (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. (EST), Monday through Friday, except Federal holidays.

FOR FURTHER INFORMATION CONTACT: Caylee Kenny, Office of Nuclear 
Material Safety and Safeguards, telephone: 301-415-7150, email: 
[email protected]; or Michael Benson, Office of Nuclear Reactor 
Regulation, telephone: 301-415-2425, 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 NRC is amending its regulations to incorporate by reference the 
2019 Edition of the American Society of Mechanical Engineers (ASME) 
Boiler and Pressure Vessel Code (BPV Code) and the 2020 Edition of the 
ASME Operation and Maintenance of Nuclear Power Plants, Division 1: OM 
Code: Section IST (OM Code), for nuclear power plants. The NRC is also 
incorporating by reference the ASME OM Code Case OMN-28, ``Alternative 
Valve Position Verification Approach to Satisfy ISTC-3700 for Valves 
Not Susceptible to Stem-Disk Separation;'' the 2011 Addenda to ASME 
NQA-1-2008, ``Quality Assurance Requirements for Nuclear Facility 
Applications'' (ASME NQA-1b-2011); and the 2012 and 2015 Editions of 
ASME NQA-1, ``Quality Assurance Requirements for Nuclear Facility 
Applications.''
    ASME periodically revises and updates its codes for nuclear power 
plants by issuing new editions; this final rule is in accordance with 
the NRC's practice to incorporate those new editions into the NRC's 
regulations. This rule maintains the safety of nuclear power plants, 
makes NRC activities more effective and efficient, and allows nuclear 
power plant licensees and applicants to take advantage of the latest 
ASME Codes. ASME is a voluntary consensus standards organization, and 
ASME Codes are voluntary consensus standards. The NRC's use of the ASME 
Codes is consistent with applicable requirements of the National 
Technology Transfer and Advancement Act (NTTAA). See also Section XIV 
of this document, ``Voluntary Consensus Standards.''

B. Major Provisions

    Major provisions of this final rule include the incorporation by 
reference with conditions of the following ASME Codes and Code Case 
into NRC regulations and delineation of NRC requirements for the use of 
these Codes:

 The 2019 Edition of the BPV Code
 The 2020 Edition of the OM Code
 OM Code Case OMN-28, ``Alternative Valve Position Verification 
Approach to Satisfy ISTC-3700 for Valves Not Susceptible to Stem-Disk 
Separation''
 The 2011 Addenda to ASME NQA-1-2008, ``Quality Assurance 
Requirements for Nuclear Facility Applications,'' (ASME NQA-1b-2011) 
and the 2012 and 2015 Editions of ASME NQA-1.

C. Costs and Benefits

    The NRC prepared a regulatory analysis to determine the expected 
costs and benefits of this final rule. The regulatory analysis 
identifies costs and benefits in both a quantitative fashion as well as 
in a qualitative fashion.
    Based on the analysis, the NRC concludes that this final rule 
results in a net quantitative averted cost to the industry and the NRC. 
This final rule, relative to the regulatory baseline, would result in a 
net averted cost for industry of $10.2 million based on a 7 percent net 
present value (NPV) and

[[Page 65129]]

$11.0 million based on a 3 percent NPV. The estimated incremental 
industry averted cost per reactor unit ranges from $112,087 based on a 
7 percent NPV to $120,879 based on a 3 percent NPV. The rulemaking 
alternative benefits the NRC by averting costs for reviewing and 
approving requests to use alternatives to the Codes on a plant-specific 
basis under Sec.  50.55a(z) of title 10 of the Code of Federal 
Regulations (10 CFR). The NRC net benefit ranges from $0.91 million 
based on a 7 percent NPV to $0.99 million based on a 3 percent NPV.
    Qualitative factors that were considered include regulatory 
stability and predictability, regulatory efficiency, and consistency 
with the provisions of the NTTAA. The regulatory analysis includes a 
discussion of the costs and benefits that were considered 
qualitatively. If the results of the regulatory analysis were based 
solely on quantified costs and benefits, the regulatory analysis would 
show that the rulemaking is justified because the total quantified 
benefits of the regulatory action exceed the costs of the action. When 
the qualitative benefits (including the safety benefit and improvement 
in knowledge) are considered together with the quantified benefits, the 
benefits outweigh the identified quantitative and qualitative impacts.
    The NRC has had a decades-long practice of approving and/or 
mandating the use of certain parts of editions and addenda of these 
ASME Codes in Sec.  50.55a. Continuing this practice in this final rule 
ensures regulatory stability and predictability. This practice also 
provides consistency across the industry and provides assurance to the 
industry and the public that the NRC will continue to support the use 
of the most updated and technically sound techniques developed by ASME 
to provide adequate protection to the public. In this regard, the ASME 
Codes are voluntary consensus standards developed by technical 
committees composed of mechanical engineers and others who represent 
the broad and varied interests of their industries, from manufacturers 
and installers to insurers, inspectors, distributors, regulatory 
agencies, and end users. The standards have undergone extensive 
external review before being considered to be incorporated by reference 
by the NRC. Finally, the NRC's use of the ASME Codes is consistent with 
the NTTAA, which directs Federal agencies to adopt voluntary consensus 
standards instead of developing ``government-unique'' (i.e., Federal 
agency-developed) standards, unless inconsistent with applicable law or 
otherwise impractical.
    For more information, please see the regulatory analysis (Accession 
No. ML21267A092 in the NRC's Agencywide Documents Access and Management 
System (ADAMS)).

Table of Contents

I. Background
II. Discussion
    A. ASME BPV Code, Section III
    B. ASME BPV Code, Section XI
    C. ASME OM Code
III. Opportunities for Public Participation
IV. NRC Responses to Public Comments
    A. ASME BPV Code, Section XI
    B. ASME OM Code
V. Section-by-Section Analysis
VI. Generic Aging Lessons Learned Report
VII. Regulatory Flexibility Certification
VIII. Regulatory Analysis
IX. Backfitting and Issue Finality
X. Plain Writing
XI. Environmental Assessment and Final Finding of No Significant 
Environmental Impact
XII. Paperwork Reduction Act
XIII. Congressional Review Act
XIV. Voluntary Consensus Standards
XV. Incorporation by Reference--Reasonable Availability to 
Interested Parties
XVI. Availability of Guidance
XVII. Availability of Documents

I. Background

    The American Society of Mechanical Engineers (ASME) develops and 
publishes the ASME BPV Code, which contains requirements for the 
design, construction, and inservice inspection (ISI) of nuclear power 
plant components, and the ASME Operation and Maintenance of Nuclear 
Power Plants, Division 1: OM Code: Section IST (OM Code),\1\ which 
contains requirements for inservice testing (IST) of nuclear power 
plant components. Until 2012, ASME issued new editions of the ASME BPV 
Code every 3 years and addenda to the editions annually, except in 
years when a new edition was issued. Similarly, ASME periodically 
published new editions and addenda of the ASME OM Code. Starting in 
2012, the ASME decided to issue editions of its BPV and OM Codes 
(without addenda) every 2 years, with the BPV Code to be issued on the 
odd years (e.g., 2013, 2015, etc.) and the OM Code to be issued on the 
even years \2\ (e.g., 2012, 2014, etc.). The new editions typically 
revise provisions of the ASME Codes to broaden their applicability, add 
specific elements to current provisions, delete specific provisions, 
and/or clarify them to narrow the applicability of the provision. New 
editions of the ASME Codes do not significantly change code philosophy 
or approach.
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    \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 collectively in this rule as the 
``OM Code.''
    \2\ The 2014 Edition of the ASME OM Code was delayed and was 
designated the 2015 Edition. Similarly, the 2016 Edition of the OM 
Code was delayed and was designated the 2017 Edition.
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    The NRC's practice is to establish requirements for the design, 
construction, operation, ISI (examination), and IST of nuclear power 
plants by approving the use of editions and addenda of the ASME BPV and 
OM Codes (ASME Codes) in Sec.  50.55a of title 10 of the Code of 
Federal Regulations (10 CFR). The NRC approves or mandates the use of 
certain parts of editions and addenda of these ASME Codes in Sec.  
50.55a through the rulemaking process of ``incorporation by 
reference.'' Upon incorporation by reference of the ASME Codes into 
Sec.  50.55a, the provisions of the ASME Codes are legally binding NRC 
requirements as delineated in Sec.  50.55a, and subject to the 
conditions on certain specific ASME Codes' provisions that are set 
forth in Sec.  50.55a. The editions and addenda of the ASME BPV and OM 
Codes were last incorporated by reference into the NRC's regulations in 
a final rule dated May 4, 2020 (85 FR 26540) and amended June 3, 2020 
(85 FR 34087).
    The ASME Codes are consensus standards developed by participants, 
including the NRC and licensees of nuclear power plants, who have broad 
and varied interests. The ASME's adoption of new editions of, and 
addenda to, the ASME Codes does not mean that there is unanimity on 
every provision in the ASME Codes. There may be disagreement among the 
technical experts, including the NRC's representatives on the ASME Code 
committees and subcommittees, regarding the acceptability or 
desirability of a particular code provision included in an ASME-
approved Code edition or addenda. If the NRC believes that there is a 
significant technical or regulatory concern with a provision in an 
ASME-approved Code edition or addenda being considered for 
incorporation by reference, then the NRC conditions the use of that 
provision when it incorporates by reference that ASME Code edition or 
addenda into its regulations. In some instances, the condition 
increases the level of safety afforded by the ASME Code provision, or 
addresses a regulatory issue not considered by ASME. In other 
instances, where research data or experience has shown that certain 
code provisions are unnecessarily conservative, the condition may 
provide that the code provision need not be complied with in some or 
all respects. The NRC's

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conditions are included in Sec.  50.55a, typically in paragraph (b) of 
that section. NRC rulemakings adopting (incorporating by reference) a 
voluntary consensus standard identify and justify each part of the 
standard that is not adopted. For this final rule, the provisions of 
the 2019 Edition of Section III, Division 1; and the 2019 Edition of 
Section XI, Division 1, of the ASME BPV Code; and the 2020 Edition of 
the ASME OM Code that the NRC is not adopting, or is only partially 
adopting, are identified in the Discussion, Regulatory Analysis, and 
Backfitting and Issue Finality sections of this document. The 
provisions of those specific editions and the Code Case that are the 
subject of this final rule that the NRC finds to be conditionally 
acceptable, together with the applicable conditions, are also 
identified in the Discussion, Regulatory Analysis, and Backfitting and 
Issue Finality sections of this document.
    The ASME Codes are voluntary consensus standards, and the NRC's 
incorporation by reference of these Codes is consistent with applicable 
requirements of the NTTAA. Additional discussion on the NRC's 
compliance with the NTTAA is set forth in Section XIV of this document, 
``Voluntary Consensus Standards.''

II. Discussion

    The NRC regulations incorporate by reference ASME Codes for nuclear 
power plants. This final rule is the latest in a series of rulemakings 
to amend the NRC's regulations to incorporate by reference revised and 
updated ASME Codes for nuclear power plants. This final rule is 
intended to maintain the safety of nuclear power plants and make NRC 
activities more effective and efficient.
    The NRC follows a three-step process to determine acceptability of 
new provisions in new editions to the Codes and the need for conditions 
on the uses of these Codes. This process was employed in the review of 
the Codes that are the subjects of this rule. First, the NRC staff 
actively participates with other ASME committee members with full 
involvement in discussions and technical debates in the development of 
new and revised Codes. This includes a technical justification of each 
new or revised Code provision. Second, the NRC's committee 
representatives discuss the Codes and technical justifications with 
other cognizant NRC staff to ensure an adequate technical review. 
Third, the NRC position on each Code is reviewed and approved by NRC 
management as part of this rule amending Sec.  50.55a to incorporate by 
reference new editions of the ASME Codes and conditions on their use. 
This regulatory process, when considered together with the ASME's own 
process for developing and approving the ASME Codes, assures that the 
NRC approves for use only those new and revised Code edition and 
addenda, with conditions as necessary, that provide reasonable 
assurance of adequate protection to the public health and safety, and 
that do not have significant adverse impacts on the environment.
    The NRC is amending its regulations to incorporate by reference:
     The 2019 Edition to the ASME BPV Code, Section III, 
Division 1 and Section XI, Division 1, with conditions on their use.
     The 2020 Edition to Division 1 of the ASME OM Code, with 
conditions on its use.
     ASME OM Code Case OMN-28, ``Alternative Valve Position 
Verification Approach to Satisfy ISTC-3700 for Valves Not Susceptible 
to Stem-Disk Separation,'' without conditions.
     ASME Standard NQA-1, ``Quality Assurance Requirements for 
Nuclear Facility Applications,'' including several editions and addenda 
to NQA-1. More specifically, the NRC is incorporating by reference the 
2011 Addenda to ASME NQA-1b-2008, ``Quality Assurance Requirements for 
Nuclear Facility Applications'' (ASME NQA-1b-2011), and the 2012 and 
2015 Editions of ASME NQA-1, with conditions on their use.
    The current regulations in Sec.  50.55a(a)(1)(i) incorporate by 
reference ASME BPV Code, Section III, 1963 Edition through the 1970 
Winter Addenda; and the 1971 Edition (Division 1) through the 2017 
Edition (Division 1), subject to the conditions identified in current 
Sec.  50.55a(b)(1)(i) through (xii). This final rule revises Sec.  
50.55a(a)(1)(i) to incorporate by reference the 2019 Edition (Division 
1) of the ASME BPV Code, Section III.
    The current regulations in Sec.  50.55a(a)(1)(ii) incorporate by 
reference ASME BPV Code, Section XI, 1970 Edition through the 1973 
Winter Addenda; and the 1974 Edition (Division 1) through the 2017 
Edition (Division 1), subject to the conditions identified in the 
current Sec.  50.55a(b)(2)(i) through (xlii). This final rule revises 
Sec.  50.55a(a)(1)(ii) to incorporate by reference the 2019 Edition 
(Division 1) of the ASME BPV Code, Section XI. It also removes the 
incorporation by reference of older editions and addenda of Section XI 
prior to 2001 Edition that are no longer in use, and adds, removes, or 
revises some of the conditions as explained in the rule.
    The current regulations in Sec.  50.55a(a)(1)(iv) incorporate by 
reference ASME OM Code, 1995 Edition through the 2006 Addenda, and the 
2009 Edition (Division 1) through the 2017 Edition (Division 1), 
subject to the conditions currently identified in Sec.  50.55a(b)(3)(i) 
through (xi). This final rule revises Sec.  50.55a(a)(1)(iv) to 
incorporate by reference the 2020 Edition of Division 1 of the ASME OM 
Code. As explained in Section II.C of this document, this final rule 
also revises Sec.  50.55a(a)(1)(iv) to remove the incorporation by 
reference of the 2011 Addenda of the ASME OM Code as well as the 2015 
Edition of the ASME OM Code. This final rule also revises Sec.  
50.55a(a)(1)(iii) to add the incorporation by reference of the ASME OM 
Code Case OMN-28, which is referenced in paragraph (b)(3)(xi).
    The current regulations in Sec.  50.55a(a)(1)(v) incorporate by 
reference ASME NQA-1, 1983 Edition through the 2009 Addenda, subject to 
conditions identified in Sec.  50.55a(b)(1)(iv) and (b)(2)(x). This 
final rule revises Sec.  50.55a(a)(1)(v) to incorporate by reference 
the 2011 Addenda to ASME NQA-1-2008 (ASME NQA-1b-2011) and the 2012 and 
2015 Editions of ASME NQA-1.
    In the introductory discussion of its Codes, ASME specifies that 
errata to those Codes may be posted on the ASME website under the 
Committee Pages to provide corrections to incorrectly published items, 
or to correct typographical or grammatical errors in those Codes. Users 
of the ASME BPV Code and ASME OM Code should be aware of errata when 
implementing the specific provisions of those Codes. Applicants and 
licensees should monitor errata to determine when they might need to 
submit a request for an alternative under Sec.  50.55a(z) to implement 
provisions specified in an errata to their ASME code of record.
    The NRC reviewed changes to the Codes in the editions identified in 
this final rule, and published a proposed rule in the Federal Register 
setting forth the NRC's proposal to incorporate by reference the ASME 
Codes, together with proposed conditions on their use (86 FR 16087; 
March 26, 2021). The NRC also corrected minor editorial and 
administrative errors, including spacing and typos. After consideration 
of the public comments received on the proposed rule (public comments 
are discussed in Section IV of this document, ``NRC Responses to Public 
Comments''), the NRC concludes, in accordance with the process for 
review of changes to the Codes, that these

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editions of the Codes are technically adequate, consistent with current 
NRC regulations, and approved for use with the specified conditions set 
forth in this final rule. Each of the NRC conditions and the reasons 
for each condition are discussed in the following sections of this 
document. The discussions are organized under the applicable ASME Code 
and Section.

A. ASME BPV Code, Section III

Section 50.55a(a)(1)(i)(E) Rules for Construction of Nuclear Facility 
Components--Division 1
    The NRC is revising Sec.  50.55a(a)(1)(i)(E) to incorporate by 
reference the 2019 Edition of the ASME BPV Code, Section III, including 
Subsection NCA and Division 1 Subsections NB through NG and Appendices. 
As stated in Sec.  50.55a(a)(1)(i), the Nonmandatory Appendices are 
excluded and not incorporated by reference. The Mandatory Appendices 
are incorporated by reference because they include information 
necessary for Division 1. However, the Mandatory Appendices also 
include material that pertains to other Divisions that have not been 
reviewed and approved by the NRC. Although this information is included 
in the sections and appendices being incorporated by reference, the NRC 
notes that the use of Divisions other than Division 1 has not been 
approved, nor are they required by NRC regulations and, therefore, such 
information is not relevant to current applicants and licensees. The 
NRC is not taking a position on the non-Division 1 information in the 
appendices and is including it in the incorporation by reference only 
for convenience. Therefore, this final rule revises the introductory 
text to Sec.  50.55a(a)(1)(i)(E) to reference the 2019 Edition of the 
ASME BPV Code, Section III, including Subsection NCA and Division 1 
Subsections NB through NG and Appendices.
Section 50.55a(b)(1) Conditions on ASME BPV Code Section III
    The NRC is revising the definition of Section III in Sec.  
50.55a(b)(1) to include the latest edition of the ASME BPV Code, 
Section III incorporated by reference in paragraph (a)(1)(i).
Section 50.55a(b)(1)(ii) Section III Condition: Weld Leg Dimensions
    The NRC is revising Sec.  50.55a(b)(1)(ii) to extend the 
applicability of the condition through the latest edition of the ASME 
BPV Code, Section III incorporated by reference in paragraph (a)(1)(i). 
The 2019 Edition of Section III was not modified in a way that would 
make it possible for the NRC to remove this condition. Therefore, the 
NRC is revising this condition to apply to the latest edition 
incorporated by reference.
Section 50.55a(b)(1)(iv) Section III Condition: Quality Assurance
    The NRC is revising this condition to allow the use of the editions 
of NQA-1 that are both incorporated by reference in paragraph (a)(1)(v) 
of Sec.  50.55a and specified in either NCA-4000 or NCA-7000 of the 
1989 or later edition of Section III that is incorporated by reference 
in Sec.  50.55a. This will allow applicants and licensees to use the 
2011 Addenda to ASME NQA-1-2008, ``Quality Assurance Requirements for 
Nuclear Facility Applications'' (ASME NQA-1b-2011), and the 2012 and 
2015 Edition of NQA-1 when using the 2019 or later Edition of Section 
III, that is incorporated by reference in Sec.  50.55a.
Section 50.55a(b)(1)(vii) Section III Condition: Capacity Certification 
and Demonstration of Function of Incompressible-Fluid Pressure-Relief 
Valves
    The NRC is revising Sec.  50.55a(b)(1)(vii) to extend the 
applicability of the condition through the latest edition of the ASME 
BPV Code, Section III incorporated by reference in paragraph (a)(1)(i). 
The 2019 Edition of Section III was not modified in a way that would 
make it possible for the NRC to remove this condition. Therefore, the 
NRC is revising this condition to apply to the latest edition 
incorporated by reference.
Section 50.55a(b)(1)(x) Section III Condition: Visual Examination of 
Bolts, Studs, and Nuts
    The NRC is revising Sec.  50.55a(b)(1)(x) to extend the 
applicability of the condition through the latest edition of the ASME 
BPV Code, Section III incorporated by reference in paragraph (a)(1)(i). 
The 2019 Edition of Section III was not modified in a way that would 
make it possible for the NRC to remove this condition. Therefore, the 
NRC is revising this condition to apply to the latest edition 
incorporated by reference.
Section 50.55a(b)(1)(xiii) Section III Condition: Preservice Inspection 
of Steam Generator Tubes
    The NRC is adding a new condition Sec.  50.55a(b)(1)(xiii) to 
condition the provisions of NB 5283 in the 2019 Edition of Section III, 
which exempted steam generator tubing from preservice examinations. The 
condition is in two provisions as follows:
Section 50.55a(b)(1)(xiii)(A) Section III Condition: Preservice 
Inspection of Steam Generator Tubes, First Provision
    The NRC is adding a condition to require that a full-length 
preservice examination of 100 percent of the steam generator tubing in 
each newly installed steam generator be performed prior to plant 
startup. Preservice examinations provide a baseline for future required 
inservice examinations and provide assurance of its structural 
integrity and ability to perform its intended function. The 2019 
Edition does not require these preservice examinations to be performed. 
Therefore, the NRC is adding Sec.  50.55a(b)(1)(xiii)(A) to condition 
the provisions of NB-5283 in the 2019 Edition of Section III to require 
that preservice examination of steam generator tubing shall be 
performed, in order to ensure that the steam generator tubing which is 
part of the reactor coolant pressure boundary has an adequate baseline 
examination for future inservice examinations and ensures the tubing's 
structural integrity to perform its intended function.
Section 50.55a(b)(1)(xiii)(B) Section III Condition: Preservice 
Inspection of Steam Generator Tubes, Second Provision
    The provisions of NB-5360 in the 2019 Edition of Section III 
removed the requirements for eddy current preservice examination of 
installed steam generator tubing and the criteria for evaluating flaws 
found during the preservice examination. A preservice examination is 
important because it ensures that the steam generator tubes, which are 
part of the reactor coolant pressure boundary, are acceptable for 
initial operation. In addition, preservice examination provides the 
baseline condition of the tubes, which is essential in assessing the 
nature of indications found in the tubes during subsequent inservice 
examinations. These inspections must be performed with the objective of 
finding and characterizing the types of preservice flaws that may be 
present in the tubes and flaws that may occur during operation. 
Therefore, the NRC is adding Sec.  50.55a(b)(1)(xiii)(B) to condition 
the provisions of NB-5360 in the 2019 Edition of Section III, to 
require that flaws revealed during preservice examination of steam 
generator tubing shall be evaluated using the criteria in the design 
specifications.

[[Page 65132]]

B. ASME BPV Code, Section XI

Section 50.55a(a)(1)(ii) ASME Boiler and Pressure Vessel Code, Section 
XI
    The NRC is removing and reserving Sec.  50.55a(a)(1)(ii)(A), 
removing Sec.  50.55a(a)(1)(ii)(B)(5) through (7), and removing and 
reserving Sec.  50.55a(a)(1)(ii)(C)(1) through (32) and 
(a)(1)(ii)(C)(37) through (40) because these sections incorporate by 
reference older editions and addenda of Section XI prior to 2001 
Edition, which are no longer in use. As a result of removing those 
older editions that are no longer in use, the NRC is amending 
regulations in Sec.  50.55a(b)(2)(viii), (ix), (xii), (xiv), and (xv), 
(b)(2)(xviii)(A), (b)(2)(xix), and (b)(2)(xx)(A) to remove references 
to these older editions and addenda.
    The NRC is amending the regulations in Sec.  50.55a(a)(1)(ii)(C) to 
incorporate by reference the 2019 Edition (Division 1) of the ASME BPV 
Code, Section XI. The current regulations in Sec.  50.55a(a)(1)(ii)(C) 
incorporate by reference ASME BPV Code, Section XI, the 1977 Edition 
(Division 1) through the 2017 Edition (Division 1), subject to the 
conditions identified in current Sec.  50.55a(b)(2)(i) through (xlii). 
The amendment revises the introductory text to Sec.  
50.55a(a)(1)(ii)(C) to reference the 2019 Edition (Division 1) of the 
ASME BPV Code, Section XI.
Section 50.55a(b)(2) Conditions on ASME BPV Code Section XI
    The NRC is revising the definition of Section XI in Sec.  
50.55a(b)(2) to include the latest edition of the ASME BPV Code, 
Section XI incorporated by reference in paragraph (a)(1)(ii).
Section 50.55a(b)(2)(viii) Section XI Condition: Concrete Containment 
Examinations
    As stated above, the NRC is amending the regulations in Sec.  
50.55a(b)(2)(viii) to remove references to Section XI editions and 
addenda prior to the 2001 Edition. With the removal of these earlier 
editions the NRC also is deleting paragraphs (b)(2)(viii)(A) through 
(D) as these conditions apply to these earlier editions.
Section 50.55a(b)(2)(ix) Section XI Condition: Metal Containment 
Examinations
    As stated above, the NRC is amending the regulations in Sec.  
50.55a(b)(2)(ix) to remove references to Section XI editions and 
addenda prior to the 2001 Edition that are no longer in use. With the 
removal of these earlier editions the NRC also is deleting paragraphs 
(b)(2)(ix)(C) through (E) as these conditions apply to these earlier 
editions.
Section 50.55a(b)(2)(x) Section XI Condition: Quality Assurance
    The NRC is revising this condition to extend it to the versions of 
NQA-1 referenced in the 2019 Edition of the ASME BPV Code, Section XI, 
Table IWA 1600-1, ``Referenced Standards and Specifications,'' which 
this final rule incorporates by reference.
    The NRC is revising this condition to allow the use of the editions 
of NQA-1 that are both incorporated by reference in paragraph (a)(1)(v) 
of Sec.  50.55a and specified in Table IWA 1600-1 of the 1989 or later 
Editions of Section XI. In the 2019 Edition of ASME BPV Code, Section 
XI, Table IWA 1600-1 was updated to specify that licensees use the 1994 
Edition or 2008 Edition through 2015 Editions of NQA-1 when using the 
2019 Edition of Section XI. These revisions will allow licensees to use 
the 2011 Addenda to ASME NQA-1-2008 or the 2012 or 2015 Edition of NQA-
1 when using the 2019 or later Edition of Section XI that is 
incorporated by reference in Sec.  50.55a.
    The NRC also is revising this condition to remove the reference to 
IWA-1400 because it does not reference editions of NQA-1. The removal 
of reference to IWA-1400 clarifies the text of the condition because 
Table IWA 1600-1 specifies the editions of NQA-1 to be used while IWA-
1400 simply refers to using NQA-1 generally, without specifying any 
particular edition.
Section 50.55a(b)(2)(xviii)(D) Section XI Condition: NDE Personnel 
Certification: Fourth Provision
    The NRC is amending the condition found in Sec.  
50.55a(b)(2)(xviii) to address the removal of ASME BPV Code, Section 
XI, 2011 Addenda from Sec.  50.55a(a)(1)(ii).
    In addition, research performed at the Pacific Northwest National 
Laboratory (PNNL) has shown that laboratory practice can be effective 
in developing the skill to find flaws, and on-the-job training is 
effective at developing the ability to perform examinations in a 
nuclear reactor environment. Based on the research described in 
Technical Letter Report PNNL-29761, the 250 experience hours for a 
Level I certification can be reduced to 175 hours, with 125 experience 
hours and 50 hours of laboratory practice, and the experience hours for 
Level II Certification can be reduced to 720 hours, with 400 experience 
hours and 320 hours of laboratory practice, without significantly 
reducing the capabilities of the examiners to navigate in a nuclear 
reactor environment. The NRC is therefore adding an option to Sec.  
50.55a(b)(2)(xviii) to allow these requirements as an alternative to 
Appendix VII, Table VII-4110-1 and Appendix VIII, Subarticle VIII-2200 
in the 2010 Edition.
Section 50.55a(b)(2)(xx)(C) Section XI Condition: System Leakage Tests: 
Third Provision
    The NRC is amending the regulations in Sec.  50.55a(b)(2)(xx)(C) to 
extend the applicability of the condition through the latest edition of 
the ASME BPV Code, Section XI incorporated by reference in paragraph 
(a)(1)(ii) of this section. The NRC also is amending Sec.  
50.55a(b)(2)(xx)(C) to reflect that IWB-5210(c) was deleted from the 
2019 Edition because it contained verbiage that was redundant to the 
language in IWA-5213(b)(2) and IWB-5221(d).
Section 50.55a(b)(2)(xxi)(B) Section XI Condition: Table IWB-2500-1 
Examination Requirements: Table IWB-2500-1 Examination
    The NRC is amending the regulations in Sec.  50.55a(b)(2)(xxi)(B) 
to extend the applicability of the condition through the latest edition 
of the ASME BPV Code, Section XI incorporated by reference in paragraph 
(a)(1)(ii) of this section.
Section 50.55a(b)(2)(xxv)(B) Section XI Condition: Mitigation of 
Defects by Modification: Second Provision
    The NRC is amending the regulations in Sec.  50.55a(b)(2)(xxv)(B) 
to extend the applicability of the condition through the latest edition 
of the ASME BPV Code, Section XI incorporated by reference in paragraph 
(a)(1)(ii) of this section. The NRC also is amending the conditions 
found in Sec.  50.55a(b)(2)(xxv)(B) by revising requirements associated 
with (1) conducting wall thickness examinations at alternative 
locations; and (2) follow-on examination requirements for external 
corrosion of buried piping.
    Paragraph (b)(2)(xxv)(B)(2) currently requires the licensee to 
establish a loss of material rate by conducting wall thickness 
examinations at the location of the defect. The condition also 
establishes the timing of the examinations (i.e., two prior consecutive 
or nonconsecutive refueling outage cycles in the 10-year period prior 
to installation of the modification). The NRC is providing an 
alternative by allowing loss of material rates to be measured at an 
alternative location with similar corrosion conditions, similar flow 
characteristics, and the same

[[Page 65133]]

piping configuration (e.g., straight run of pipe, elbow, tee). The NRC 
had already accepted these characteristics as those necessary to 
establish equivalency for internal corrosion on buried piping 
configurations. The NRC recognizes that many licensees are conducting 
periodic wall thickness examinations of piping systems as part of aging 
management plans. Allowing an alternative equivalent location to be 
used to obtain loss of material rates provides flexibility and reduces 
unnecessary burden. In addition, the NRC is deleting the timing of the 
examination requirements because the 2-times multiplier required by the 
condition provides a conservative bias for measured loss of material 
rates.
    Paragraph (b)(2)(xxv)(B)(3) currently requires the licensee to 
conduct wall thickness examinations on a refueling outage interval 
until projected flaw growth rates have been validated. After validation 
of the flaw growth rate, the modification would be examined at half its 
expected life or, if the modification has an expected life greater than 
19 years, once per interval. The NRC is deleting the refueling outage 
interval examinations and only requiring the examination to occur at 
half the modification's expected life or, if the modification has an 
expected life greater than 19 years, once per interval. The NRC has 
concluded that a 2-times multiplier for known loss of material rates or 
a 4-times multiplier for estimated loss of material rates provides 
sufficient conservatism to allow a follow-up examination to occur at 
half the modification's expected life or, if the modification has an 
expected life greater than 19 years, once per interval.
    The changes in paragraph (b)(2)(xxv)(B)(3)(i) are editorial. The 
NRC is deleting the term ``through wall'' from the clarification of 
extent of degradation differences. The NRC recognizes that it would be 
unlikely that through wall leakage would be occurring in two locations 
(i.e., modification location, different examination location). The term 
``percent wall loss plus or minus 25 percent'' is sufficient to capture 
``through wall,'' if it should occur at the different examination 
location.
    Paragraph (b)(2)(xxv)(B)(3)(ii) currently requires licensees to 
examine a buried pipe modification location where loss of material has 
occurred due to external corrosion at half its expected life or 10 
years, whichever is sooner. The NRC is revising this condition to 
include a provision that would allow an extension of the required 
inspection to any time in the first full 10-year inspection interval 
after installation if the modification is recoated prior to backfill 
following modification. This could mean that the modification might not 
be inspected until as much as 19 years after installation. The NRC and 
industry recognize that effective coatings can isolate the base 
material from the environment and prevent further degradation. If 
coating holidays (e.g., voids in coating) were to go undetected, only 
localized loss of material would occur versus widespread general 
corrosion. The NRC has reached this conclusion for two reasons: (1) 
effective coatings ensure isolation of the modification site from the 
environment such that only the areas with coating holidays would be 
affected by the environment; and (2) because pitting corrosion that 
might occur due to holidays would not affect the intended function of 
the piping (i.e., to deliver flow), extension of the examination timing 
will not challenge the intended function of the piping system.
Section 50.55a(b)(2)(xxvi), Section XI Condition: Pressure Testing of 
Class 1, 2, and 3 Mechanical Joints
    The NRC is amending Sec.  50.55a(b)(2)(xxvi) to remove references 
to Section XI pressure test and VT-2 examination. The NRC is relaxing 
the requirement to perform an ASME Section XI pressure test in 
accordance with IWA-5211(a) and VT-2 examination of mechanical joints 
disassembled and reassembled during the course of repair/replacement 
activities. This condition was established in the final rule dated 
October 1, 2004 (69 FR 58804) to supplement the test provisions in IWA-
4540 of the 2001 Edition and the 2002 and 2003 Addenda of Section XI of 
the ASME BPV Code to require that Class 1, 2, and 3 mechanical joints 
be pressure tested in accordance with IWA-4540(c) of the 1998 Edition 
of Section XI. Over the years and in several rulemakings, commenters 
have stated this condition was not required because licensee post-
maintenance test programs in accordance with appendix B to 10 CFR part 
50, ``Quality Assurance Criteria for Nuclear Power Plants and Fuel 
Reprocessing Plants,'' specify requirements for leak testing mechanical 
connections following reassembly.
    The final rule issued on May 4, 2020 (85 FR 26540), revised this 
condition to clarify examiner and pressure test code requirements. But 
this change caused confusion, because the industry interpreted the rule 
to mean that some exemptions from pressure testing allowed by the code 
were no longer allowable and that certain pressure testings would now 
be required, whereas they were not required prior to this change. 
Following the publication of the final rule, the NRC held a public 
meeting on June 4, 2020, to discuss this condition. The industry asked 
the NRC to reevaluate the interpretation and the need for the 
condition. The NRC performed a qualitative risk analysis to judge the 
safety significance of performing the Section XI pressure test and VT-2 
examinations. The NRC looked at several risk scenarios and leveraged 
the principles of risk-informed decision-making with technical work 
completed through closure of Generic Safety Issue 29 (GSI-29): Bolting 
Degradation of Failure in Nuclear Power Plants and current operational 
experience; the NRC concluded that the risk of failure of mechanical 
joints in the absence of pressure testing and VT-2 examination after 
repair/replacement activities is very low. The NRC found that the risk 
analyses suggest that the absence of the pressure test after repair/
replacement activities imposes a minimal safety concern when taking 
into account the additional measures conducted by the industry to 
ensure leak tightness. The NRC concluded that failure of a mechanical 
joint in the absence of a pressure test and VT-2 exam is unlikely, and 
the corresponding condition for Section XI pressure testing after 
repair/replacement activities is not needed for safety. The NRC 
presented the results of this risk analysis at a public meeting held 
June 25, 2020.
    In performing the risk determination, the NRC considered several 
principles of risk-informed decision-making. While not relying fully on 
these concepts, the NRC determined that the following additional 
measures help reduce the uncertainty associated with the qualitative 
risk assessment discussed above. With respect to performance 
monitoring, the NRC considered (1) leak tests conducted as part of the 
licensee quality assurance programs; (2) walkdowns of accessible areas 
by Operations staff, including inspecting for leaks as part of plant 
rounds; (3) containment monitoring for identified and unidentified 
leakage; and (4) pressure testing of the reactor coolant loop performed 
after each refueling outage. With respect to defense-in-depth, the NRC 
considered that many systems, including the emergency core cooling 
system, are in place to maintain core cooling if a primary system has a 
flange failure, and that many Code systems have redundant trains. With 
respect to safety margins, the NRC considered that leak-before-break 
analysis of nuclear power plant primary systems have illustrated that 
significant

[[Page 65134]]

safety margins exist for leaking joints, and the results of studies 
conducted during closure of GSI-29 showed that a joint will leak with a 
sufficient rate to be detected and mitigated by the licensees before 
joint rupture occurs.
    The NRC initially proposed requiring that licensees define a leak 
test to be applied, but received comments that licensees are already 
performing such tests to the standards of their quality assurance 
programs under appendix B to 10 CFR part 50 and that requiring 
licensees to create an additional program for such tests is duplicative 
and unnecessary. The NRC agrees with these comments. Therefore, the NRC 
is amending Sec.  50.55a(b)(2)(xxvi) to require mechanical joints in 
Class 1, 2, and 3 piping and components greater than NPS-1 that are 
disassembled and reassembled during the performance of a Section XI 
repair/replacement activity must be verified to be leak tight, and the 
verification must be performed to the standards of the licensee's 
appendix B program. To be clear, this condition requires licensees to 
verify that these mechanical joints are leak tight even under 
circumstances a licensee's program under appendix B to 10 CFR part 50 
would not require such verification. However, licensees need not define 
a new leak test or personnel qualifications; instead, licensees will 
apply the quality standards of their appendix B programs.
    Because the condition no longer requires an ASME Code pressure 
test, the ASME Code NDE examiner qualification requirements would no 
longer apply. Therefore, in this final rule the NRC also is removing 
the requirement for the NDE examiners to meet the requirements of the 
licensee's current ISI code of record. In contrast to the proposed 
rule, which indicated licensees would need to establish qualifications 
for personnel performing the licensee-defined leak test, the final rule 
relies on the qualification requirements of appendix B to part 50 to 
ensure that tests are conducted by qualified personnel.
    Requiring verification of leak tightness ensures the leak tests are 
completed, and the NRC agrees that requirements of the licensee's 
program under appendix B to part 50 are sufficient to ensure the tests 
are conducted to an appropriate standard for nuclear applications. This 
requirement is consistent with recommendations of the ASME Post 
Construction Committee (PCC), which develops and maintains standards 
addressing common issues and technologies related to post construction 
activities. The PCC works with other consensus committees on the 
development of separate, product-specific, codes and standards that 
address issues encountered after initial construction for equipment and 
piping covered by Pressure Technology Codes and Standards. The PCC-
developed standards generally follow ``Recognized and Generally 
Accepted Good Engineering Practice.'' The PCC has developed PCC-1, 
``Guidelines for Pressure Boundary Bolted Flange Joint Assembly,'' for 
maintaining flanged joints, which has been referenced in American 
Petroleum Institute and National Board of Boiler and Pressure Vessel 
Inspectors Inspection Code standards. PCC-1 requires an owner defined 
leak test, which is generally accepted as a good engineering practice.
    The NRC will continue to monitor operating experience related to 
mechanical joints to determine if this condition merits modification in 
the future.
Section 50.55a(b)(2)(xxix), Section XI Condition: Nonmandatory Appendix 
R
    The NRC is amending Sec.  50.55a(b)(2)(xxix) to allow the use of 
Supplement 2 of Nonmandatory Appendix R of Section XI in the 2017 and 
2019 Editions without submittal of an alternative in accordance with 
Sec.  50.55a(z). Currently Sec.  50.55a(b)(2)(xxix) requires licensees 
who desire to implement a Risk-Informed Inservice Inspection (RI-ISI) 
program in accordance with Appendix R to obtain prior authorization of 
an alternative in accordance with Sec.  50.55a(z). The NRC has reviewed 
the latest revisions to Appendix R and have found that Supplement 2 of 
Appendix R in the 2017 and 2019 Editions of ASME Section XI would 
ensure that future RI-ISI programs continue to comply with RG 1.178, 
``An Approach for Plant-Specific Risk-Informed Decision making for 
Inservice Inspection of Piping''; RG 1.200, ``An Approach for 
Determining the Technical Adequacy of Probabilistic Risk Assessment 
Results for Risk-Informed Activities''; and NRC Standard Review Plan 
Chapter 3.9.8, ``Review of Risk-Informed Inservice Inspection of 
Piping.'' Therefore, the NRC is amending Sec.  50.55a(b)(2)(xxix) to 
allow RI-ISI programs in accordance with Supplement 2 of Appendix R in 
ASME Section XI editions 2017 and later to be used without submittal of 
an alternative in accordance with Sec.  50.55a(z). The submittal of an 
alternative is still required for RI-ISI programs in accordance with 
Supplement 1 of Appendix R or to use Supplement 2 of Section XI 
editions prior to 2017.
Section 50.55a(b)(2)(xxxii) Section XI Condition: Summary Report 
Submittal
    The NRC is amending the condition in Sec.  50.55a(b)(2)(xxxii) to 
relax the timeframe for submittal of Summary Reports (pre-2015 Edition) 
or Owner Activity Reports (2015 Edition and later) for inservice 
examinations and repair replacement activities. Through the 2017 
Edition of ASME BPV Code, Section XI, owners were required to prepare 
Summary Reports or Owner Activity Reports of preservice examination, 
inservice examinations and repair replacement activities within 90 
calendar days of the completion of each refueling outage. In the 2019 
Edition of Section XI this timeframe was extended to 120 days. The NRC 
has no objections to allowing licensees up to 120 days to submit the 
reports and sees no reason to require earlier submittal for users of 
previous editions. Therefore, the NRC is relaxing the requirement for 
all licensees. Licensees using Section XI, Editions and Addenda prior 
to the 2010 Edition may utilize Code Case N-778, ``Alternative 
Requirements for Preparation and Submittal of Inservice Inspection 
Plans, Schedules, and Preservice and Inservice Inspection Summary 
Reports, Section XI, Division 1,'' to obtain the 120 day submittal 
relaxation.
Section 50.55a(b)(2)(xxxvi) Section XI Condition: Fracture Toughness of 
Irradiated Materials
    The NRC is amending the regulations in Sec.  50.55a(b)(2)(xxxvi) to 
extend the applicability of the condition through the latest edition of 
the ASME BPV Code, Section XI incorporated by reference in paragraph 
(a)(1)(ii) of this section.
Section 50.55a(b)(2)(xxxix) Section XI Condition: Defect Removal
    The NRC is amending the regulations in Sec.  50.55a(b)(2)(xxxix) to 
extend the applicability of the condition through the latest edition of 
the ASME BPV Code, Section XI incorporated by reference in paragraph 
(a)(1)(ii) of this section.
Section 50.55a(b)(2)(xl) Section XI Condition: Prohibitions on Use of 
IWB-3510.4(b)
    The NRC is removing the existing condition Sec.  50.55a(b)(2)(xl) 
and its proposed modification as a result of public comments, which 
provided information demonstrating that the condition is not necessary 
(see ``NRC Responses to Public Comments: Final Rule: American Society 
of Mechanical Engineers 2019-2020 Code Editions,'' as provided in the 
``Availability of

[[Page 65135]]

Documents'' section of this document) on the proposed modification to 
the condition. Removal of this condition and its proposed modification 
will extend the applicability of the ASME BPV Code, Section XI 
procedures to certain ferritic steels with specified minimum yield 
strength greater than 50 kilopound per square inch (ksi).
Section 50.55a(b)(2)(xliii) Section XI Condition: Regulatory Submittal 
Requirements
    The NRC is adding Sec.  50.55a(b)(2)(xliii) to require licensees to 
submit certain analyses for NRC review. In the 2019 Edition of the 
Code, ASME elected to remove a number of submittal requirements related 
to flaw evaluation. The subparagraphs where these requirements were 
removed included IWA-3100(b), IWB-3410.2(d), IWB-3610(e), IWB-3640, 
IWC-3640, IWD-3640, IWB-3720(c), IWB-3730(c), G-2216, G-2510, G-2520, 
A-4200(c), A-4400(b), and G-2110(a). The NRC reviewed each of these 
subparagraphs and determined that three of these removed submittal 
requirements were necessary to allow the NRC to review plant safety 
with respect to violation of pressure-temperature limits, ductile-to-
brittle transition behavior of ferritic steels, and the effects of 
radiation embrittlement. Therefore, the condition simply retains the 
requirement from previous editions of ASME Section XI.
    The IWB-3720 addresses the scenario where plant pressure-
temperature limits are violated due to an unanticipated operating 
event. Pressure-temperature limits provide important operational 
limitations that protect against brittle fracture of the Reactor 
Coolant System. In the case that such limits are exceeded, IWB-3720(a) 
directs the plant owner to perform an analysis that determines the 
effect of the out-of-limit condition on the structural integrity of the 
Reactor Coolant System. Given the important safety implications of 
violating pressure-temperature limits, the NRC determined that 
licensees shall submit analyses performed under IWB-3720(a) for NRC 
review.
    Nonmandatory Appendix A, subparagraph A-4200(c) and Nonmandatory 
Appendix G, subparagraph G-2110(c) allow owners to use a reference 
temperature based upon T0 (called RTT0) instead 
of RTNDT. RTNDT is a long-accepted method for 
accounting for ductile-to-brittle transition behavior of ferritic 
steels, including the effects of radiation embrittlement. T0 
has not been extensively used in the nuclear power industry, at this 
time. Determination of plant-specific T0 values requires 
careful consideration of the operating characteristics of the plant. 
Given the safety significance of the reactor pressure vessel and the 
relative lack of experience with using T0, the NRC 
determined that licensees shall submit analyses to determine 
T0 for NRC review.

C. ASME OM Code

Section 50.55a(a)(1)(iii), ASME Code Cases: Nuclear Components
    The NRC is amending the regulations in Sec.  50.55a(a)(1)(iii) to 
incorporate by reference the ASME OM Code Case OMN-28, ``Alternative 
Valve Position Verification Approach to Satisfy ISTC-3700 for Valves 
Not Susceptible to Stem-Disk Separation.'' Public comments on Sec.  
50.55a(b)(3)(xi) requested that the NRC include acceptance of Code Case 
OMN-28 in this final rule for the purpose of extending the test 
interval for valves that have a stem-disk connection that is not 
susceptible to separation from two years to 12 years. The NRC agrees 
that Code Case OMN-28 provides a structured approach for the testing of 
these valves. The NRC is incorporating by reference ASME OM Code Case 
OMN-28 in Sec.  50.55a(a)(1)(iii) because it is referenced in Sec.  
50.55a(b)(3)(xi).
    Although the proposed rule did not include this Code Case, the NRC 
has determined that the incorporation by reference of this Code Case at 
the final rule stage is a logical outgrowth of the proposed rule. The 
preamble for the proposed rule stated that the NRC was aware that the 
ASME OM Code committees were considering allowing up to 12 years as the 
maximum interval for valve position verification testing in a Code 
Case, and that if that Code Case was issued prior to publication of the 
final rule, the NRC may adopt the 12-year maximum interval specified in 
that Code Case (86 FR 16087; 16096). Although the Code Case number was 
not yet assigned at the time when the NRC was preparing the proposed 
rule, it was issued in March 2021 as OM Code Case OMN-28. Several 
public comments were received seeking approval of OM Code Case OMN-28. 
There were no comments in opposition to the adoption of such a Code 
Case. Therefore, the NRC concludes that it may incorporate by reference 
ASME OM Code Case OMN-28. See also Section XV. of this document for 
additional discussion on the reasonable availability of this standard 
during the comment period.
Section 50.55a(a)(1)(iv), ASME Operation and Maintenance Code
    The NRC is amending the regulations in Sec.  50.55a(a)(1)(iv)(B) to 
incorporate by reference the 2020 Edition of the ASME OM Code for 
nuclear power plants.
    The current NRC regulations in Sec.  50.55a(a)(1)(iv)(B)(2) 
incorporate by reference the 2011 Addenda of the ASME OM Code into 
Sec.  50.55a. The NRC is streamlining Sec.  50.55a wherever possible to 
provide clearer IST regulatory requirements for nuclear power plant 
licensees and applicants. As part of this effort, the NRC has 
determined that the incorporation by reference of the 2011 Addenda of 
the ASME OM Code into Sec.  50.55a is not necessary. There are no 
licensees or applicants currently implementing the 2011 Addenda of the 
ASME OM Code. Further, the NRC regulations would have required updating 
licensees or applicants to implement the 2012 Edition of the ASME OM 
Code (rather than the 2011 Addenda) because it is a later edition and 
was incorporated by reference into Sec.  50.55a on the same date. 
Therefore, the NRC is removing the incorporation by reference of the 
2011 Addenda of the ASME OM Code from Sec.  50.55a(a)(1)(iv)(B)(2), 
which allows the NRC to remove the condition on the use of the 2011 
Addenda specified in Sec.  50.55a(b)(3)(xi) as well as the reference to 
the 2011 Addenda in Sec.  50.55a(b)(3)(ix). For similar reasons, the 
NRC is removing the incorporation by reference of the 2015 Edition of 
the ASME OM Code from Sec.  50.55a(a)(1)(iv)(C)(2) because the 2017 
Edition of the ASME OM Code was incorporated by reference into Sec.  
50.55a on the same date as the 2015 Edition. In the case of both the 
2011 Addenda and 2015 Edition, the NRC incorporated these editions of 
the Code on the same date as a later Edition, and as a result neither 
was ever eligible for use by applicants or updating licensees; if 
similar circumstances occur in the future, the NRC will consider 
skipping an edition rather than incorporating a revision that would not 
be usable for applicants or updating licensees.
Section 50.55a(b)(3) Conditions on ASME OM Code
    The NRC is simplifying Sec.  50.55a(b)(3) to be consistent with the 
removal of specific editions or addenda from Sec.  50.55a(a)(1)(iv) as 
previously mentioned and further discussed in the following.

[[Page 65136]]

Section 50.55a(b)(3)(iii) OM Condition: New Reactors
    The NRC is simplifying Sec.  50.55a(b)(3)(iii) by revising the 
applicability date to read ``April 17, 2018'' instead of ``the date 12 
months after April 17, 2017.'' This editorial correction does not 
change the applicability date of the condition.
Section 50.55a(b)(3)(iv) OM Condition: Check Valves (Appendix II)
    The NRC is replacing the reference to the 2015 Edition of the ASME 
OM Code with the 2012 Edition of the ASME OM Code in this paragraph 
because the NRC is amending Sec.  50.55a(a)(1)(iv)(C)(2) to remove the 
incorporation by reference of the 2015 Edition of the ASME OM Code. The 
2012 Edition becomes the latest edition that this condition applies to 
because changes were made to the 2017 and later Editions that allowed 
the NRC not to extend the condition to the newer Editions.
Section 50.55a(b)(3)(vii) OM Condition: Subsection ISTB
    The NRC is removing this condition on the use of Subsection ISTB, 
``Inservice Testing of Pumps in Light-Water Reactor Nuclear Power 
Plants--Pre-2000 Plants,'' in the 2011 Addenda of the ASME OM Code from 
Sec.  50.55a. The condition is unnecessary because the NRC also is 
amending Sec.  50.55a(a)(1)(iv)(B)(2) to remove the incorporation by 
reference of the 2011 Addenda of the ASME OM Code. The NRC is reserving 
this paragraph for future use.
Section 50.55a(b)(3)(viii) OM Condition: Subsection ISTE
    The current NRC regulations in Sec.  50.55a(b)(3)(viii) specify 
that licensees may not implement the risk-informed approach for IST of 
pumps and valves specified in Subsection ISTE, ``Risk-Informed 
Inservice Testing of Components in Light-Water Reactor Nuclear Power 
Plants,'' in the ASME OM Code, 2009 Edition through the latest edition 
and addenda of the ASME OM Code incorporated by reference in Sec.  
50.55a(a)(1)(iv), without first obtaining NRC authorization to use 
Subsection ISTE as an alternative to the applicable IST requirements in 
the ASME OM Code pursuant to Sec.  50.55a(z). In its review of 
Subsection ISTE, ``Risk-Informed Inservice Testing of Components in 
Water-Cooled Nuclear Power Plants,'' in the 2020 Edition of the ASME OM 
Code, the NRC has found that the ASME revised the subsection to be 
acceptable in the 2020 Edition of the ASME OM Code. Therefore, the NRC 
is not extending this condition to the 2020 Edition of the ASME OM 
Code. The NRC notes that a licensee will be expected to address 
performance issues with pumps and valves regardless of the risk ranking 
of the pumps and valves during the extent of condition review as part 
of the corrective action program to avoid common cause safety concerns 
at the applicable nuclear power plant.
Section 50.55a(b)(3)(ix), OM Condition: Subsection ISTF
    The NRC is amending the condition on the use of Subsection ISTF in 
Sec.  50.55a(b)(3)(ix) by removing the references to the 2011 Addenda 
and the 2015 Edition of the ASME OM Code. The references are 
unnecessary because the NRC also is amending Sec.  
50.55a(a)(1)(iv)(B)(2) to remove the incorporation by reference of the 
2011 Addenda and amending Sec.  50.55a(a)(1)(iv)(C)(2) to remove the 
incorporation by reference of the 2015 Edition of the ASME OM Code. The 
2012 Edition becomes the latest edition that this condition applies to 
because changes were made to the 2017 and later Editions that allowed 
the NRC not to extend the condition to the newer Editions.
Section 50.55a(b)(3)(xi) OM Condition: Valve Position Indication
    The NRC is amending Sec.  50.55a(b)(3)(xi) for the implementation 
of paragraph ISTC-3700, ``Position Verification Testing,'' in the ASME 
OM Code to clarify the condition by removing the reference to addenda 
of the ASME OM Code. ASME stopped publishing addenda after the 2011 
Addenda to the 2009 Edition, and the condition applies only to the 2012 
or later editions.
    In addition, the NRC is amending Sec.  50.55a(b)(3)(xi) to allow 
schedule flexibility for valves not susceptible to stem-disk separation 
by accepting ASME OM Code Case OMN-28, ``Alternative Valve Position 
Verification Approach to Satisfy ISTC-3700 for Valves Not Susceptible 
to Stem-Disk Separation,'' directly in Sec.  50.55a(b)(3)(xi). In the 
proposed rule, the NRC provided a revision to Sec.  50.55a(b)(3)(xi) 
for public comment that would have allowed a 10-year interval (rather 
than the 2-year interval specified in ISTC-3700) for valves not 
susceptible to separation of the stem-disk connection where 
justification is documented and available for NRC review. In the 
Federal Register notice of proposed rulemaking, the NRC noted that the 
ASME OM Code committees were considering increased schedule flexibility 
for valve position verification testing with a 12-year interval as part 
of a proposed Code Case. The NRC stated that if that Code Case was 
issued before the final rule was published, the NRC may adopt the 12-
year maximum interval in that Code Case. ASME has finalized that draft 
Code Case as Code Case OMN-28, which the NRC considers to be consistent 
with the intent of the proposed rule. Therefore, the NRC is 
incorporating by reference Code Case OMN-28 in this final rule for 
efficiency in the regulatory process. In response to a public comment, 
the NRC revised Sec.  50.55a(b)(3)(xi) to include a provision 
indicating that where plant conditions make it impractical to perform 
the initial ISTC-3700 test as supplemented by Sec.  50.55a(b)(3)(xi) by 
the date 2 years following the previously performed ISTC-3700 test, a 
licensee may justify an extension of this initial supplemental valve 
position verification provided the ISTC-3700 test as supplemented by 
Sec.  50.55a(b)(3)(xi) is performed at the next available opportunity 
and no later than the next plant shutdown. This one-time extension of 
the ISTC-3700 test schedule as supplemented by Sec.  50.55a(b)(3)(xi) 
is acceptable provided the licensee has available for NRC review 
documented justification based on information obtained over the 
previous 5 years of the structural integrity of the stem-disk 
connection for the applicable valves. The licensee's justification 
could be based on, for example, verification of the valve stem-disk 
connection through an appropriate weak link analysis, appropriate disk 
motion confirmed during diagnostic testing, or allowance and cessation 
of flow through the valves. The licensee's justification must provide 
reasonable assurance that the remote indicating lights accurately 
reveal the position of the valve obturator until the next ISTC-3700 
test as supplemented by Sec.  50.55a(b)(3)(xi) is performed.
    The NRC provides the following discussion in response to public 
comment on the supplemental valve position indication requirement in 
Sec.  50.55a(b)(3)(xi). The NRC regulations in Sec.  50.55a(b)(3)(xi) 
apply to valves within the scope of ASME OM Code, Subsection ISTC, and 
allow the valve position verification methods and frequencies in the 
ASME OM Code appendices, such as Appendix III, ``Preservice and 
Inservice Testing of Active Electric Motor-Operated Valve Assemblies in 
Water-Cooled Reactor Nuclear Power Plants,'' and Appendix IV, 
``Preservice and Inservice Testing of Active Pneumatically Operated 
Valve Assemblies in Nuclear Reactor Power Plants.'' The condition in

[[Page 65137]]

Sec.  50.55a(b)(3)(xi) applies when the remote position indication test 
required by ISTC-3700 is performed (i.e., 2 years from the previous 
remote position indication test). The NRC regulations in Sec.  
50.55a(b)(3)(xi) emphasize the intent of the valve position 
verification requirement in ISTC-3700 to provide assurance that the 
remote indicating lights provide accurate indication of the position of 
the valve obturator. The supplemental valve position verification 
requirement in Sec.  50.55a(b)(3)(xi) is not a separate test from the 
valve position verification requirement in ISTC-3700.
    The NRC agrees that the statement in ISTC-3700 that the 
observations need not be concurrent is confusing, because the purpose 
of observing such parameters as flow is to provide reasonable assurance 
that the indicating lights are accurately monitoring the valve 
obturator position. Therefore, the lights and supplemental observations 
need to be monitored together to demonstrate that the lights are 
performing properly. Although ISTC-3700 is not clear, this ASME OM Code 
paragraph allows flexibility regarding when someone physically is 
located at the valve to monitor stem travel and when someone is 
monitoring flow at another location. Further, the NRC considers the 
discussion of non-concurrent testing in ISTC-3700 to apply to the open 
and close function of each valve. For example, licensees might find it 
more convenient to verify that the remote indicating light for the open 
function is operating properly on a different day than the remote 
indicating light for the close function. The ASME OM Code allows non-
concurrent testing for both the open and close function as long as the 
2-year test frequency required by IST-3700 is satisfied for each stroke 
direction.
    Supplemental position verification observations are required to 
start during performance of the first remote position indication test 
required by ISTC-3700 following licensee implementation of the ASME OM 
Code, 2012 Edition through the latest edition of the ASME OM Code 
incorporated by reference in Sec.  50.55a(a)(1)(iv). The wording 
presented by the NRC staff during the public meeting on June 14, 2021, 
that ISTC-3700 requires valve position verification testing every 2 
years and the Sec.  50.55a(b)(3)(xi) condition applies when the ISTC-
3700 test is performed (2 years from the previous ISTC-3700 test) does 
not reflect a change of the NRC's the intent for the condition. The 
condition in Sec.  50.55a(b)(3)(xi) does not modify the schedule for 
valve position indication testing either in ISTC-3700 or ASME OM Code, 
Appendix III. ASME OM Code, Subsection ISTC, paragraph ISTC-3700, 
specifies that position verification testing for motor-operated valves 
will follow ASME OM Code, Appendix III. Therefore, the supplemental 
position indication testing required by Sec.  50.55a(b)(3)(xi) will 
follow the IST intervals specified in ASME OM Code, Appendix III, and 
extended IST intervals allowed in ASME OM Code Case OMN-26, ``Alternate 
Risk-Informed and Margin Based Rules for Inservice Testing of Motor 
Operated Valves,'' where a licensee has authorization to apply that 
Code Case.
Section 50.55a(f)(4): Inservice Testing Standards Requirement for 
Operating Plants
    The NRC is modifying Sec.  50.55a(f)(4) to clarify the relationship 
between Sec.  50.55a(f)(4) and (g)(4) regarding the IST or ISI programs 
for dynamic restraints (snubbers). In the 2006 Addenda of the BPV Code, 
Section XI, ASME moved the requirements for snubbers to Subsection 
ISTD, ``Preservice and Inservice Requirements for Dynamic Restraints 
(Snubbers) in Water-Cooled Reactor Nuclear Power Plants,'' of the OM 
Code. The NRC is including provisions in this paragraph that for 
dynamic restraints (snubbers), inservice examination, testing, and 
service life monitoring must meet the inservice examination and testing 
requirements set forth in the applicable ASME OM Code or ASME BPV Code, 
Section XI, as specified in Sec.  50.55a(b)(3)(v)(A) and (B). When 
using the 2006 Addenda or later of the ASME BPV Code, Section XI, the 
inservice examination, testing, and service life monitoring 
requirements for dynamic restraints (snubbers) must meet the 
requirements set forth in the applicable ASME OM Code as specified in 
Sec.  50.55a(b)(3)(v)(B). When using the 2005 Addenda or earlier 
edition or addenda of the ASME BPV Code, Section XI, the inservice 
examination, testing, and service life monitoring requirements for 
dynamic restraints (snubbers) must meet the requirements set forth in 
either the applicable ASME OM Code or ASME BPV Code, Section XI, as 
specified in Sec.  50.55a(b)(3)(v). This change to Sec.  50.55a(f)(4), 
coupled with the change to Sec.  50.55a(g)(4), clarifies the 
applicability of the inservice examination, testing, and service life 
monitoring requirements for dynamic restraints (snubbers) with either 
the ASME OM Code or ASME BPV Code, Section XI.
    In response to public comments on the proposed revision to 
paragraph (f)(4), the NRC is revising this paragraph to clarify that an 
augmented IST program may be implemented for pumps and valves that are 
within the scope of the ASME OM Code but are not ASME BPV Code Class 1, 
2, or 3 components. This use of an augmented IST program is acceptable 
without prior NRC approval (i.e., without relief under Sec.  
50.55a(f)(5) or an alternative under Sec.  50.55a(z)), provided the 
basis for deviations from the ASME OM Code, as incorporated by 
reference in Sec.  50.55a, demonstrates an acceptable level of quality 
and safety, or that implementing the Code provisions would result in 
hardship or unusual difficulty without a compensating increase in the 
level of quality and safety, where documented and available for NRC 
review.
Section 50.55a(f)(7), Inservice Testing Reporting Requirements
    The NRC is adding Sec.  50.55a(f)(7) to require nuclear power plant 
applicants and licensees to submit their IST Plans related to pumps and 
valves, and IST Plans related to snubber examination and testing to the 
NRC.
    The ASME OM Code editions prior to the 2020 Edition state in 
paragraph (a) of ISTA-3200, ``Administrative Requirements,'' that ``IST 
Plans shall be filed with the regulatory authorities having 
jurisdiction at the plant site.'' However, ASME has removed this 
provision from the 2020 Edition of the ASME OM Code, asserting this 
provision is more appropriate as a regulatory requirement rather than a 
Code requirement. The NRC needs these IST Plans for use in evaluating 
relief and alternative requests and to review deferral of quarterly 
testing to cold shutdowns and refueling outages. Therefore, the 
condition retains a requirement from previous editions of the ASME OM 
Code. In response to public comments, this final rule does not include 
the proposed requirement to submit interim IST Program Plans together 
with final safety analysis report updates. As noted in public comments, 
the NRC can request a licensee to submit an updated IST Program Plan if 
needed for the evaluation of relief or alternative requests submitted 
by a licensee.
Section 50.55a(g)(4), Inservice Inspection Standards Requirement for 
Operating Plants
    The NRC is modifying Sec.  50.55a(g)(4) to parallel proposed 
revisions to Sec.  50.55a(f)(4) to clarify the relationship between 
Sec.  50.55a(f)(4) and (g)(4) regarding the IST and ISI programs for 
dynamic restraints (snubbers). This change to Sec.  50.55a(g)(4), 
coupled with the change to Sec.  50.55a(f)(4), clarifies the 
applicability of the inservice

[[Page 65138]]

examination, testing, and service life monitoring requirements for 
dynamic restraints (snubbers) with either the ASME OM Code or ASME BPV 
Code, Section XI.

III. Opportunities for Public Participation

    The proposed rule was published on March 26, 2021, for a 60-day 
comment period (86 FR 16087). The public comment period closed on May 
25, 2021.
    During the public comment period, the NRC held a public meeting on 
May 6, 2021, to discuss the proposed rule, to answer questions on 
specific provisions of the proposed rule, and to encourage public input 
on the proposed rule. The public meeting summary is available in ADAMS 
as provided in the ``Availability of Documents'' section of this 
document.

IV. NRC Responses to Public Comments

    The NRC received eight letters and emails in response to the 
opportunity for public comment on the proposed rule. These comment 
submissions were submitted by the following commenters (listed in order 
of receipt):

1. Dominion Energy
2. Inservice Testing Owners Group
3. Private citizen, Terence Chan
4. Nuclear Energy Institute
5. American Society of Mechanical Engineers
6. Exelon Generation Company, LLC
7. Electric Power Research Institute
8. Tennessee Valley Authority

    In general, the comments:
     Suggested revising or rewording conditions to make them 
clearer.
     Opposed proposed conditions.
     Supplied additional information for NRC's consideration.
     Supported the proposed changes to revise or remove 
conditions.
     Proposed removal of several conditions.
    Due to the large number of comments received and the length of the 
NRC's response, a summary of the NRC's response to comments in areas of 
particular interest to stakeholders is included in this final rule. 
Special attention has been made to discuss comments that prompted the 
NRC to make more than editorial changes in this final rule from what 
the NRC had proposed. As such, comments on ASME BPV Code, Section III 
are not discussed since no changes were made in response to public 
comments. The public comment submittals are available from the Federal 
e-Rulemaking website at https://www.regulations.gov under Docket ID 
NRC-2018-0290. A discussion of all comments and complete NRC responses 
are presented in a separate document, ``NRC Responses to Public 
Comments: Final Rule: American Society of Mechanical Engineers 2019-
2020 Code Editions,'' as provided in the ``Availability of Documents'' 
section of this document.

A. ASME BPV Code, Section XI

10 CFR 50.55a(b)(2)(xxv), Mitigation of Defects by Modification
    One commenter recommended that the reexamination required by Sec.  
50.55a(b)(2)(xxv)(B)(3) be changed from ``once per interval'' to ``once 
every ten years'' to clarify that the reexamination need not be 
performed in the current inspection interval if less than 10 years 
remain in that inspection interval. Another commenter suggested that 
Sec.  50.55a(b)(2)(xxv)(B)(3)(ii) should be revised for clarity and 
provided recommended text. The NRC agrees with the comments but made 
further revisions to the suggested clarifications to afford licensees 
additional flexibility. The NRC has revised Sec.  50.55a(b)(2)(B)(3) to 
reflect these changes.
10 CFR 50.55a(b)(2)(xxvi), Pressure Testing Class 1, 2, and 3 
Mechanical Joints
    One commenter was concerned that the proposed rule language in 
Sec.  50.55a(b)(2)(xxvi) contained requirements that were more specific 
than those utilized in licensees' existing non-Code leak test 
procedures and for which the technical basis for such differentiation 
is unclear. The commenter suggested that the condition be deleted or 
replaced with an alternative language. The NRC disagrees with the 
commenter's suggestion to delete the condition but agrees with the 
commenter's recommendation to clarify the rule language. In response to 
this comment, the NRC revised Sec.  50.55a(b)(2)(xxvi).
10 CFR 50.55a(b)(2)(xl), Prohibitions and Restrictions on Use of IWB-
3510.4(b), IWC-3510.5(b), Table A-4200-1, and Table G-2110-1
    A commenter did not support the restriction on the use of IWB-
3510.4(b)(5) and IWC-3510.5(b)(5) for SA-508 Class 1 material, and 
recommended that this condition be revised in the final rule to not to 
apply to SA-508 Class 1 material. Further, the commenter stated that 
the prohibition or restriction on SA-533 Type B Class 2 material is 
unnecessary and recommended that the condition be deleted. The NRC 
agrees that the prohibition or restriction on the use of SA-508 Class 1 
and SA-533 Type B Class 2 material can be removed. As a result of this 
comment, the proposed condition is not included in this final rule.

B. ASME OM Code

10 CFR 50.55a(b)(3)(xi), Valve Position Indication
    One comment asserted that establishing a requirement to verify 
obturator position on every valve in the IST program with remote 
position indication could place a significant burden on the licensee to 
develop new test methods and procedures for valves that do not have 
supplemental means available, such as a flow or pressure indication. 
The comment further recommended that the condition be revised to 
provide greater flexibility to licensees and allow for the supplemental 
position obturator verification to be credited by existing performance-
based test methods and frequencies such as appendix J to 10 CFR part 
50, Code Cases OMN-23 and OMN-27, and performance-based testing in 
Mandatory Appendices II, III, and IV. One comment recommended that the 
condition be deleted because the condition represents a significant 
burden for licensees to implement, or alternatively revised to clarify 
the starting point for the condition or the timeframe when the 
implementation must be completed. Another comment suggested a complete 
revision to Sec.  50.55a(b)(3)(xi) that went beyond the changes in the 
proposed rule. Several comments recommended directly accepting ASME 
Code Case OMN-28 in Sec.  50.55a(b)(3)(xi). No comments opposed the 
adoption of a Code Case such as OMN-28.
    The NRC partially agrees and partially disagrees with these 
comments. The NRC disagrees that the condition should be revised to 
include a general reference to performance-based verification methods, 
with the intent to allow various methods for leakage testing intervals 
in appendix J to 10 CFR part 50 and other performance-based test 
methods and frequencies in the ASME OM Code and various Code Cases. The 
NRC notes that the appendix J to 10 CFR part 50 test program may be 
referenced in an alternative request in describing the proposed 
alternative schedule for valve position verification. However, appendix 
J to 10 CFR part 50 addresses, in part, containment valve leakage, and 
does not provide justification for verifying the valve position 
indicating lights. Therefore, an alternative request in accordance with 
Sec.  50.55a(z) must be submitted if the appendix J to 10 CFR part 50 
test program is proposed as part

[[Page 65139]]

of an alternative to ISTC-3700 as supplemented by Sec.  
50.55a(b)(3)(xi).
    In response to comments recommending that Sec.  50.55a(b)(3)(xi) be 
deleted, the NRC disagrees with these comments because the condition is 
necessary to ensure that licensees implement the provisions of the ASME 
OM Code, Subsection ISTC, paragraph ISTC-3700, to verify that valve 
obturator position is accurately indicated. The NRC disagrees that 
Sec.  50.55a(b)(3)(xi) should be revised to clarify the start date for 
the condition because the start date was previously discussed in the 
final rule that incorporated by reference the 2012 Edition of the ASME 
OM Code (82 FR 32934). The NRC agrees that the condition should be 
revised to include a direct reference to ASME OM Code Case OMN-28, 
which would allow licensees to extend the 2-year interval for valve 
position indication testing specified in Subsection ISTC, paragraph 
ISTC-3700, to 12 years for valves with a stem-disk connection that is 
not susceptible to separation.
    As a result of these comments, the NRC replaced the proposed 
provision allowing a 10-year interval for valve position indication 
testing for valves that have a stem-disk connection that is not 
susceptible to separation with a direct reference to the recently 
issued ASME Code Case OMN-28 in this final rule.
    The NRC agrees with a public comment to include a provision for a 
one-time extension and revised 10 CFR 50.55a(b)(3)(xi) in response. 
More detail is provided in this document in the ``Availability of 
Documents'' section under the heading ``Section 50.55a(b)(3)(xi) OM 
Condition: Valve Position Indication.''
10 CFR 50.55a(f)(4), Inservice Testing Standards Requirement for 
Operating Plants
    Several commenters were concerned that the proposed removal of the 
phrase ``without requesting relief under paragraph (f)(5) of this 
section or alternatives under paragraph (z) of this section'' caused 
confusion. The commenters indicated that the language is necessary to 
clarify that formal submittals of request for relief or alternatives 
are not required for augmented IST program related components. The NRC 
agrees with these comments that the removal of the phrase ``without 
requesting relief under paragraph (f)(5) of this section or 
alternatives under paragraph (z) of this section'' from the current 
language of Sec.  50.55a(f)(4) as proposed has caused confusion. The 
NRC's proposed revision to Sec.  50.55a(f)(4) was intended only to 
clarify the transition from the ASME BPV Code, Section XI, to the ASME 
OM Code for the IST requirements for dynamic restraints as licensees 
update their IST Programs to the more recent editions of the ASME OM 
Code. There was no intent to require submittal of requests for non-Code 
Class components when using augmented testing provisions. The phrase 
``without requesting relief under paragraph (f)(5) of this section or 
alternatives under paragraph (z) of this section'' was determined to be 
unnecessary during a final review of the proposed rule language because 
this aspect is understood. In response to public comments, the NRC has 
revised this paragraph to clarify that an augmented IST program may be 
implemented for pumps and valves that are within the scope of the ASME 
OM Code but are not ASME BPV Code Class 1, 2, or 3 components. This use 
of an augmented IST program is acceptable without prior NRC approval 
(i.e., without relief under Sec.  50.55a(f)(5) or an alternative under 
Sec.  50.55a(z)) provided the basis for deviations from the ASME OM 
Code, as incorporated by reference in Sec.  50.55a, demonstrates an 
acceptable level of quality and safety, or that implementing the Code 
provisions would result in hardship or unusual difficulty without a 
compensating increase in the level of quality and safety, where 
documented and available for NRC review.
10 CFR 50.55a(f)(7), Inservice Testing Reporting Requirements
    Several commenters were concerned that the proposed wording in 
Sec.  50.55a(f)(7) would expand the requirement for licensees to submit 
their IST Plans and interim IST Plan updates related to pumps and 
valves, and IST Plans and interim IST Plan updates related to snubber 
examination and testing to the NRC when the final safety analysis 
report is updated. The commenters indicated that this requirement would 
increase the frequency of the IST program plan submittals and would be 
unnecessary and overly burdensome. The NRC agrees that submittal of 
interim IST Program Plans by licensees is not necessary because, as 
indicated by public comments, the NRC can request that licensees 
provide the updated IST Program Plan if needed to evaluate a relief or 
alternative request. Therefore, the NRC revised Sec.  50.55a(f)(7) to 
reflect this change.

V. Section-by-Section Analysis

    This section describes the primary revisions made by this final 
rule; minor editorial and administrative corrections to correct 
spacing, administrative errors, and typos are not identified in this 
analysis.
Paragraph (a)(1)(i)(E)
    This final rule revises paragraphs (a)(1)(i)(E)(18) and (19) and 
adds new paragraph (a)(1)(i)(E)(20) to include the 2019 Edition of the 
ASME BPV Code.
Paragraph (a)(1)(ii)(A)
    This final rule removes and reserves paragraph (a)(1)(ii)(A).
Paragraph (a)(1)(ii)(B)
    This final rule revises paragraph (a)(1)(ii)(B) and removes 
paragraphs (a)(1)(ii)(B)(5) through (7).
Paragraph (a)(1)(ii)(C)
    This final rule removes and reserves paragraphs (a)(1)(ii)(C)(1) 
through (32) and paragraphs (a)(1)(ii)(C)(37) through (40), revises 
paragraphs (a)(1)(ii)(C)(54) and (55), and adds new paragraph 
(a)(1)(ii)(C)(56) to include the 2019 Edition of the ASME BPV Code.
Paragraph (a)(1)(iii)
    This final rule adds new paragraph (a)(1)(iii)(H) to include ASME 
OM Code Case OMN-28.
Paragraph (a)(1)(iv)
    This final rule revises paragraph (a)(1)(iv)(B)(1) and removes and 
reserves paragraph (a)(1)(iv)(B)(2) and it revises paragraphs 
(a)(1)(iv)(C)(2) and (3) to replace the 2015 Edition with the 2017 
Edition and the 2017 Edition with the 2020 Edition of the ASME OM Code, 
respectively.
Paragraph (a)(1)(v)(B)
    This final rule revises paragraphs (a)(1)(v)(B)(2) and (3) and adds 
new paragraphs (a)(1)(v)(B)(4) through (6) to include the 2011 addenda, 
and the 2012 and the 2015 Editions of the ASME NQA-1 Code.
Paragraph (b)(1)
    This final rule revises paragraphs (b)(1) introductory text and 
(b)(1)(ii), (iii), and (iv) to retain the applicability to users of the 
latest edition incorporated by reference in paragraph (a)(1)(i). It 
also revises paragraph (b)(1)(iv) to include the use of the 2015 
Edition of NQA-1 and paragraph (b)(1)(x) introductory text and 
paragraphs (b)(1)(x)(A) and (B) to add ``through the latest edition and 
addenda incorporated by reference in paragraph (a)(1)(i).'' New 
paragraph (b)(1)(xiii) introductory text and paragraphs (b)(1)(xiii)(A) 
and (B) which apply to preservice inspection of steam generator tubes 
are also added.

[[Page 65140]]

Paragraph (b)(2)
    This final rule revises paragraph (b)(2) introductory text to 
retain the applicability to users of the latest edition incorporated by 
reference in paragraph (a)(1)(ii).
Paragraph (b)(2)(viii)
    This final rule removes and reserves paragraphs (b)(2)(viii)(A) 
through (D).
Paragraph (b)(2)(ix)
    This final rule revises paragraph (b)(2)(ix) to remove references 
to Section XI editions and addenda prior to the 2001 Edition and to 
retain the applicability to users of the latest edition incorporated by 
reference in paragraph (a)(1)(ii). This final rule also revises 
paragraph (b)(2)(ix)(B) to remove references to Section XI editions and 
addenda prior to the 2001 Edition. This final rule also removes and 
reserves paragraphs (b)(2)(ix)(C) through (E).
Paragraph (b)(2)(x)
    This final rule revises paragraph (b)(2)(x) to include the use of 
NQA-1b-2011 Addenda to NQA-1-2008 Edition, and the 2012 and the 2015 
Editions of NQA-1. This final rule also removes the reference to IWA-
1400.
Paragraph (b)(2)(xii)
    This final rule revises paragraph (b)(2)(xii) to replace the 
reference to Section XI, 1997 Addenda with the reference to Section XI, 
2001 Edition.
Paragraph (b)(2)(xiv)
    This final rule revises paragraph (b)(2)(xiv) to replace the 
reference to the 1999 Addenda with the reference to the 2001 Edition.
Paragraph (b)(2)(xv)
    This final rule revises paragraph (b)(2)(xv) to remove the phrase 
``the 1995 Edition through.''
Paragraph (b)(2)(xviii)
    This final rule revises paragraph (b)(2)(xviii) to remove 
references to Section XI editions and addenda prior to the 2001 Edition 
and to retain the applicability to users of the latest edition 
incorporated by reference in paragraph (a)(1)(ii). This final rule also 
revises paragraph (b)(2)(xviii)(D) to add an option to allow the 
requirement in the 2019 Edition, Appendix VII, Table VII-4110-1 as an 
alternative to Table VII-4110-1 and Appendix VIII, Subarticle VIII-
2200.
Paragraph (b)(2)(xix)
    This final rule revises paragraph (b)(2)(xix) to remove references 
to Section XI editions and addenda prior to the 2001 Edition.
Paragraph (b)(2)(xx)
    This final rule revises paragraph (b)(2)(xx)(A) to replace the 
reference to the 1997 Addenda with the reference to the 2001 Edition. 
This final rule also revises paragraph (b)(2)(xx)(C) to retain the 
applicability to users of the latest edition incorporated by reference 
in paragraph (a)(1)(ii) and to remove reference to IWB-5210(c).
Paragraph (b)(2)(xxi)
    This final rule revises paragraph (b)(2)(xxi)(B) to retain the 
applicability to users of the latest edition incorporated by reference 
in paragraph (a)(1)(ii).
Paragraph (b)(2)(xxv)
    This final rule revises paragraph (b)(2)(xxv) introductory text and 
revises paragraph (b)(2)(xxv)(B) to extend the applicability to users 
of the latest edition incorporated by reference in paragraph 
(a)(1)(ii). This final rule also revises paragraph (b)(2)(xxv)(B)(2) to 
provide an alternative by allowing loss of material rates to be 
measured at an alternative location with similar corrosion conditions, 
similar flow characteristics, and the same piping configuration. This 
final rule also revises paragraph (b)(2)(xxv)(B)(3) to delete the 
refueling outage interval examination requirement and only require the 
examination to occur at half the modification's expected life or, if 
the modification has an expected life greater than 19 years, once per 
interval. This final rule also revises paragraph (b)(2)(xxv)(B)(3)(i) 
to make editorial changes and revises paragraph (b)(2)(xxv)(B)(3)(ii) 
to include a provision that would allow an extension of the required 
inspection if the modification location is recoated prior to backfill.
Paragraph (b)(2)(xxvi)
    This final rule revises paragraph (b)(2)(xxvi) to remove the 
requirements for pressure testing in accordance with IWA-5211(a) and 
NDE examination. This final rule also revises paragraph (b)(2)(xxvi) to 
add a requirement for the owner to perform the leak check to the 
standards of their appendix B to 10 CFR part 50 quality assurance 
program to demonstrate the joint's leak tightness.
Paragraph (b)(2)(xxix)
    This final rule revises paragraph (b)(2)(xxix) to add paragraphs 
(b)(2)(xxix)(A), (B), and (C) to allow the use of Supplement 2 of 
Nonmandatory Appendix R of Section XI in the 2017 and 2019 Editions 
without submittal of an alternative in accordance with Sec.  50.55a(z).
Paragraph (b)(2)(xxxii)
    This final rule revises the reporting requirements in paragraph 
(b)(2)(xxxii) to extend the timeframe for submittal of Summary Reports 
or Owner Activity Reports to 120 days.
Paragraph (b)(2)(xxxvi)
    This final rule revises paragraph (b)(2)(xxxvi) to retain 
applicability to users of the latest edition incorporated by reference 
in paragraph (a)(1)(ii).
Paragraph (b)(2)(xxxix)
    This final rule revises paragraph (b)(2)(xxxix) to retain 
applicability to users of the latest edition incorporated by reference 
in paragraph (a)(1)(ii).
Paragraph (b)(2)(xl)
    This final rule removes and reserves paragraph (b)(2)(xl).
Paragraph (b)(2)(xliii)
    This final rule adds new paragraph (b)(2)(xliii) to require 
submission of certain analyses to the NRC for review.
Paragraph (b)(3)
    This final rule revises paragraph (b)(3) to remove references to 
specific editions or addenda and to extend the applicability to users 
of the latest edition incorporated by reference in paragraph 
(a)(1)(iv).
Paragraph (b)(3)(iii)
    This final rule revises paragraph (b)(3)(iii) for clarity of the 
date of application of this condition.
Paragraph (b)(3)(iv)
    This final rule revises paragraph (b)(3)(iv) to update the 
conditions for use of Appendix II of the ASME OM Code, 2003 Addenda 
through the 2012 Edition and revises the paragraph for clarity.
Paragraph (b)(3)(vii)
    This final rule removes and reserves paragraph (b)(3)(vii).
Paragraph (b)(3)(viii)
    This final rule revises paragraph (b)(3)(viii) to prevent it from 
applying to editions later than the 2017 Edition of the ASME OM Code.
Paragraph (b)(3)(ix)
    This final rule revises paragraph (b)(3)(ix) to remove the 
reference to Subsection ISTF of the 2011 Addenda and 2015 Edition.

[[Page 65141]]

Paragraph (b)(3)(xi)
    This final rule revises paragraph (b)(3)(xi) to remove reference to 
ASME OM Code addenda, revises the paragraph for clarity, and to allow 
increased flexibility in the schedule for position verification testing 
of valves not susceptible to stem-disk separation as specified in ASME 
OM Code Case OMN-28. The final rule also allows schedule flexibility 
for the initial ASME OM Code, Subsection ISTC, paragraph ISTC-3700 
testing as supplemented by paragraph (b)(3)(xi) by the date 2 years 
after the previous ISTC-3700 test where plant conditions make such 
testing impractical.
Paragraph (f)(4)
    This final rule revises paragraph (f)(4) to clarify the 
relationship between paragraphs (f)(4) and (g)(4) regarding the IST and 
ISI programs for dynamic restraints. The final rule clarifies that 
prior NRC approval is not required to implement the augmented IST 
program activities for pumps and valves within the scope of the ASME OM 
Code, but are not ASME BPV Code Class 1, 2, or 3 components, where 
justification is available for NRC review.
Paragraph (f)(7)
    This final rule adds new paragraph (f)(7) to include the 
requirements for IST Program Plans at the outset of the 10-year IST 
Program interval.
Paragraph (g)(4)
    This final rule revises paragraph (g)(4) to clarify the 
relationship between paragraphs (f)(4) and (g)(4) regarding the IST and 
ISI programs for dynamic restraints.

VI. Generic Aging Lessons Learned Report

Background

    In December 2010, the NRC issued ``Generic Aging Lessons Learned 
(GALL) Report,'' NUREG-1801, Revision 2, for applicants to use in 
preparing license renewal applications. The GALL Report provides aging 
management programs (AMPs) that the NRC has concluded are sufficient 
for aging management in accordance with the license renewal rule, as 
required in Sec.  54.21(a)(3). In addition, ``Standard Review Plan for 
Review of License Renewal Applications for Nuclear Power Plants,'' 
NUREG-1800, Revision 2, was issued in December 2010, to ensure the 
quality and uniformity of NRC reviews of license renewal applications 
and to present a well-defined basis on which the NRC evaluates the 
applicant's AMPs and activities. In April 2011, the NRC also issued 
``Disposition of Public Comments and Technical Bases for Changes in the 
License Renewal Guidance Documents NUREG-1801 and NUREG-1800,'' NUREG-
1950, which describes the technical bases for the changes in Revision 2 
of the GALL Report and Revision 2 of the standard review plan (SRP) for 
review of license renewal applications.
    Revision 2 of the GALL Report, in Sections XI.M1, XI.S1, XI.S2, 
XI.M3, XI.M5, XI.M6, XI.M11B, and XI.S3, describes the evaluation and 
technical bases for determining the sufficiency of ASME BPV Code 
Subsections IWB, IWC, IWD, IWE, IWF, or IWL for managing aging during 
the period of extended operation (i.e., up to 60 years of operation). 
In addition, many other AMPs in the GALL Report rely, in part but to a 
lesser degree, on the requirements specified in the ASME BPV Code, 
Section XI. Revision 2 of the GALL Report also states that the 1995 
Edition through the 2004 Edition of the ASME BPV Code, Section XI, 
Subsections IWB, IWC, IWD, IWE, IWF, or IWL, as modified and limited by 
Sec.  50.55a, were found to be acceptable editions and addenda for 
complying with the requirements of Sec.  54.21(a)(3), unless 
specifically noted in certain sections of the GALL Report. The GALL 
Report further states that future Federal Register documents that amend 
Sec.  50.55a will discuss the acceptability of editions and addenda 
more recent than the 2004 Edition for their applicability to license 
renewal. In a final rule issued on June 21, 2011 (76 FR 36232), 
subsequent to Revision 2 of the GALL Report, the NRC also found that 
the 2004 Edition with the 2005 Addenda through the 2007 Edition with 
the 2008 Addenda of Section XI of the ASME BPV Code, Subsections IWB, 
IWC, IWD, IWE, IWF, or IWL, as subject to the conditions in Sec.  
50.55a, are acceptable for the AMPs in the GALL Report and the 
conclusions of the GALL Report remain valid with the augmentations 
specifically noted in the GALL Report. In a final rule issued on July 
18, 2017 (82 FR 32934), the NRC further finds that the 2009 Addenda 
through the 2013 Edition of Section XI of the ASME BPV Code, 
Subsections IWB, IWC, IWD, IWE, IWF, or IWL, as subject to the 
conditions in Sec.  50.55a, will be acceptable for the AMPs in the GALL 
Report. Also, in a final rule issued on May 4, 2020 (85 FR 26540), the 
NRC further finds that Subsections IWB, IWC, IWD, IWE, IWF, or IWL of 
Section XI of the 2015 Edition and the 2017 Edition of the ASME BPV 
Code, as subject to the conditions in Sec.  50.55a, will be acceptable 
for the AMPs in the GALL Report.
    In July 2017, the NRC issued ``Generic Aging Lessons Learned for 
Subsequent License Renewal (GALL-SLR) Report,'' NUREG-2191, for 
applicants to use in preparing applications for subsequent license 
renewal. The GALL-SLR Report provides AMPs that are sufficient for 
aging management for the subsequent period of extended operation (i.e., 
up to 80 years of operation), as required in Sec.  54.21(a)(3). The NRC 
also issued ``Standard Review Plan for Review of Subsequent License 
Renewal Applications for Nuclear Power Plants'' (SRP-SLR), NUREG-2192 
in July 2017. In a similar manner as the GALL Report does, the GALL-SLR 
Report, in Sections XI.M1, XI.S1, XI.S2, XI.M3, XI.11B, and XI.S3, 
describes the evaluation and technical bases for determining the 
sufficiency of ASME BPV Code Subsections IWB, IWC, IWD, IWE, IWF, or 
IWL for managing aging during the subsequent period of extended 
operation. Many other AMPs in the GALL-SLR Report rely, in part but to 
a lesser degree, on the requirements specified in the ASME BPV Code, 
Section XI. The GALL-SLR Report also indicates that the 1995 Edition 
through the 2013 Edition of the ASME BPV Code, Section XI, Subsections 
IWB, IWC, IWD, IWE, IWF, or IWL, as subject to the conditions in Sec.  
50.55a, are acceptable for complying with the requirements of Sec.  
54.21(a)(3), unless specifically noted in certain sections of the GALL-
SLR Report.

Evaluation With Respect to Aging Management

    As part of this final rule, the NRC evaluated whether those AMPs in 
the GALL Report and GALL-SLR Report that rely upon Subsections IWB, 
IWC, IWD, IWE, IWF, or IWL of Section XI in the editions and addenda of 
the ASME BPV Code incorporated by reference into Sec.  50.55a, in 
general continue to be acceptable if the AMP relies upon these 
Subsections in the 2019 Edition. The NRC finds that the 2019 Edition of 
Section XI of the ASME BPV Code, Subsections IWB, IWC, IWD, IWE, IWF, 
or IWL, as subject to the conditions of this rule, are acceptable for 
the AMPs in the GALL Report and GALL-SLR Report with the exception of 
augmentation, as specifically noted in those reports, and the NRC finds 
that the conclusions of the GALL Report and GALL-SLR Report remain 
valid. Accordingly, an applicant for license renewal (including 
subsequent license renewal) may use, in its plant-specific license 
renewal application, Subsections IWB, IWC, IWD, IWE, IWF, or IWL of 
Section XI of

[[Page 65142]]

the 2019 Edition of the ASME BPV Code, as subject to the conditions in 
this final rule, without additional justification. Similarly, a 
licensee approved for license renewal that relied on the AMPs may use 
Subsections IWB, IWC, IWD, IWE, IWF, or IWL of Section XI of the 2019 
Edition of the ASME BPV Code. However, applicants must assess and 
follow applicable NRC requirements with regard to licensing basis 
changes and evaluate the possible impact on the elements of existing 
AMPs.
    Some of the AMPs in the GALL Report and GALL-SLR Report recommend 
augmentation of certain Code requirements in order to ensure adequate 
aging management for license renewal. The technical and regulatory 
aspects of the AMPs for which augmentations are recommended also apply 
if the 2019 Edition of Section XI of the ASME BPV Code is used to meet 
the requirements of Sec.  54.21(a)(3). The NRC evaluated the changes in 
the 2019 Edition of Section XI of the ASME BPV Code to determine if the 
augmentations described in the GALL Report and GALL-SLR Report remain 
necessary; the NRC's evaluation has concluded that the augmentations 
described in the GALL and GALL-SLR Reports are necessary to ensure 
adequate aging management.
    For example, GALL-SLR Report AMP XI.S3, ``ASME Section XI, 
Subsection IWF,'' recommends that volumetric examination consistent 
with that of the ASME BPV Code, Section XI, Table IWB-2500-1, 
Examination Category B-G-1 should be performed to detect cracking for 
high strength structural bolting (actual measured yield strength 
greater than or equal to 150 ksi in sizes greater than 1-inch nominal 
diameter). The GALL-SLR Report also indicates that this volumetric 
examination may be waived with adequate plant-specific justification. 
This guidance for aging management in the GALL-SLR Report is the 
augmentation of the visual examination specified in Subsection IWF of 
the 2019 Edition of the ASME BPV Code, Section XI.
    A license renewal applicant may either augment its AMPs as 
described in the GALL Report and GALL-SLR Report (for operation up to 
60 and 80 years respectively), or propose alternatives for the NRC to 
review as part of the applicant's plant-specific justification for its 
AMPs.

VII. Regulatory Flexibility Certification

    Under the Regulatory Flexibility Act (5 U.S.C. 605(b)), the NRC 
certifies that this rule does 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 (10 CFR 2.810).

VIII. Regulatory Analysis

    The NRC has prepared a final regulatory analysis on this 
regulation. The analysis examines the costs and benefits of the 
alternatives considered by the NRC. The regulatory analysis is 
available as indicated in the ``Availability of Documents'' section of 
this document.

IX. Backfitting and Issue Finality

Introduction

    The NRC's Backfit Rule in Sec.  50.109 states that the NRC shall 
require the backfitting of a facility only when it finds the action to 
be justified under specific standards stated in the rule. Section 
50.109(a)(1) defines backfitting as the modification of or addition to 
systems, structures, components, or design of a facility; the design 
approval or manufacturing license for a facility; or the procedures or 
organization required to design, construct, or operate a facility. Any 
of these modifications or additions may result from a new or amended 
provision in the NRC's rules or the imposition of a regulatory position 
interpreting the NRC's rules that is either new or different from a 
previously applicable NRC position after issuance of the construction 
permit or the operating license or the design approval.
    Section 50.55a requires nuclear power plant licensees to:
     Construct ASME BPV Code Class 1, 2, and 3 components in 
accordance with the rules provided in Section III, Division 1, of the 
ASME BPV Code (``Section III'').
     Inspect, examine, and repair or replace Class 1, 2, 3, 
Class MC, and Class CC components in accordance with the rules provided 
in Section XI, Division 1, of the ASME BPV Code (``Section XI'').
     Test Class 1, 2, and 3 pumps and valves in accordance with 
the rules provided in the ASME OM Code.
     Inspect, examine, repair or replace, and test Class 1, 2, 
and 3 dynamic restraints (snubbers) in accordance with the rules 
provided in either the ASME OM Code or Section XI, depending on the 
Code Edition.
    This final rule incorporates by reference the 2019 Edition to the 
ASME BPV Code, Section III, Division 1 and ASME BPV Code, Section XI, 
Division 1, as well as the 2020 Edition to the ASME OM Code.
    The ASME BPV and OM Codes are national consensus standards 
developed by participants with broad and varied interests, in which all 
interested parties (including the NRC and utilities) participate. A 
consensus process involving a wide range of stakeholders is consistent 
with the NTTAA, inasmuch as the NRC has determined that there are sound 
regulatory reasons for establishing regulatory requirements for design, 
maintenance, ISI, and IST by rulemaking. The process also facilitates 
early stakeholder consideration of backfitting issues. Thus, the NRC 
finds that the NRC need not address backfitting with respect to the 
NRC's general practice of incorporating by reference updated ASME 
Codes.
    This final rule also incorporates by reference Code Case OMN-28, 
the 2011 Addenda to ASME NQA-1-2008, and the 2012 and 2015 Editions of 
ASME NQA-1. However, each of these are voluntary alternatives to 
provisions of the ASME Codes, and their incorporation by reference does 
not constitute backfitting, because there is no imposition of a new 
requirement or new position. Similarly, voluntary application of OMN-
28, the 2011 Addenda to ASME NQA-1-2008, or the 2012 and 2015 Editions 
of ASME NQA-1 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.

Overall Backfitting Considerations: Section III of the ASME BPV Code

    Incorporation by reference of more recent editions and addenda of 
Section III of the ASME BPV Code does not affect a plant that has 
received a construction permit or an operating license or a design that 
has been approved. This is because the edition and addenda to be used 
in constructing a plant are, under Sec.  50.55a, determined based on 
the date of the construction permit or combined license, and are not 
changed thereafter, except voluntarily by the licensee. The 
incorporation by reference of more recent editions and addenda of 
Section III ordinarily applies only to applicants after the effective 
date of the final rule incorporating these new editions and addenda. 
Thus, incorporation by reference of a more recent edition and addenda 
of Section III does not constitute ``backfitting'' as defined in Sec.  
50.109(a)(1).

[[Page 65143]]

Overall Backfitting Considerations: Section XI of the ASME BPV Code and 
the ASME OM Code

    Incorporation by reference of more recent editions and addenda of 
Section XI of the ASME BPV Code and the ASME OM Code affects the ISI 
and IST programs of operating reactors. However, the Backfit Rule 
generally does not apply to incorporation by reference of later 
editions and addenda of the ASME BPV Code (Section XI) and OM Code. As 
previously mentioned, the NRC's longstanding regulatory practice has 
been to incorporate later versions of the ASME Codes into Sec.  50.55a. 
Under Sec.  50.55a, licensees must revise their ISI and IST programs 
every 120 months to the latest edition and addenda of Section XI of the 
ASME BPV Code and the ASME OM Code incorporated by reference into Sec.  
50.55a 18 months before the start of a new 120-month ISI and IST 
interval. Thus, when the NRC approves and requires the use of a later 
version of the Code for ISI and IST, it is implementing this 
longstanding regulatory practice and requirement. In this final rule, 
the NRC's elimination of some Section XI editions and addenda from the 
regulations does not constitute a backfit because the editions and 
addenda of codes being removed are no longer in use or available for 
use by licensees.
    Other circumstances where the NRC does not apply the Backfit Rule 
to the approval and requirement to use later Code editions and addenda 
are as follows:
    1. When the NRC takes exception to a later ASME BPV Code or OM Code 
provision but merely retains the current existing requirement, 
prohibits the use of the later Code provision, limits the use of the 
later Code provision, or supplements the provisions in a later Code, 
the Backfit Rule does not apply because the NRC is not imposing new 
requirements. However, the NRC explains any such exceptions to the Code 
in the preamble to and regulatory analysis for the rule.
    2. When an NRC exception relaxes an existing ASME BPV Code or OM 
Code provision but does not prohibit a licensee from using the existing 
Code provision, the Backfit Rule does not apply because the NRC is not 
imposing new requirements.
    3. Modifications and limitations imposed during previous routine 
updates of Sec.  50.55a have established a precedent for determining 
which modifications or limitations are backfits, or require a backfit 
analysis (e.g., final rule dated September 10, 2008 (73 FR 52731), and 
a correction dated October 2, 2008 (73 FR 57235)). The application of 
the backfit requirements to modifications and limitations in the 
current rule are consistent with the application of backfit 
requirements to modifications and limitations in previous rules.
    The incorporation by reference and adoption of a requirement 
mandating the use of a later ASME BPV Code or OM Code may constitute 
backfitting in some circumstances. In these cases, the NRC would 
perform a backfit analysis or prepare documented evaluation in 
accordance with Sec.  50.109. These include the following:
    1. When the NRC endorses a later provision of the ASME BPV Code or 
OM Code that takes a substantially different direction from the 
existing requirements, the action is treated as a backfit (e.g., 61 FR 
41303; August 8, 1996).
    2. When the NRC requires implementation of a later ASME BPV Code or 
OM Code provision on an expedited basis, the action is treated as a 
backfit. This applies when implementation is required sooner than it 
would be required if the NRC simply endorsed the Code without any 
expedited language (e.g., 64 FR 51370; September 22, 1999).
    3. When the NRC takes an exception to an ASME BPV Code or OM Code 
provision and imposes a requirement that is substantially different 
from the existing requirement as well as substantially different from 
the later Code (e.g., 67 FR 60529; September 26, 2002).

Detailed Backfitting Discussion: Changes Beyond Those Necessary To 
Incorporate by Reference the New ASME BPV and OM Code Provisions

    This section discusses the backfitting considerations for all the 
changes to Sec.  50.55a that go beyond the minimum changes necessary 
and required to adopt the new ASME Code Addenda into Sec.  50.55a.

ASME BPV Code, Section III

    1. Revise Sec.  50.55a(b)(1)(iv) to require that when applying 
editions and addenda later than the 1989 Edition of Section III, the 
requirements of NQA-1 the 1994 Edition, the 2008 Edition, the 2009-1a 
Addenda to 2008 Edition and the 2015 Edition are acceptable for use, 
provided that the edition and addenda of NQA-1 specified in either NCA-
4000 or NCA-7000 is used in conjunction with the administrative, 
quality, and technical provisions contained in the edition and addenda 
of Section III being used. This revision clarifies the current 
requirements and is considered to be consistent with the meaning and 
intent of the current requirements, and therefore is not considered to 
result in a change in requirements. As such, this change is not a 
backfit.
    2. Add Sec.  50.55a(b)(1)(xiii)(A) and (B) to require compliance 
with two new provisions related to preservice examination of steam 
generator tubing. The 2017 Edition of the ASME Code contains 
requirements for preservice examination of steam generator tubing, 
however, the 2019 Edition does not require these preservice 
examinations of steam generator tubing to be performed including the 
acceptance criteria. Therefore, the NRC is adding two conditions to 
ensure the tubing's structural integrity and ability to perform its 
intended function along with an adequate preservice examination 
baseline for future required inservice examinations. Because the new 
conditions maintain the current requirements that were removed from the 
latest Edition of the ASME Code, the conditions do not constitute a new 
or changed NRC position. Therefore, this change is not a backfit.

ASME BPV Code, Section XI

    1. Revise Sec.  50.55a(a)(1)(ii) to remove the incorporation by 
reference of the addenda 1975 Winter Addenda, 1976 Summer Addenda 1976 
Winter Addenda, and the Division 1 1977 Edition through1994 Addenda and 
1998 Edition through 2000 Addenda because they incorporate by reference 
older editions and addenda of Section XI that are no longer in use or 
available for use by licensees. The revisions do not modify the current 
inservice inspection regulatory requirements and, therefore, are not 
backfits.
    2. Revise Sec.  50.55a(b)(2)(viii), (ix), (xii), (xiv), and (xv), 
(b)(2)(xviii)(A), and (b)(2)(xix) and (xx) to be consistent with the 
removal of specific editions and addenda from Sec.  50.55a(a)(1)(ii). 
These changes do not modify current requirements and, therefore, are 
not backfits.
    3. Revise Sec.  50.55a(b)(2)(viii), to delete Sec.  
50.55a(b)(2)(viii)(A) through (D), to be consistent with the removal of 
specific editions and addenda from Sec.  50.55a(a)(1)(ii). These 
changes to Sec.  50.55a(b)(2)(viii) reflect the removal of conditions 
that are no longer needed because they were applicable only to the 
addenda and editions being removed. Therefore, this change is not a 
backfit.
    4. Revise Sec.  50.55a(b)(2)(ix), to delete Sec.  
50.55a(b)(2)(ix)(C) through (E), to be consistent with the removal of 
specific editions and addenda from Sec.  50.55a(a)(1)(ii). These 
changes to Sec.  50.55a(b)(2)(ix) reflect the removal of

[[Page 65144]]

conditions that are no longer needed because they were applicable only 
to the addenda and editions being removed. Therefore, this change is 
not a backfit.
    5. Revise Sec.  50.55a(b)(2)(x), to remove the reference to IWA-
1400. This revision clarifies the condition because the editions of 
NQA-1 are specified in Table IWA 1600-1 instead of IWA-1400. Therefore, 
the revision of this condition is not a backfit.
    6. Revise Sec.  50.55a(b)(2)(xviii)(D) to add an alternative to the 
requirements of Table VII-4110-1 which allows NDE examiners to achieve 
qualification with reduced experience hours based on hours of 
laboratory practice. The revised condition represents a relaxation in 
the current requirements. Therefore, the revision of this condition is 
not a backfit.
    7. Revise Sec.  50.55a(b)(2)(xxv), by revising requirements 
associated with (a) Conducting wall thickness examinations at 
alternative locations; and (b) follow-on examination requirements for 
external corrosion of buried piping.
    The revised condition represents a relaxation in the current 
requirements. Therefore, the revision of this condition is not a 
backfit.
    8. Revise Sec.  50.55a(b)(2)(xxvi), to allow the use of a licensee 
defined leak check in lieu of a Section XI pressure test and VT-2 
examination of mechanical joints. The revised condition represents a 
relaxation in the current requirements and allows licensees to perform 
a leak check in accordance with their post-maintenance test program and 
Quality Assurance program. Therefore, the revision of this condition is 
not a backfit.
    9. Revise Sec.  50.55a(b)(2)(xxix), to allow the use of 
Nonmandatory Appendix R, Supplement 2 in the 2019 and future editions 
of the code. The revised condition represents a relaxation from the 
current requirements. Therefore, the revision of this condition is not 
a backfit.
    10. Revise Sec.  50.55a(b)(2)(xxxii), to extend the timeframe for 
licensees to submit Summary Reports and Owner Activity Reports 
following completion of a refueling outage for users of the 2019 and 
future editions of the code. The revised condition represents a 
relaxation from the current requirements. Therefore, the revision of 
this condition is not a backfit.
    11. Remove Sec.  50.55a(b)(2)(xl) to allow use of Subparagraphs 
IWB-3510.4(b)(4), IWB-3510.4(b)(5), IWC-3510.5(b)(4), and IWC-
3510(b)(5), and Table A-4200-1, Table G-2110-1, Figure A-4200-1, and 
Figure G-220-1 as it relates to the toughness of certain ferritic 
steels with specified minimum yield strength greater than 50 ksi. 
Removing this condition represents a relaxation from the current 
requirements. Therefore, the removal of this condition is not a 
backfit.
    12. Add Sec.  50.55a(b)(2)(xliii) to require submittals of analyses 
performed under IWB-3720, Nonmandatory Appendix A, subparagraph A-
4200(c), and Nonmandatory Appendix G, subparagraph G-2110(c). The 
condition on regulatory submittal requirements does not constitute a 
new or changed NRC position. Therefore, the addition of this condition 
is not a backfit.

ASME OM Code

    1. Revise Sec.  50.55a(a)(1)(iv) to remove the incorporation by 
reference of the 2011 Addenda and the 2015 Edition of the ASME OM Code, 
as well as make corresponding changes to Sec.  50.55a(b)(3)(iv), (vii), 
and (ix) to reflect that the 2011 Addenda and the 2015 Edition are not 
incorporated by reference in Sec.  50.55a. These changes remove 
editions of the code that are not in use. The revisions do not modify 
the current IST regulatory requirements and, therefore, are not 
backfits.
    2. Revise Sec.  50.55a(b)(3) to be consistent with the removal of 
specific editions or addenda from Sec.  50.55a(a)(1)(iv). These changes 
to Sec.  50.55a(b)(3) are editorial and, therefore, are not backfits.
    3. Revise Sec.  50.55a(b)(3)(viii) to specify that the condition on 
the use of Subsection ISTE applies through the 2017 Edition of the ASME 
OM Code incorporated by reference in Sec.  50.55a(a)(1)(iv). This 
change allows the use of Subsection ISTE in the 2020 Edition of the 
ASME OM Code without conditions and, therefore, is not a backfit.
    4. Revise Sec.  50.55a(b)(3)(xi) to allow increased flexibility in 
the schedule for position verification testing of valves not 
susceptible to stem-disk separation. The final rule also allows 
schedule flexibility for the initial ASME OM Code, Subsection ISTC, 
paragraph ISTC-3700 testing as supplemented by paragraph (b)(3)(xi) by 
the date 2 years after the previous ISTC-3700 test where plant 
conditions make such testing impractical. These changes allow increased 
flexibility in the testing interval where justified and, therefore, are 
not a backfit.
    5. Revise Sec.  50.55a(f)(4) to clarify the relationship between 
Sec.  50.55a(f)(4) and (g)(4) regarding the IST and ISI programs for 
dynamic restraints (snubbers). This modification reflects a 
clarification of Sec.  50.55a(f)(4) and (g)(4) and, therefore, is not a 
backfit.
    6. Add Sec.  50.55a(f)(7) to state that IST Plans for pumps, 
valves, and dynamic restraints (snubbers) must be submitted to the NRC. 
This requirement was specified in the ASME OM Code up to the 2020 
Edition, but ASME removed this requirement from the 2020 Edition of the 
ASME OM Code as more appropriate to the regulatory authority 
responsibilities. Therefore, this rule change is not a backfit because 
the NRC is maintaining the current requirement and is not imposing a 
new requirement.
    7. Modify Sec.  50.55a(g)(4) to clarify the relationship between 
Sec.  50.55a(f)(4) and (g)(4) regarding the IST and ISI programs for 
dynamic restraints (snubbers). This modification reflects a 
clarification of Sec.  50.55a(f)(4) and (g)(4) and, therefore, is not a 
backfit.

Conclusion

    The NRC finds that incorporation by reference into Sec.  50.55a of 
the 2019 Edition of Section III, Division 1, of the ASME BPV Code 
subject to the identified conditions; the 2019 Edition of Section XI, 
Division 1, of the ASME BPV Code, subject to the identified conditions; 
and the 2020 Edition of the ASME OM Code subject to the identified 
conditions, does not constitute backfitting or represent an 
inconsistency with any issue finality provisions in 10 CFR part 52.

X. 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 
31883).

XI. Environmental Assessment and Final Finding of No Significant 
Environmental Impact

    This final rule action is in accordance with the NRC's policy to 
incorporate by reference in Sec.  50.55a new editions and addenda of 
the ASME BPV and OM Codes to provide updated rules for constructing and 
inspecting components and testing pumps, valves, and dynamic restraints 
(snubbers) in light-water nuclear power plants. The ASME Codes are 
national voluntary consensus standards and are required by the NTTAA to 
be used by Government agencies unless the use of such a standard is 
inconsistent with applicable law or otherwise impractical. The National 
Environmental Policy Act (NEPA) requires Federal agencies to study the 
impacts of their major Federal actions significantly affecting the

[[Page 65145]]

quality of the human environment, and prepare detailed statements on 
the environmental impacts of the proposed action and alternatives to 
the proposed action (42 U.S.C. 4332(C); NEPA Sec. 102(C)).
    The NRC has determined under NEPA, as amended, and the NRC's 
regulations in subpart A of 10 CFR part 51, that this rule is not a 
major Federal action significantly affecting the quality of the human 
environment and, therefore, an environmental impact statement is not 
required. The rulemaking does not significantly increase the 
probability or consequences of accidents, no changes are being made in 
the types of effluents that may be released off-site, and there is no 
significant increase in public radiation exposure. The NRC concludes 
that the increase in occupational exposure would not be significant. 
This final rule does not involve non-radiological plant effluents and 
has no other environmental impact. Therefore, no significant non-
radiological impacts are associated with this action. The determination 
of this environmental assessment is that there will be no significant 
off-site impact to the public from this action.

XII. 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 (OMB), approval number 3150-0011.
    Because the rule will reduce the burden for existing information 
collections, the public burden for the information collections is 
expected to be decreased by 240 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 ISI and IST programs. The records are generally 
historical in nature and provide data on which future activities can be 
based. The practical utility of the information collection for the NRC 
is that appropriate records are available for auditing by NRC personnel 
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, or whether specific 
enforcement actions are necessary. Responses to this collection of 
information are generally 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-2018-0290.
     Mail comments to: FOIA, Library, and Information 
Collections Branch, Office of the Chief Information Officer, Mail Stop: 
T6-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.

XIII. 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.

XIV. Voluntary Consensus Standards

    The National Technology Transfer and Advancement Act of 1995, 
Public Law 104-113 (NTTAA), and implementing guidance in U.S. Office of 
Management and Budget (OMB) Circular A-119 (revised on January 27, 
2016), 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. The NTTAA requires Federal agencies to use 
industry consensus standards to the extent practical; it does not 
require Federal agencies to endorse a standard in its entirety. Neither 
the NTTAA nor Circular A-119 prohibit an agency from adopting a 
voluntary consensus standard while taking exception to specific 
portions of the standard, if those provisions are deemed to be 
``inconsistent with applicable law or otherwise impractical.'' 
Furthermore, taking specific exceptions furthers the Congressional 
intent of Federal reliance on voluntary consensus standards because it 
allows the adoption of substantial portions of consensus standards 
without the need to reject the standards in their entirety because of 
limited provisions that are not acceptable to the agency.
    In this final rule, the NRC is continuing its existing practice of 
establishing requirements for the design, construction, operation, ISI 
(examination) and IST of nuclear power plants by approving the use of 
the latest editions and addenda of the ASME BPV and OM Codes (ASME 
Codes) in Sec.  50.55a. The ASME Codes are voluntary consensus 
standards, developed by participants with broad and varied interests, 
in which all interested parties (including the NRC and licensees of 
nuclear power plants) participate. Therefore, the NRC's incorporation 
by reference of the ASME Codes is consistent with the overall 
objectives of the NTTAA and OMB Circular A-119.
    In this final rule, the NRC also is continuing its existing 
practice of approving the use of an ASME OM Code Case, which is an 
ASME-approved alternative to compliance with various provisions of the 
ASME OM Code. The ASME Code Cases are national consensus standards as 
defined in the NTTAA 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. Therefore, the NRC's approval of the use of the ASME Code 
Case in this final rule is consistent with the overall objectives of 
the NTTAA and OMB Circular A-119.
    As discussed in Section II of this document, this final rule 
conditions the use of certain provisions of the 2019 Edition to the 
ASME BPV Code, Section III, Division 1 and the ASME BPV Code, Section 
XI, Division 1, as well as the 2020 Edition to the ASME OM Code. This 
final rule also includes the 2011 Addenda to ASME NQA-1-2008, (ASME 
NQA-1b-2011), the 2012 and 2015 Editions of ASME NQA-1, and Code Case 
OMN-28. In addition, this final rule does not adopt (``excludes'') 
certain provisions of the ASME Codes as discussed in this document, and 
in the regulatory and backfit analyses for this final rule. The NRC 
finds that this final rule complies with the NTTAA and OMB Circular A-
119 despite these conditions and ``exclusions.''
    If the NRC did not conditionally accept the ASME editions and 
addenda, the NRC would disapprove them entirely. The effect would be 
that licensees and applicants would submit a larger number of requests 
for the use of alternatives under Sec.  50.55a(z), requests for relief 
under Sec.  50.55a(f) and (g), or requests for exemptions under

[[Page 65146]]

Sec.  50.12 and/or Sec.  52.7. These requests would likely include 
broad-scope requests for approval to issue the full scope of the ASME 
Code editions and addenda which would otherwise be approved in this 
final rule (i.e., the request would not be simply for approval of a 
specific ASME Code provision with conditions). These requests would be 
an unnecessary additional burden for both the licensee and the NRC, 
inasmuch as the NRC has already determined that the ASME Codes and Code 
Case that are the subject of this final rule are acceptable for use (in 
some cases with conditions). For these reasons, the NRC concludes that 
this final rule's treatment of ASME Code editions and addenda any 
conditions placed on them does not conflict with any policy on agency 
use of consensus standards specified in OMB Circular A-119.
    The NRC did not identify any other voluntary consensus standards 
developed by U.S. voluntary consensus standards bodies for use within 
the U.S. that the NRC could incorporate by reference instead of the 
ASME Codes. The NRC also did not identify any voluntary consensus 
standards developed by multinational voluntary consensus standards 
bodies for use on a multinational basis that the NRC could incorporate 
by reference instead of the ASME Codes. The NRC identified codes 
addressing the same subject as the ASME Codes for use in individual 
countries. At least one country, Korea, directly translated the ASME 
Code for use in that country. In other countries (e.g., Japan), the 
ASME Codes were the basis for development of the country's codes, but 
the ASME Codes were substantially modified to accommodate that 
country's regulatory system and reactor designs. Finally, there are 
countries (e.g., the Russian Federation) where that country's code was 
developed without regard to the ASME Code. However, some of these codes 
may not meet the definition of a voluntary consensus standard because 
they were developed by the state rather than a voluntary consensus 
standards body. Evaluation by the NRC of the countries' codes to 
determine whether each code provides a comparable or enhanced level of 
safety when compared against the level of safety provided under the 
ASME Codes would require a significant expenditure of agency resources. 
This expenditure does not seem justified, given that substituting 
another country's code for the U.S. voluntary consensus standard does 
not appear to substantially further the apparent underlying objectives 
of the NTTAA.
    In summary, this final rule satisfies the requirements of the NTTAA 
and OMB Circular A-119.

XV. Incorporation by Reference--Reasonable Availability to Interested 
Parties

    The NRC is incorporating by reference two recent editions to the 
ASME Codes for nuclear power plants. The NRC also is incorporating by 
reference the ASME OM Code Case OMN-28, ``Alternative Valve Position 
Verification Approach to Satisfy ISTC-3700 for Valves Not Susceptible 
to Stem-Disk Separation,'' the 2011 Addenda to ASME NQA-1-2008, 
``Quality Assurance Requirements for Nuclear Facility Applications'' 
(ASME NQA-1b-2011), and the 2012 and 2015 Editions of ASME NQA-1, 
``Quality Assurance Requirements for Nuclear Facility Applications.'' 
As described in the ``Background'' and ``Discussion'' sections of this 
document, these materials contain standards for the design, 
fabrication, and inspection of nuclear power plant components.
    The NRC is required by law to obtain approval for incorporation by 
reference from the Office of the Federal Register (OFR). The OFR's 
requirements for incorporation by reference are set forth in 1 CFR part 
51. On November 7, 2014, the OFR adopted changes to its regulations 
governing incorporation by reference (79 FR 66267). The OFR regulations 
require an agency to discuss, in the preamble of the final rule, the 
ways that the materials it incorporates by reference are reasonably 
available to interested parties and how interested parties can obtain 
the materials. The discussion in this section complies with the 
requirement for final rules as set forth in Sec.  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 but vary with respect to the 
considerations for determining reasonable availability. Therefore, the 
NRC distinguishes between different classes of interested parties for 
the purposes of determining whether the material is ``reasonably 
available.'' The NRC considers the following to be classes of 
interested parties in NRC rulemakings with regard to the material to be 
incorporated by reference:
     Individuals and small entities regulated or otherwise 
subject to the NRC's regulatory oversight (this class also includes 
applicants and potential applicants for licenses and other NRC 
regulatory approvals) and who are subject to the material to be 
incorporated by reference by rulemaking. In this context, ``small 
entities'' has the same meaning as a ``small entity'' under 10 CFR 
2.810.
     Large entities otherwise subject to the NRC's regulatory 
oversight (this class also includes applicants and potential applicants 
for licenses and other NRC regulatory approvals) and who are subject to 
the material to be incorporated by reference by rulemaking. In this 
context, ``large entities'' are those that do 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 \3\ Indian 
tribes.
---------------------------------------------------------------------------

    \3\ State-recognized Indian tribes are not within the scope of 
10 CFR 2.315(c). However, for purposes of the NRC's compliance with 
1 CFR 51.5, ``interested parties'' includes a broad set of 
stakeholders, including 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 may wish to gain access 
to the materials that the NRC is incorporating by reference by 
rulemaking in order to participate in the rulemaking process.
    The NRC makes the materials to be incorporated by reference 
available for inspection to all interested parties, 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]. Interested parties may purchase 
a copy of the ASME materials from ASME at Three Park Avenue, New York, 
NY 10016, or at the ASME website https://www.asme.org/shop/standards. 
The materials are also accessible through third-party subscription 
services such as IHS (15 Inverness Way East, Englewood, CO 80112; 
https://global.ihs.com) and Thomson Reuters Techstreet (3916 Ranchero 
Drive, Ann Arbor, MI 48108; https://www.techstreet.com). The purchase 
prices for individual documents range from $225 to $720 and the cost to 
purchase all documents is approximately $9,000.
    For the class of interested parties constituting members of the 
general public who wish to gain access to the materials that are 
incorporated by reference in order to participate in the

[[Page 65147]]

rulemaking, the NRC recognizes that the $9,000 cost may be so high that 
the materials could be regarded as not reasonably available for 
purposes of commenting on this rulemaking, despite the NRC's actions to 
make the materials available at the NRC's PDR. Accordingly, the NRC 
requested that ASME consider enhancing public access to these materials 
during the public comment period. On April 14, 2020, ASME agreed to 
make the materials available online in a read-only electronic access 
format during the public comment period.
    During the public comment period, the ASME made publicly available 
the two editions to the ASME Codes for nuclear power plants, the 2011 
Addenda to ASME NQA-1-2008, and the 2012 and 2015 Editions of ASME NQA-
1 that the NRC proposed to incorporate by reference. ASME made these 
materials publicly available in read-only format at the ASME website 
https://go.asme.org/NRC-ASME. In addition, on March 16, 2021, ASME made 
Code Case OMN-28 available at the ASME website https://go.asme.org/OMcommittee.
    The materials are available to all interested parties in multiple 
ways and in a manner consistent with their interest in this final rule. 
Therefore, the NRC concludes that the materials the NRC is 
incorporating by reference in this final rule are reasonably available 
to all interested parties.

XVI. Availability of Guidance

    The NRC will not be issuing guidance for this final rule. The ASME 
BPV Code and OM Code provide direction for the performance of 
activities to satisfy the Code requirements for design, inservice 
inspection, and inservice testing of nuclear power plant structures, 
systems, and components (SSCs). In addition, the NRC provides guidance 
in this document for the implementation of the new conditions on the 
ASME BPV code and OM Code, as necessary. The NRC has a number of 
standard review plans (SRPs) that provide guidance to NRC reviewers and 
make communication and understanding of NRC review processes available 
to members of the public and the nuclear power industry. NUREG-0800, 
``Review of Safety Analysis Reports for Nuclear Power Plants,'' has 
numerous sections which discuss implementation of various aspects of 
the ASME BPV Code and OM Code (e.g., Sections 3.2.2, 3.8.1, 3.8.2, 
3.9.3, 3.9.6, 3.9.7, 3.9.8, 3.13, 5.2.1.1, 5.2.1.2, 5.2.4, and 6.6). 
The NRC also publishes Regulatory Guides and Generic Communications 
(i.e., Regulatory Issue Summaries and Information Notices) to 
communicate and clarify NRC technical or policy positions on regulatory 
matters which may contain guidance relative to this final rule.
    Revision 3 of NUREG-1482, ``Guidelines for Inservice Testing at 
Nuclear Power Plants,'' provides guidance for the development and 
implementation of IST programs at nuclear power plants. With direction 
provided in the ASME BPV and OM Codes, and guidance in this document, 
the NRC has determined that preparation of a separate guidance document 
is not necessary for this update to Sec.  50.55a. However, the NRC will 
consider preparing a revision to NUREG-1482 in the future to address 
the latest edition of the ASME OM Code incorporated by reference in 
Sec.  50.55a.

XVII. 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
                  Document                      link/Federal Register
                                                       citation
------------------------------------------------------------------------
                         Proposed Rule Documents
------------------------------------------------------------------------
Proposed Rule--Federal Register Document     86 FR 16087
 (March 26, 2021).
Draft Regulatory Analysis (March 2021).....  ML20178A448
------------------------------------------------------------------------
                          Final Rule Documents
------------------------------------------------------------------------
Final Regulatory Analysis (September 2022).  ML21267A092
NRC Responses to Public Comments: Final      ML21267A094
 Rule: American Society of Mechanical
 Engineers 2019-2020 Code Editions
 (September 2022).
Annotated Public Comments on Proposed Rule:  ML21267A098
 American Society of Mechanical Engineers
 2019-2020 Code Editions (September 2022).
------------------------------------------------------------------------
                            Related Documents
------------------------------------------------------------------------
Email from Louise Lund, NRC, to Allyson B.   ML21014A012
 Byk, ASME, ``NRC Request for Public Access
 to ASME Materials--Correction Needed
 (Docket No. NRC-2018-0290),'' January 5,
 2021.
Email from Louise Lund, NRC, to Allyson B.   ML20308A511
 Byk, ASME, ``NRC Request for Public Access
 to ASME Material the NRC Seeks to
 Incorporate by Reference into Its
 Regulations (Docket No. NRC-2018-0290),''
 October 22, 2020.
Email from Louise Lund, NRC, to Christian    ML20127H677
 A. Sanna, ASME, ``NRC Request for Public
 Access to ASME Material the NRC Seeks to
 Incorporate by Reference into Its
 Regulations (Docket No. NRC-2018-0290),''
 April 14, 2020.
Email from Christian A. Sanna, ASME, to      ML20127H684
 Louise Lund, NRC, ``NRC Request for Public
 Access to ASME Material the NRC Seeks to
 Incorporate by Reference into Its
 Regulations (Docket No. NRC-2018-0290),''
 April 14, 2020.
Summary of the May 6, 2021, Public Meeting   ML21139A222
 on the Proposed Rule to Incorporate by
 Reference the 2019 and 2020 Editions of
 ASME Codes into 10 CFR 50.55a.
Summary of the June 4, 2020, Public Meeting  ML20163A609
 with the Nuclear Industry to Discuss Title
 10 of the Code of Federal Regulations,
 Section 50.55a(b)(xxvi) Condition of
 Pressure Testing of Class 1, 2, and 3
 Mechanical Joints.
Summary of the June 25, 2020, Public         ML20189A286
 Meeting with the Nuclear Industry to
 Discuss Title 10 of the Code of Federal
 Regulations, Section 50.55a(b)(xxvi)
 Condition of Pressure Testing of Class 1,
 2, and 3 Mechanical Joints.
Staff Requirements Memorandum--Affirmation   ML003755050
 Session, 11:30 a.m., Friday, September 10,
 1999, Commissioners' Conference Room, One
 White Flint North, Rockville, Maryland
 (Open to Public Attendance).

[[Page 65148]]

 
Enforcement Guidance Memorandum 14-003,      ML14169A582
 ``Enforcement Discretion not to Cite
 Violations Involving Bolt and Stud Non-
 Destructive Examination Qualification
 Programs, while Rulemaking Changes are
 Being Developed,'' January 16, 2015.
Information to Licensees Regarding Two NRC   ML031140549
 Inspection Manual Sections on Resolution
 of Degraded and Nonconforming Conditions
 and on Operability (Generic Letter 91-18),
 November 7, 1991.
NRC Regulatory Issue Summary 2004-16, ``Use  ML042590067
 of Later Editions and Addenda to ASME Code
 Section XI for Repair/Replacement
 Activities,'' October 19, 2004.
Regulatory Guide 1.28, Revision 5,           ML17207A293
 ``Quality Assurance Program Criteria
 (Design and Construction),'' October 2017.
Regulatory Guide 1.147, Revision 19,         ML19128A244
 ``Inservice Inspection Code Case
 Acceptability, ASME Section XI, Division
 1,'' October 2019.
Regulatory Guide 1.178, Revision 1, ``An     ML032510128
 Approach for Plant-Specific Risk-Informed
 Decisionmaking for Inservice Inspection of
 Piping,'' September 2003.
Regulatory Guide 1.200, Revision 2, ``An     ML090410014
 Approach for Determining the Technical
 Adequacy of Probabilistic Risk Assessment
 Results for Risk-Informed Activities,''
 March 2009.
NUREG-0800, NRC Standard Review Plan for     ML032510135
 the Review of Safety Analysis Reports for
 Nuclear Power Plants: LWR Edition (NUREG-
 0800), Chapter 3.9.8, ``Risk-Informed
 Inservice Inspection of Piping,''
 September 2003.
NUREG-1339, ``Resolution of Generic Safety   ML031430208
 Issue 29: Bolting Degradation or Failure
 in Nuclear Power Plants,'' June 1990.
NUREG-1482, Revision 3, ``Guidelines for     ML20202A473
 Inservice Testing at Nuclear Power
 Plants,'' July 2020.
NUREG-1801, Revision 2, ``Generic Aging      ML103490041
 Lessons Learned (GALL) Report,'' December
 2010.
NUREG-1800, Revision 2, ``Standard Review    ML103490036
 Plan for Review of License Renewal
 Applications for Nuclear Power Plants,''
 December 2010.
NUREG-2191, Vols. 1 and 2, ``Generic Aging   ML17187A031
 Lessons Learned for Subsequent License      ML17187A204
 Renewal (GALL-SLR) Report,'' July 2017.
NUREG-1950, ``Disposition of Public          ML11116A062
 Comments and Technical Bases for Changes
 in the License Renewal Guidance Documents
 NUREG-1801 and NUREG-1800,'' April 2011.
NUREG-2192, ``Standard Review Plan for       ML17188A158
 Review of Subsequent License Renewal
 Applications for Nuclear Power Plants,''
 July 2017.
Report Number PNNL-29761, ``Nondestructive   ML20079E343
 Examination (NDE) Training and
 Qualifications: Implications of Research
 on Human Learning and Memory, Instruction
 and Expertise,'' March 2020.
------------------------------------------------------------------------
                        ASME Codes and Standards
------------------------------------------------------------------------
ASME BPV Code, Section III, Division 1:      https://go.asme.org/NRC-
 2019 Edition.                                ASME
ASME BPV Code, Section XI, Division 1: 2019  https://go.asme.org/NRC-
 Edition.                                     ASME
ASME OM Code, Division 1: 2020 Edition.....  https://go.asme.org/NRC-ASME ASME
ASME OM Code Case OMN-28, ``Alternative      https://go.asme.org/
 Valve Position Verification Approach to      OMcommittee
 Satisfy ISTC-3700 for Valves Not
 Susceptible to Stem-Disk Separation''.
ASME NQA-1b-2011, ``Quality Assurance        https://go.asme.org/NRC-
 Requirements for Nuclear Facility            ASME
 Applications'' (2011 Addenda).
ASME NQA-1-2012, ``Quality Assurance         https://go.asme.org/NRC-
 Requirements for Nuclear Facility            ASME
 Applications''.
ASME NQA-1-2015, ``Quality Assurance         https://go.asme.org/NRC-
 Requirements for Nuclear Facility            ASME
 Applications''.
------------------------------------------------------------------------

List of Subjects in 10 CFR Part 50

    Administrative practice and procedure, Antitrust, Backfitting, 
Classified information, Criminal penalties, Education, Emergency 
planning, Fire prevention, Fire protection, Incorporation by reference, 
Intergovernmental relations, Nuclear power plants and reactors, 
Penalties, Radiation protection, Reactor siting criteria, Reporting and 
recordkeeping requirements, Whistleblowing.

    For the reasons set forth 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. In paragraph (a)(1)(i)(E)(18), remove ``, and'' and add a semicolon 
in its place;
0
b. Revise paragraph (a)(1)(i)(E)(19) and add paragraph 
(a)(1)(i)(E)(20);
0
c. Revise and republish paragraphs (a)(1)(ii) through (iv), 
(a)(1)(v)(B), (b)(1), (b)(2) introductory text, and (b)(2)(viii) 
through (xiv);
0
d. In paragraph (b)(2)(xv) introductory text, remove the text ``the 
1995 Edition through'';
0
e. Revise and republish paragraphs (b)(2)(xviii) through (xxi), (xxv), 
(xxvi), (xxix), (xxxii), (xxxvi), and (xxxix);
0
f. Remove and reserve paragraph (b)(2)(xl);
0
g. Add paragraph (b)(2)(xliii);
0
h. In paragraph (b)(3) introductory text, remove the text ``1995 
Edition through the latest edition'' and add in its place the word 
``editions'';
0
i. Revise and republish paragraph (b)(3)(iii);
0
j. In paragraph (b)(3)(iv), remove the year ``2015'' and add in its 
place the year ``2012'' and remove the word ``shall'' and add in its 
place the word ``must'' everywhere it appears;

[[Page 65149]]

0
k. Remove and reserve paragraph (b)(3)(vii);
0
l. Revise and republish paragraphs (b)(3)(viii) through (xi) and 
(f)(4);
0
m. Add paragraph (f)(7); and
0
n. Revise paragraph (g)(4) introductory text.
    The revisions, republications, and additions read as follows:


Sec.  50.55a  Codes and standards.

    (a) * * *
    (1) * * *
    (i) * * *
    (E) * * *
    (19) 2017 Edition (including Subsection NCA; and Division 1 
subsections NB through NG and Appendices); and
    (20) 2019 Edition (including Subsection NCA; and Division 1 
subsections NB through NG and Appendices).
    (ii) ASME Boiler and Pressure Vessel Code, Section XI. The editions 
and addenda for Section XI of the ASME Boiler and Pressure Vessel Code 
are listed in this paragraph (a)(1)(ii), but limited by those 
provisions identified in paragraph (b)(2) of this section.
    (A) [Reserved]
    (B) ``Rules for Inservice Inspection of Nuclear Power Plant 
Components:''
    (1) 1974 Edition;
    (2) 1974 Summer Addenda;
    (3) 1974 Winter Addenda; and
    (4) 1975 Summer Addenda.
    (C) ``Rules for Inservice Inspection of Nuclear Power Plant 
Components--Division 1:''
    (1)-(32) [Reserved]
    (33) 1995 Edition;
    (34) 1995 Addenda;
    (35) 1996 Addenda;
    (36) 1997 Addenda;
    (37)-(40) [Reserved]
    (41) 2001 Edition;
    (42) 2001 Addenda;
    (43) 2002 Addenda;
    (44) 2003 Addenda;
    (45) 2004 Edition;
    (46) 2005 Addenda;
    (47) 2006 Addenda;
    (48) 2007 Edition;
    (49) 2008 Addenda;
    (50) 2009b Addenda;
    (51) 2010 Edition;
    (52) 2011a Addenda;
    (53) 2013 Edition;
    (54) 2015 Edition;
    (55) 2017 Edition; and
    (56) 2019 Edition.
    (iii) ASME Code Cases: Nuclear Components--(A) ASME BPV Code Case 
N-513-3 Mandatory Appendix I. ASME BPV Code Case N-513-3, ``Evaluation 
Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 
or 3 Piping Section XI, Division 1,'' Mandatory Appendix I, ``Relations 
for Fm, Fb, and F for Through-Wall Flaws'' (Approval Date: January 26, 
2009). ASME BPV Code Case N-513-3 Mandatory Appendix I is referenced in 
paragraph (b)(2)(xxxiv)(B) of this section.
    (B) ASME BPV Code Case N-722-1. ASME BPV Code Case N-722-1, 
``Additional Examinations for PWR Pressure Retaining Welds in Class 1 
Components Fabricated with Alloy 600/82/182 Materials, Section XI, 
Division 1'' (Approval Date: January 26, 2009), with the conditions in 
paragraph (g)(6)(ii)(E) of this section.
    (C) ASME BPV Code Case N-729-6. ASME BPV Code Case N-729-6, 
``Alternative Examination Requirements for PWR Reactor Vessel Upper 
Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds 
Section XI, Division 1'' (Approval Date: March 3, 2016), with the 
conditions in paragraph (g)(6)(ii)(D) of this section.
    (D) ASME BPV Code Case N-770-5. ASME BPV Code Case N-770-5, 
``Alternative Examination Requirements and Acceptance Standards for 
Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS 
N06082 or UNS W86182 Weld Filler Material With or Without Application 
of Listed Mitigation Activities Section XI, Division 1'' (Approval 
Date: November 7, 2016), with the conditions in paragraph (g)(6)(ii)(F) 
of this section.
    (E) [Reserved]
    (F) ASME BPV Code Case N-852. ASME BPV Code Case N-852, 
``Application of the ASME NPT Stamp, Section III, Division 1; Section 
III, Division 2; Section III, Division 3; Section III, Division 5'' 
(Approval Date: February 9, 2015). ASME BPV Code Case N-852 is 
referenced in paragraph (b)(1)(ix) of this section.
    (G) [Reserved]
    (H) ASME OM Code Case OMN-28. ASME OM Case OMN-28, ``Alternative 
Valve Position Verification Approach to Satisfy ISTC-3700 for Valves 
Not Susceptible to Stem-Disk Separation.'' Issued March 4, 2021. OMN-28 
is referenced in paragraph (b)(3)(xi) of this section.
    (iv) ASME Operation and Maintenance Code. The editions and addenda 
for the ASME Operation and Maintenance of Nuclear Power Plants are 
listed in this paragraph (a)(1)(iv), but limited by those provisions 
identified in paragraph (b)(3) of this section.
    (A) ``Code for Operation and Maintenance of Nuclear Power Plants:''
    (1) 1995 Edition;
    (2) 1996 Addenda;
    (3) 1997 Addenda;
    (4) 1998 Edition;
    (5) 1999 Addenda;
    (6) 2000 Addenda;
    (7) 2001 Edition;
    (8) 2002 Addenda;
    (9) 2003 Addenda;
    (10) 2004 Edition;
    (11) 2005 Addenda; and
    (12) 2006 Addenda.
    (B) ``Operation and Maintenance of Nuclear Power Plants, Division 
1: Section IST Rules for Inservice Testing of Light-Water Reactor Power 
Plants:''
    (1) 2009 Edition.
    (2) [Reserved]
    (C) Operation and Maintenance of Nuclear Power Plants:
    (1) 2012 Edition, ``Division 1: OM Code: Section IST'';
    (2) 2017 Edition; and
    (3) 2020 Edition.
    (v) * * *
    (B) ASME NQA-1, ``Quality Assurance Requirements for Nuclear 
Facility Applications:''
    (1) NQA-1--1994 Edition;
    (2) NQA-1--2008 Edition;
    (3) NQA-1a--2009;
    (4) NQA-1b--2011 Addenda;
    (5) NQA-1--2012; and
    (6) NQA-1--2015.
* * * * *
    (b) * * *
    (1) Conditions on ASME BPV Code Section III. Each manufacturing 
license, standard design approval, and design certification under 10 
CFR part 52 is subject to the following conditions. As used in this 
section, references to Section III refer to Section III of the ASME BPV 
Code and include the 1963 Edition through 1973 Winter Addenda and the 
1974 Edition (Division 1) through the latest edition and addenda 
incorporated by reference in paragraph (a)(1)(i) of this section, 
subject to the following conditions:
    (i) Section III condition: Section III materials. When applying the 
1992 Edition of Section III, applicants or licensees must apply the 
1992 Edition with the 1992 Addenda of Section II of the ASME Boiler and 
Pressure Vessel Code.
    (ii) Section III condition: Weld leg dimensions. When applying the 
1989 Addenda through the latest edition and addenda incorporated by 
reference in paragraph (a)(1) of this section, applicants and licensees 
may not apply the Section III provisions identified in table 1 to this 
paragraph (b)(1)(ii) for welds with leg size less than 1.09 
tn:

[[Page 65150]]



       Table 1 to Paragraph (b)(1)(ii)--Prohibited Code Provisions
------------------------------------------------------------------------
        Editions and addenda                    Code provision
------------------------------------------------------------------------
1989 Addenda through the latest      Subparagraph NB-3683.4(c)(1);
 edition and addenda incorporated     Subparagraph NB-3683.4(c)(2).
 by reference in paragraph
 (a)(1)(i) of this section.
1989 Addenda through 2003 Addenda..  Footnote 11 to Figure NC-3673.2(b)-
                                      1; Note 11 to Figure ND-3673.2(b)-
                                      1.
2004 Edition through 2010 Edition..  Footnote 13 to Figure NC-3673.2(b)-
                                      1; Note 13 to Figure ND-3673.2(b)-
                                      1.
2011 Addenda through the latest      Footnote 11 to Table NC-3673.2(b)-
 edition and addenda incorporated     1; Note 11 to Table ND-3673.2(b)-
 by reference in paragraph            1.
 (a)(1)(i) of this section.
------------------------------------------------------------------------

    (iii) Section III condition: Seismic design of piping. Applicants 
or licensees may use Subarticles NB-3200, NB-3600, NC-3600, and ND-3600 
for seismic design of piping, up to and including the 1993 Addenda, 
subject to the condition specified in paragraph (b)(1)(ii) of this 
section. Applicants or licensees may not use these subarticles for 
seismic design of piping in the 1994 Addenda through the 2005 Addenda 
incorporated by reference in paragraph (a)(1) of this section, except 
that Subarticle NB-3200 in the 2004 Edition through the 2017 Edition 
may be used by applicants and licensees, subject to the condition in 
paragraph (b)(1)(iii)(A) of this section. Applicants or licensees may 
use Subarticles NB-3600, NC-3600, and ND-3600 for the seismic design of 
piping in the 2006 Addenda through the latest edition and addenda 
incorporated by reference in paragraph (a)(1)(i) of this section, 
subject to the conditions of this paragraph (b)(1)(iii) corresponding 
to those subarticles.
    (A) Seismic design of piping: First provision. When applying Note 
(1) of Figure NB-3222-1 for Level B service limits, the calculation of 
Pb stresses must include reversing dynamic loads (including inertia 
earthquake effects) if evaluation of these loads is required by NB-
3223(b).
    (B) Seismic design of piping: Second provision. For Class 1 piping, 
the material and Do/t requirements of NB-3656(b) must be met for all 
Service Limits when the Service Limits include reversing dynamic loads, 
and the alternative rules for reversing dynamic loads are used.
    (iv) Section III condition: Quality assurance. When applying 
editions and addenda later than the 1989 Edition of Section III, an 
applicant or licensee may use the requirements of NQA-1, ``Quality 
Assurance Requirements for Nuclear Facility Applications,'' that is 
both incorporated by reference in paragraph (a)(1)(v) of this section 
and specified in either NCA-4000 or NCA-7000 of that Edition and 
Addenda of Section III, provided that the administrative, quality, and 
technical provisions contained in that Edition and Addenda of Section 
III are used in conjunction with the applicant's or licensee's appendix 
B to this part quality assurance program; and that the applicant's or 
licensee's Section III activities comply with those commitments 
contained in the applicant's or licensee's quality assurance program 
description. Where NQA-1 and Section III do not address the commitments 
contained in the applicant's or licensee's appendix B quality assurance 
program description, those licensee commitments must be applied to 
Section III activities.
    (v) Section III condition: Independence of inspection. Applicants 
or licensees may not apply the exception in NCA-4134.10(a) of Section 
III, 1995 Edition through 2009b Addenda of the 2007 Edition, from 
paragraph 3.1 of Supplement 10S-1 of NQA-1-1994 Edition.
    (vi) Section III condition: Subsection NH. The provisions in 
Subsection NH, ``Class 1 Components in Elevated Temperature Service,'' 
1995 Addenda through all editions and addenda up to and including the 
2013 Edition incorporated by reference in paragraph (a)(1) of this 
section, may only be used for the design and construction of Type 316 
stainless steel pressurizer heater sleeves where service conditions do 
not cause the components to reach temperatures exceeding 900 [deg]F.
    (vii) Section III condition: Capacity certification and 
demonstration of function of incompressible-fluid pressure-relief 
valves. When applying the 2006 Addenda through all editions and addenda 
up to and including the latest edition and addenda incorporated by 
reference in paragraph (a)(1)(i) of this section, applicants and 
licensees may use paragraph NB-7742, except that paragraph NB-
7742(a)(2) may not be used. For a valve design of a single size to be 
certified over a range of set pressures, the demonstration of function 
tests under paragraph NB-7742 must be conducted as prescribed in NB-
7732.2 on two valves covering the minimum set pressure for the design 
and the maximum set pressure that can be accommodated at the 
demonstration facility selected for the test.
    (viii) Section III condition: Use of ASME certification marks. When 
applying editions and addenda earlier than the 2011 Addenda to the 2010 
Edition, licensees may use either the ASME BPV Code Symbol Stamps or 
the ASME Certification Marks with the appropriate certification 
designators and class designators as specified in the 2013 Edition 
through the latest edition and addenda incorporated by reference in 
paragraph (a)(1) of this section.
    (ix) Section III Condition: NPT Code Symbol Stamps. Licensees may 
use the NPT Code Symbol Stamp with the letters arranged horizontally as 
specified in ASME BPV Code Case N-852 for the service life of a 
component that had the NPT Code Symbol Stamp applied during the time 
period from January 1, 2005, through December 31, 2015.
    (x) Section III Condition: Visual examination of bolts, studs and 
nuts. Applicants or licensees applying the provisions of NB-2582, NC-
2582, ND-2582, NE-2582, NF-2582, NG-2582 in the 2017 Edition of Section 
III through the latest edition and addenda incorporated by reference in 
paragraph (a)(1)(i) of this section, must apply paragraphs (b)(1)(x)(A) 
and (B) of this section.
    (A) Visual examination of bolts, studs, and nuts: First provision. 
When applying the provisions of NB-2582, NC-2582, ND-2582, NE-2582, NF-
2582, NG-2582 in the 2017 Edition of Section III through the latest 
edition and addenda incorporated by reference in paragraph (a)(1)(i) of 
this section, the visual examinations are required to be performed in 
accordance with procedures qualified to NB-5100, NC-5100, ND-5100, NE-
5100, NF-5100, NG-5100 and performed by personnel qualified in 
accordance with NB-5500, NC-5500, ND-5500, NE-5500, NF-5500, and NG-
5500.
    (B) Visual examination of bolts, studs, and nuts: Second provision. 
When applying the provisions of NB-2582, NC-2582, ND-2582, NE-2582, NF-

[[Page 65151]]

2582, and NG-2582 in the 2017 Edition of Section III through the latest 
edition and addenda incorporated by reference in paragraph (a)(1)(i) of 
this section, bolts, studs, and nuts must be visually examined for 
discontinuities including cracks, bursts, seams, folds, thread lap, 
voids, and tool marks.
    (xi) Section III condition: Mandatory Appendix XXVI. When applying 
the 2015 and 2017 Editions of Section III, Mandatory Appendix XXVI, 
``Rules for Construction of Class 3 Buried Polyethylene Pressure 
Piping,'' applicants or licensees must meet the following conditions:
    (A) Mandatory Appendix XXVI: First provision. When performing 
fusing procedure qualification testing in accordance with XXVI-2300 and 
XXVI-4330 the following essential variables must be used for the 
performance qualification tests of butt fusion joints:
    (1) Joint Type: A change in the type of joint from that qualified, 
except that a square butt joint qualifies as a mitered joint.
    (2) Pipe Surface Alignment: A change in the pipe outside diameter 
(O.D.) surface misalignment of more than 10 percent of the wall 
thickness of the thinner member to be fused.
    (3) PE Material: Each lot of polyethylene source material to be 
used in production (XXVI-2310(c)).
    (4) Wall Thickness: Each thickness to be fused in production (XXVI-
2310(c)).
    (5) Diameter: Each diameter to be fused in production (XXVI-
2310(c)).
    (6) Cross-sectional Area: Each combination of thickness and 
diameter (XXVI-2310(c)).
    (7) Position: Maximum machine carriage slope when greater than 20 
degrees from horizontal (XXVI-4321(c)).
    (8) Heater Surface Temperature: A change in the heater surface 
temperature to a value beyond the range tested (XXVI-2321).
    (9) Ambient Temperature: A change in ambient temperature to less 
than 50 [deg]F (10 [deg]C) or greater than 125 [deg]F (52 [deg]C) 
(XXVI-4412(b)).
    (10) Interfacial Pressure: A change in interfacial pressure to a 
value beyond the range tested (XXVI-2321).
    (11) Decrease in Melt Bead Width: A decrease in melt bead size from 
that qualified.
    (12) Increase in Heater Removal Time: An increase in heater plate 
removal time from that qualified.
    (13) Decrease in Cool-down Time: A decrease in the cooling time at 
pressure from that qualified.
    (14) Fusing Machine Carriage Model: A change in the fusing machine 
carriage model from that tested (XXVI-2310(d)).
    (B) Mandatory Appendix XXVI: Second provision. When performing 
procedure qualification for high speed tensile impact testing of butt 
fusion joints in accordance with XXVI-2300 or XXVI-4330, breaks in the 
specimen that are away from the fusion zone must be retested. When 
performing fusing operator qualification bend tests of butt fusion 
joints in accordance with XXVI-4342, guided side bend testing must be 
used for all thicknesses greater than 1.25 inches.
    (C) Mandatory Appendix XXVI: Third provision. When performing 
fusing procedure qualification tests in accordance with 2017 Edition of 
BPV Code Section III XXVI-2300 and XXVI-4330, the following essential 
variables must be used for the testing of electrofusion joints:
    (1) Joint Design: A change in the design of an electrofusion joint.
    (2) Fit-up Gap: An increase in the maximum radial fit-up gap 
qualified.
    (3) Pipe PE Material: A change in the PE designation or cell 
classification of the pipe from that tested (XXVI-2322(a)).
    (4) Fitting PE Material: A change in the manufacturing facility or 
production lot from that tested (XXVI-2322(b)).
    (5) Pipe Wall Thickness: Each thickness to be fused in production 
(XXVI-2310(c)).
    (6) Fitting Manufacturer: A change in fitting manufacturer.
    (7) Pipe Diameter: Each diameter to be fused in production (XXVI-
2310(c)).
    (8) Cool-down Time: A decrease in the cool time at pressure from 
that qualified.
    (9) Fusion Voltage: A change in fusion voltage.
    (10) Nominal Fusion Time: A change in the nominal fusion time.
    (11) Material Temperature Range: A change in material fusing 
temperature beyond the range qualified.
    (12) Power Supply: A change in the make or model of electrofusion 
control box (XXVI-2310(f)).
    (13) Power Cord: A change in power cord material, length, or 
diameter that reduces current at the coil to below the minimum 
qualified.
    (14) Processor: A change in the manufacturer or model number of the 
processor. (XXVI-2310(f)).
    (15) Saddle Clamp: A change in the type of saddle clamp.
    (16) Scraping Device: A change from a clean peeling scraping tool 
to any other type of tool.
    (xii) Section III condition: Certifying Engineer. When applying the 
2017 and later editions of ASME BPV Code Section III, the NRC does not 
permit applicants and licensees to use a Certifying Engineer who is not 
a Registered Professional Engineer qualified in accordance with 
paragraph XXIII-1222 for Code-related activities that are applicable to 
U.S. nuclear facilities regulated by the NRC. The use of paragraph 
XXIII-1223 is prohibited.
    (xiii) Section III Condition: Preservice Inspection of Steam 
Generator Tubes. Applicants or licensees applying the provisions of NB-
5283 and NB-5360 in the 2019 Edition of Section III, must apply 
paragraphs (b)(1)(xiii)(A) and (B) of this section.
    (A) Preservice Inspection of Steam Generator Tubes: First 
provision. When applying the provisions of NB-5283 in the 2019 Edition 
of Section III, a full-length preservice examination of 100 percent of 
the steam generator tubing in each newly installed steam generator must 
be performed prior to plant startup.
    (B) Preservice Inspection of Steam Generator Tubes: Second 
provision. When applying the provisions of NB-5360 in the 2019 Edition 
of Section III, flaws revealed during preservice examination of steam 
generator tubing performed in accordance with paragraph (b)(1)(xiii)(A) 
of this section must be evaluated using the criteria in the design 
specifications.
    (2) Conditions on ASME BPV Code, Section XI. As used in this 
section, references to Section XI refer to Section XI, Division 1, of 
the ASME BPV Code, and include the 1970 Edition through the 1976 Winter 
Addenda and the 1977 Edition through the latest edition incorporated by 
reference in paragraph (a)(1)(ii) of this section, subject to the 
following conditions:
* * * * *
    (viii) Section XI condition: Concrete containment examinations. 
Applicants or licensees applying Subsection IWL, 2001 Edition through 
the 2004 Edition, up to and including the 2006 Addenda, must apply 
paragraphs (b)(2)(viii)(E) through (G) of this section. Applicants or 
licensees applying Subsection IWL, 2007 Edition up to and including the 
2008 Addenda must apply paragraph (b)(2)(viii)(E) of this section. 
Applicants or licensees applying Subsection IWL, 2007 Edition with the 
2009 Addenda through the latest edition and addenda incorporated by 
reference in paragraph (a)(1)(ii) of this section, must apply 
paragraphs (b)(2)(viii)(H) and (I) of this section.
    (A)-(D) [Reserved]
    (E) Concrete containment examinations: Fifth provision. For Class 
CC applications, the applicant or licensee must evaluate the 
acceptability of inaccessible areas when conditions exist in accessible 
areas that could indicate the presence of or the result in

[[Page 65152]]

degradation to such inaccessible areas. For each inaccessible area 
identified, the applicant or licensee must provide the following in the 
ISI Summary Report required by IWA-6000:
    (1) A description of the type and estimated extent of degradation, 
and the conditions that led to the degradation;
    (2) An evaluation of each area, and the result of the evaluation; 
and
    (3) A description of necessary corrective actions.
    (F) Concrete containment examinations: Sixth provision. Personnel 
that examine containment concrete surfaces and tendon hardware, wires, 
or strands must meet the qualification provisions in IWA-2300. The 
``owner-defined'' personnel qualification provisions in IWL-2310(d) are 
not approved for use.
    (G) Concrete containment examinations: Seventh provision. Corrosion 
protection material must be restored following concrete containment 
post-tensioning system repair and replacement activities in accordance 
with the quality assurance program requirements specified in IWA-1400.
    (H) Concrete containment examinations: Eighth provision. For each 
inaccessible area of concrete identified for evaluation under IWL-
2512(a), or identified as susceptible to deterioration under IWL-
2512(b), the licensee must provide the applicable information specified 
in paragraphs (b)(2)(viii)(E)(1), (2), and (3) of this section in the 
ISI Summary Report required by IWA-6000.
    (I) Concrete containment examinations: Ninth provision. During the 
period of extended operation of a renewed license under part 54 of this 
chapter, the licensee must perform the technical evaluation under IWL-
2512(b) of inaccessible below-grade concrete surfaces exposed to 
foundation soil, backfill, or groundwater at periodic intervals not to 
exceed 5 years. In addition, the licensee must examine representative 
samples of the exposed portions of the below-grade concrete, when such 
below-grade concrete is excavated for any reason.
    (ix) Section XI condition: Metal containment examinations. 
Applicants or licensees applying Subsection IWE, 2001 Edition up to and 
including the 2003 Addenda, must satisfy the requirements of paragraphs 
(b)(2)(ix)(A) and (B), (F) through (I), and (K) of this section. 
Applicants or licensees applying Subsection IWE, 2004 Edition, up to 
and including the 2005 Addenda, must satisfy the requirements of 
paragraphs (b)(2)(ix)(A) and (B), (F) through (H), and (K) of this 
section. Applicants or licensees applying Subsection IWE, 2004 Edition 
with the 2006 Addenda, must satisfy the requirements of paragraphs 
(b)(2)(ix)(A)(2) and (b)(2)(ix)(B) and (K) of this section. Applicants 
or licensees applying Subsection IWE, 2007 Edition through the 2015 
Edition, must satisfy the requirements of paragraphs (b)(2)(ix)(A)(2) 
and (b)(2)(ix)(B), (J), and (K) of this section. Applicants or 
licensees applying Subsection IWE, 2017 Edition, through the latest 
edition and addenda incorporated by reference in paragraph (a)(1)(ii) 
of this section must satisfy the requirements of paragraphs 
(b)(2)(ix)(A)(2) and (b)(2)(ix)(B) and (J) of this section.
    (A) Metal containment examinations: First provision. For Class MC 
applications, the following apply to inaccessible areas.
    (1) The applicant or licensee must evaluate the acceptability of 
inaccessible areas when conditions exist in accessible areas that could 
indicate the presence of or could result in degradation to such 
inaccessible areas.
    (2) For each inaccessible area identified for evaluation, the 
applicant or licensee must provide the following in the ISI Summary 
Report as required by IWA-6000:
    (i) A description of the type and estimated extent of degradation, 
and the conditions that led to the degradation;
    (ii) An evaluation of each area, and the result of the evaluation; 
and
    (iii) A description of necessary corrective actions.
    (B) Metal containment examinations: Second provision. When 
performing remotely the visual examinations required by Subsection IWE, 
the maximum direct examination distance specified in Table IWA-2210-1 
(2001 Edition through 2004 Edition) or Table IWA-2211-1 (2005 Addenda 
through the latest edition and addenda incorporated by reference in 
paragraph (a)(1) of this section) may be extended and the minimum 
illumination requirements specified may be decreased provided that the 
conditions or indications for which the visual examination is performed 
can be detected at the chosen distance and illumination.
    (C)-(E) [Reserved]
    (F) Metal containment examinations: Sixth provision. VT-1 and VT-3 
examinations must be conducted in accordance with IWA-2200. Personnel 
conducting examinations in accordance with the VT-1 or VT-3 examination 
method must be qualified in accordance with IWA-2300. The ``owner-
defined'' personnel qualification provisions in IWE-2330(a) for 
personnel that conduct VT-1 and VT-3 examinations are not approved for 
use.
    (G) Metal containment examinations: Seventh provision. The VT-3 
examination method must be used to conduct the examinations in Items 
E1.12 and E1.20 of Table IWE-2500-1, and the VT-1 examination method 
must be used to conduct the examination in Item E4.11 of Table IWE-
2500-1. An examination of the pressure-retaining bolted connections in 
Item E1.11 of Table IWE-2500-1 using the VT-3 examination method must 
be conducted once each interval. The ``owner-defined'' visual 
examination provisions in IWE-2310(a) are not approved for use for VT-1 
and VT-3 examinations.
    (H) Metal containment examinations: Eighth provision. Containment 
bolted connections that are disassembled during the scheduled 
performance of the examinations in Item E1.11 of Table IWE-2500-1 must 
be examined using the VT-3 examination method. Flaws or degradation 
identified during the performance of a VT-3 examination must be 
examined in accordance with the VT-1 examination method. The criteria 
in the material specification or IWB-3517.1 must be used to evaluate 
containment bolting flaws or degradation. As an alternative to 
performing VT-3 examinations of containment bolted connections that are 
disassembled during the scheduled performance of Item E1.11, VT-3 
examinations of containment bolted connections may be conducted 
whenever containment bolted connections are disassembled for any 
reason.
    (I) Metal containment examinations: Ninth provision. The ultrasonic 
examination acceptance standard specified in IWE-3511.3 for Class MC 
pressure-retaining components must also be applied to metallic liners 
of Class CC pressure-retaining components.
    (J) Metal containment examinations: Tenth provision. In general, a 
repair/replacement activity such as replacing a large containment 
penetration, cutting a large construction opening in the containment 
pressure boundary to replace steam generators, reactor vessel heads, 
pressurizers, or other major equipment; or other similar modification 
is considered a major containment modification. When applying IWE-5000 
to Class MC pressure-retaining components, any major containment 
modification or repair/replacement must be followed by a Type A test to 
provide assurance of both containment structural integrity and leak-
tight integrity prior to returning to service, in accordance with

[[Page 65153]]

appendix J to this part, Option A or Option B, on which the applicant's 
or licensee's Containment Leak-Rate Testing Program is based. When 
applying IWE-5000, if a Type A, B, or C Test is performed, the test 
pressure and acceptance standard for the test must be in accordance 
with appendix J to this part.
    (K) Metal Containment Examinations: Eleventh provision. A general 
visual examination of containment leak chase channel moisture barriers 
must be performed once each interval, in accordance with the completion 
percentages in Table IWE 2411-1 of the 2017 Edition. Examination shall 
include the moisture barrier materials (caulking, gaskets, coatings, 
etc.) that prevent water from accessing the embedded containment liner 
within the leak chase channel system. Caps of stub tubes extending to 
or above the concrete floor interface may be inspected, provided the 
configuration of the cap functions as a moisture barrier as described 
previously. Leak chase channel system closures need not be disassembled 
for performance of examinations if the moisture barrier material is 
clearly visible without disassembly, or coatings are intact. The 
closures are acceptable if no damage or degradation exists that would 
allow intrusion of moisture against inaccessible surfaces of the metal 
containment shell or liner within the leak chase channel system. 
Examinations that identify flaws or relevant conditions shall be 
extended in accordance with paragraph IWE 2430 of the 2017 Edition.
    (x) Section XI condition: Quality assurance. When applying the 
editions and addenda later than the 1989 Edition of ASME BPV Code, 
Section XI, licensees may use any edition or addenda of NQA-1, 
``Quality Assurance Requirements for Nuclear Facility Applications,'' 
that is both incorporated by reference in paragraph (a)(1)(v) of this 
section and specified in Table IWA 1600-1 of that edition and addenda 
of Section XI, provided that the licensee uses its appendix B to this 
part quality assurance program in conjunction with Section XI 
requirements and the commitments contained in the licensee's quality 
assurance program description. Where NQA-1 and Section XI do not 
address the commitments contained in the licensee's appendix B quality 
assurance program description, those licensee commitments must be 
applied to Section XI activities.
    (xi) [Reserved]
    (xii) Section XI condition: Underwater welding. The provisions in 
IWA-4660, ``Underwater Welding,'' of Section XI, 2001 Edition through 
the latest edition and addenda incorporated by reference in paragraph 
(a)(1)(ii) of this section, are approved for use on irradiated material 
with the following conditions:
    (A) Underwater welding: First provision. Licensees must obtain NRC 
approval in accordance with paragraph (z) of this section regarding the 
welding technique to be used prior to performing welding on ferritic 
material exposed to fast neutron fluence greater than 1 x 10\17\ n/
cm\2\ (E > 1 MeV).
    (B) Underwater welding: Second provision. Licensees must obtain NRC 
approval in accordance with paragraph (z) of this section regarding the 
welding technique to be used prior to performing welding on austenitic 
material other than P-No. 8 material exposed to thermal neutron fluence 
greater than 1 x 10\17\ n/cm\2\ (E < 0.5 eV). Licensees must obtain NRC 
approval in accordance with paragraph (z) regarding the welding 
technique to be used prior to performing welding on P-No. 8 austenitic 
material exposed to thermal neutron fluence greater than 1 x 10\17\ n/
cm\2\ (E < 0.5 eV) and measured or calculated helium concentration of 
the material greater than 0.1 atomic parts per million.
    (xiii) [Reserved]
    (xiv) Section XI condition: Appendix VIII personnel qualification. 
All personnel qualified for performing ultrasonic examinations in 
accordance with Appendix VIII must receive 8 hours of annual hands-on 
training on specimens that contain cracks. Licensees applying the 2001 
Edition through the latest edition and addenda incorporated by 
reference in paragraph (a)(1)(ii) of this section may use the annual 
practice requirements in VII-4240 of Appendix VII of Section XI in 
place of the 8 hours of annual hands-on training provided that the 
supplemental practice is performed on material or welds that contain 
cracks, or by analyzing prerecorded data from material or welds that 
contain cracks. In either case, training must be completed no earlier 
than 6 months prior to performing ultrasonic examinations at a 
licensee's facility.
* * * * *
    (xviii) Section XI condition: NDE personnel certification--(A) NDE 
personnel certification: First provision. Level I and II nondestructive 
examination personnel must be recertified on a 3-year interval in lieu 
of the 5-year interval specified in IWA-2314(a) and IWA-2314(b) of the 
2001 Edition through the latest edition and addenda incorporated by 
reference in paragraph (a)(1)(ii) of this section.
    (B) NDE personnel certification: Second provision. When applying 
editions and addenda prior to the 2007 Edition of Section XI, paragraph 
IWA-2316 may only be used to qualify personnel that observe leakage 
during system leakage and hydrostatic tests conducted in accordance 
with IWA 5211(a) and (b).
    (C) NDE personnel certification: Third provision. When applying 
editions and addenda prior to the 2005 Addenda of Section XI, 
licensee's qualifying visual examination personnel for VT-3 visual 
examination under paragraph IWA-2317 of Section XI must demonstrate the 
proficiency of the training by administering an initial qualification 
examination and administering subsequent examinations on a 3-year 
interval.
    (D) NDE personnel certification: Fourth provision. The use of 
Appendix VII, Table VII-4110-1 and Appendix VIII, Subarticle VIII-2200 
of the 2011 Addenda through the latest edition incorporated by 
reference in paragraph (a)(1)(ii) of this section is prohibited. When 
using ASME BPV Code, Section XI editions and addenda later than the 
2010 Edition, licensees and applicants must use the prerequisites for 
ultrasonic examination personnel certifications in Appendix VII, Table 
VII-4110-1 and Appendix VIII, Subarticle VIII-2200 in the 2010 Edition.
    (1) As an alternative to Note (c) in Table VII-4110-1 of ASME BPV 
Code, Section XI, 2010 Edition, the 250 hours of Level I experience 
time may be reduced to 175 hours, if the experience time includes a 
minimum of 125 hours of field experience and 50 hours of laboratory 
practice beyond the requirements of for training in accordance with 
Appendix VII Subarticle 4220, provided those practice hours are 
dedicated to the Level I or Level II skill areas as described in ANSI/
ASNT CP-189.
    (2) As an alternative to Note (d) in Table VII-4110-1 of ASME BPV 
Code, Section XI, 2010 Edition, the 800 hours of Level II experience 
time may be reduced to 720 hours, if the experience time includes a 
minimum of 400 hours of field experience and a minimum of 320 hours of 
laboratory practice. The practice must be dedicated to scanning 
specimens containing flaws in materials representative of those in 
actual power plant components. Additionally, for Level II 
Certification, the candidate must pass a Mandatory Appendix VIII, 
Supplement 2 performance demonstration for detection and length sizing.
    (xix) Section XI condition: Substitution of alternative methods. 
The provisions for substituting alternative examination methods, a 
combination of

[[Page 65154]]

methods, or newly developed techniques in the 1997 Addenda of IWA-2240 
must be applied when using the 2001 Edition through the 2004 Edition of 
Section XI of the ASME BPV Code. The provisions in IWA-4520(c), 2001 
Edition through the 2004 Edition, allowing the substitution of 
alternative methods, a combination of methods, or newly developed 
techniques for the methods specified in the Construction Code, are not 
approved for use. The provisions in IWA-4520(b)(2) and IWA-4521 of the 
2008 Addenda through the latest edition and addenda incorporated by 
reference in paragraph (a)(1)(ii) of this section, allowing the 
substitution of ultrasonic examination for radiographic examination 
specified in the Construction Code, are not approved for use.
    (xx) Section XI condition: System leakage tests--(A) System leakage 
tests: First provision. When performing system leakage tests in 
accordance with IWA-5213(a), 2001 Edition through 2002 Addenda, the 
licensee must maintain a 10-minute hold time after test pressure has 
been reached for Class 2 and Class 3 components that are not in use 
during normal operating conditions. No hold time is required for the 
remaining Class 2 and Class 3 components provided that the system has 
been in operation for at least 4 hours for insulated components or 10 
minutes for uninsulated components.
    (B) System leakage tests: Second provision. The nondestructive 
examination method and acceptance criteria of the 1992 Edition or later 
of Section III shall be met when performing system leakage tests (in 
lieu of a hydrostatic test) in accordance with IWA-4520 after repair 
and replacement activities performed by welding or brazing on a 
pressure retaining boundary using the 2003 Addenda through the latest 
edition and addenda of Section XI incorporated by reference in 
paragraph (a)(1)(ii) of this section. The nondestructive examination 
and pressure testing may be performed using procedures and personnel 
meeting the requirements of the licensee's/applicant's current ISI code 
of record.
    (C) System leakage tests: Third provision. The use of the 
provisions for an alternative BWR pressure test at reduced pressure to 
satisfy IWA-4540 requirements as described in IWB-5210(c) of Section 
XI, 2017 Edition and IWA-5213(b)(2) and IWB-5221(d) of Section XI, 2017 
Edition through the latest edition incorporated by reference in 
paragraph (a)(1)(ii) of this section may be used subject to the 
following conditions:
    (1) The use of nuclear heat to conduct the BWR Class 1 system 
leakage test is prohibited (i.e., the reactor must be in a non-critical 
state), except during refueling outages in which the ASME Section XI 
Category B-P pressure test has already been performed, or at the end of 
mid-cycle maintenance outages fourteen (14) days or less in duration.
    (2) In lieu of the test condition holding time of IWA-5213(b)(2), 
after pressurization to test conditions, and before the visual 
examinations commence, the holding time shall be 1 hour for non-
insulated components.
    (xxi) Section XI condition: Table IWB-2500-1 examination 
requirements. (A) [Reserved]
    (B) Table IWB-2500-1 examination. Use of the provisions of IWB-
2500(f) and (g) and Table IWB-2500-1 Notes 6 and 7 of Section XI, 2017 
Edition through the latest edition incorporated by reference in 
paragraph (a)(1)(ii) of this section, for examination of Examination 
Category B-D Item Numbers B3.90 and B3.100 shall be subject to the 
following conditions:
    (1) A plant-specific evaluation demonstrating the criteria of IWB-
2500(f) are met must be maintained in accordance with IWA-1400(l).
    (2) The use of the provisions of IWB-2500(f) and Table IWB-2500-1 
Note 6 for examination of Examination Category B-D Item Numbers B3.90 
is prohibited for plants with renewed licenses in accordance with 10 
CFR part 54.
    (3) The provisions of IWB-2500(g) and Table IWB-2500-1 Notes 6 and 
7 for examination of Examination Category B-D Item Numbers B3.90 and 
B3.100 shall not be used to eliminate the preservice or inservice 
volumetric examination of plants with a Combined Operating License 
pursuant to 10 CFR part 52, or a plant that receives its operating 
license after October 22, 2015.
* * * * *
    (xxv) Section XV Condition: Mitigation of defects by modification. 
Use of the provisions of IWA-4340 must be subject to the following 
conditions:
    (A) Mitigation of defects by modification: First person. The use of 
the provisions for mitigation of defects by modification in IWA-4340 of 
Section XI 2001 Edition through the 2010 Addenda, is prohibited.
    (B) Mitigation of defects by modification: Second provision. The 
provisions for mitigation of defects by modification in IWA-4340 of 
Section XI, 2011 Edition through the latest edition incorporated by 
reference in paragraph (a)(1)(ii) of this section, may be used subject 
to the following conditions:
    (1) The use of the provisions in IWA 4340 to mitigate crack-like 
defects or those associated with flow accelerated corrosion are 
prohibited.
    (2) The design of a modification that mitigates a defect must 
incorporate a loss of material rate either 2 times the actual measured 
corrosion rate, which must be established based on wall thickness 
measurements conducted at least twice, in that pipe location or another 
location with similar corrosion conditions, similar flow 
characteristics, and the same piping configuration (e.g., straight run 
of pipe, elbow, tee) as the encapsulated area, or 4 times the estimated 
maximum corrosion rate for the piping system.
    (3) The licensee must perform a wall thickness examination in the 
vicinity of the modification and relevant pipe base metal at half its 
expected life or, if the modification has an expected life greater than 
19 years, once per interval starting with the interval subsequent to 
the mitigation, and the results must be used to confirm corrosion 
rates, determine the next inspection date, and confirm the design 
inputs.
    (i) For buried pipe locations where the loss of material has 
occurred due to internal corrosion, the wall thickness examinations may 
be conducted at a different location in the same system as long as: 
Wall thickness measurements were conducted at the different location at 
the same time as installation of the modification; the flow rate is the 
same or higher at the different location; the piping configuration is 
the same (e.g., straight run of pipe, elbow, tee); and if pitting 
occurred at the modification location, but not the different location, 
wall loss values must be multiplied by four (instead of two) times the 
actual measured corrosion rate. Where wall loss values are greater than 
that assumed during the design of the modification, the structural 
integrity of the modification must be reanalyzed. Additionally, if the 
extent of degradation is different (i.e., percent wall loss plus or 
minus 25 percent) or the corrosion mechanism (e.g., general, pitting) 
is not the same at the different location as at the modification 
location, the modification must be examined at half its expected life 
or 10 years, whichever is sooner.
    (ii) For buried pipe locations where loss of material has occurred 
due to external corrosion, the modification must be examined at half 
its expected life or 10 years, whichever is sooner. Alternatively, when 
the modification has been recoated prior to return to service, the 
modification may be examined at half its expected life or during the 
subsequent 10-year

[[Page 65155]]

inspection interval after installation, whichever is sooner.
    (xxvi) Section XI condition: Pressure Testing of Class 1, 2, and 3 
Mechanical Joints. Mechanical joints in Class 1, 2, and 3 piping and 
components greater than NPS-1 that are disassembled and reassembled 
during the performance of a Section XI repair/replacement activity 
requiring documentation on a Form NIS-2 must be verified to be leak 
tight. The verification must be performed to the standards of the 
licensee's appendix B to this part quality assurance program.
* * * * *
    (xxix) Section XI condition: Nonmandatory Appendix R. (A) 
Nonmandatory Appendix R, ``Risk-Informed Inspection Requirements for 
Piping Supplement 1--Risk-Informed Selection Process--Method A,'' of 
Section XI, 2005 Addenda through the latest edition and addenda 
incorporated by reference in paragraph (a)(1)(ii) of this section, may 
not be implemented without prior NRC authorization of the proposed 
alternative in accordance with paragraph (z) of this section.
    (B) Nonmandatory Appendix R, ``Risk-Informed Inspection 
Requirements for Piping, Supplement 2--Risk-Informed Selection 
Process--Method B'' of Section XI, 2005 Addenda through the 2015 
Edition, may not be implemented without prior NRC authorization of the 
proposed alternative in accordance with paragraph (z) of this section.
    (C) Nonmandatory Appendix R, ``Risk-Informed Inspection 
Requirements for Piping, Supplement 2--Risk-Informed Selection 
Process--Method B'' of Section XI, 2017 Edition through the latest 
edition and addenda incorporated by reference in paragraph (a)(1)(ii) 
of this section, may be implemented without prior NRC authorization of 
the proposed alternative in accordance with paragraph (z) of this 
section.
* * * * *
    (xxxii) Section XI condition: Summary report submittal. When using 
ASME BPV Code, Section XI, 2010 Edition through the latest edition and 
addenda incorporated by reference in paragraph (a)(1)(ii) of this 
section, Summary Reports and Owner's Activity Reports described in IWA-
6230 must be submitted to the NRC. Preservice inspection reports for 
examinations prior to commercial service must be submitted prior to the 
date of placement of the unit into commercial service. For preservice 
and inservice examinations performed following placement of the unit 
into commercial service, reports must be submitted within 120 calendar 
days of the completion of each refueling outage.
* * * * *
    (xxxvi) Section XI condition: Fracture toughness of irradiated 
materials. When using the 2013 Edition through the latest edition 
incorporated by reference in paragraph (a)(1)(ii) of this section of 
the ASME BPV Code, Section XI, Appendix A paragraph A-4400, the 
licensee shall obtain NRC approval under paragraph (z) of this section 
before using irradiated T0 and the associated 
RTT0 in establishing fracture toughness of irradiated 
materials.
* * * * *
    (xxxix) Section XI condition: Defect Removal. The use of the 
provisions for removal of defects by welding or brazing in IWA-
4421(c)(1) and IWA-4421(c)(2) of Section XI, 2017 Edition through the 
latest edition incorporated by reference in paragraph (a)(1)(ii) of 
this section may be used subject to the following conditions:
    (A) Defect removal requirements: First provision. The provisions of 
subparagraph IWA 4421(c)(1) shall not be used to contain or isolate a 
defective area without removal of the defect.
    (B) Defect removal requirements: Second provision. The provisions 
of subparagraph IWA-4421(c)(2) shall not be used for crack-like 
defects.
* * * * *
    (xliii) Section XI condition: Section XI Condition: Regulatory 
Submittal Requirements. Licensees shall submit for NRC review and 
approval the following analyses:
    (A) The analytical evaluation determining the effects of an out-of-
limit condition on the structural integrity of the Reactor Coolant 
System, as described in IWB-3720(a);
    (B) Determination of T0 and RTT0, as 
described in Nonmandatory Appendix A, A-4200(c); and
    (C) Determination of T0 and RTT0, as 
described in Nonmandatory Appendix G, G-2110(c).
    (3) * * *
    (iii) OM condition: New reactors. In addition to complying with the 
provisions in the ASME OM Code with the conditions specified in 
paragraph (b)(3) of this section, holders of operating licenses for 
nuclear power reactors that received construction permits under this 
part on or after August 17, 2018, and holders of combined licenses 
issued under 10 CFR part 52, whose initial fuel loading occurs on or 
after August 17, 2018, must also comply with the following conditions, 
as applicable:
    (A) Power-operated valves. Licensees must periodically verify the 
capability of power-operated valves to perform their design-basis 
safety functions.
    (B) Check valves. Licensees must perform bi-directional testing of 
check valves within the IST program where practicable.
    (C) Flow-induced vibration. Licensees must monitor flow-induced 
vibration from hydrodynamic loads and acoustic resonance during 
preservice testing or inservice testing to identify potential adverse 
flow effects on components within the scope of the IST program.
    (D) High risk non-safety systems. Licensees must assess the 
operational readiness of pumps, valves, and dynamic restraints within 
the scope of the Regulatory Treatment of Non-Safety Systems for 
applicable reactor designs.
* * * * *
    (viii) OM condition: Subsection ISTE. Licensees may not implement 
the risk-informed approach for inservice testing (IST) of pumps and 
valves specified in Subsection ISTE, ``Risk-Informed Inservice Testing 
of Components in Light-Water Reactor Nuclear Power Plants,'' in the 
ASME OM Code, 2009 Edition through the 2017 Edition, without first 
obtaining NRC authorization to use Subsection ISTE as an alternative to 
the applicable IST requirements in the ASME OM Code, pursuant to 
paragraph (z) of this section.
    (ix) OM condition: Subsection ISTF. Licensees applying Subsection 
ISTF, 2012 Edition must satisfy the requirements of Mandatory Appendix 
V, ``Pump Periodic Verification Test Program,'' of the ASME OM Code in 
that edition.
    (x) [Reserved]
    (xi) OM condition: Valve Position Indication. When implementing 
paragraph ISTC-3700, ``Position Verification Testing,'' in the ASME OM 
Code, 2012 Edition through the latest edition of the ASME OM Code 
incorporated by reference in paragraph (a)(1)(iv) of this section, 
licensees must verify that valve operation is accurately indicated by 
supplementing valve position indicating lights with other indications, 
such as flow meters or other suitable instrumentation to provide 
assurance of proper obturator position for valves with remote position 
indication within the scope of Subsection ISTC including its mandatory 
appendices and their verification methods and frequencies. For valves 
not susceptible to stem-disk separation, licensees may implement ASME 
OM Code Case OMN-28, ``Alternative Valve Position Verification Approach 
to Satisfy ISTC-3700 for Valves Not Susceptible to Stem-Disk 
Separation,'' which is incorporated by

[[Page 65156]]

reference in paragraph (a)(1)(iii)(H) of this section. Where plant 
conditions make it impractical to perform the initial ISTC-3700 test as 
supplemented by paragraph (b)(3)(xi) of this section by the date 2 
years following the previously performed ISTC-3700 test, a licensee may 
justify an extension of this initial supplemental valve position 
verification provided the ISTC-3700 test as supplemented by paragraph 
(b)(3)(xi) of this section is performed at the next available 
opportunity and no later than the next plant shutdown. This one-time 
extension of the ISTC-3700 test schedule as supplemented by paragraph 
(b)(3)(xi) of this section is acceptable provided the licensee has 
available for NRC review documented justification based on information 
obtained over the previous 5 years of the structural integrity of the 
stem-disk connection for the applicable valves. The licensee's 
justification could be based on, for example, verification of the valve 
stem-disk connection through an appropriate weak link analysis, 
appropriate disk motion confirmed during diagnostic testing, or 
allowance and cessation of flow through the valves. The licensee's 
justification must provide reasonable assurance that the remote 
indicating lights accurately reveal the position of the valve obturator 
until the next ISTC-3700 test as supplemented by paragraph (b)(3)(xi) 
of this section is performed.
* * * * *
    (f) * * *
    (4) Inservice testing standards requirement for operating plants. 
Throughout the service life of a boiling or pressurized water-cooled 
nuclear power facility, pumps and valves that are within the scope of 
the ASME OM Code must meet the inservice test requirements (except 
design and access provisions) set forth in the ASME OM Code and addenda 
that become effective subsequent to editions and addenda specified in 
paragraphs (f)(2) and (3) of this section and that are incorporated by 
reference in paragraph (a)(1)(iv) of this section, to the extent 
practical within the limitations of design, geometry, and materials of 
construction of the components. The inservice test requirements for 
pumps and valves that are within the scope of the ASME OM Code but are 
not classified as ASME BPV Code Class 1, Class 2, or Class 3 may be 
satisfied as an augmented IST program. This use of an augmented IST 
program is acceptable without prior NRC approval provided the basis for 
deviations from the ASME OM Code, as incorporated by reference in this 
section, demonstrates an acceptable level of quality and safety, or 
that implementing the Code provisions would result in hardship or 
unusual difficulty without a compensating increase in the level of 
quality and safety, where documented and available for NRC review. When 
using the 2006 Addenda or later of the ASME BPV Code, Section XI, the 
inservice examination, testing, and service life monitoring 
requirements for dynamic restraints (snubbers) must meet the 
requirements set forth in the applicable ASME OM Code as specified in 
paragraph (b)(3)(v)(B) of this section. When using the 2005 Addenda or 
earlier edition or addenda of the ASME BPV Code, Section XI, the 
inservice examination, testing, and service life monitoring 
requirements for dynamic restraints (snubbers) must meet the 
requirements set forth in either the applicable ASME OM Code or ASME 
BPV Code, Section XI as specified in paragraph (b)(3)(v) of this 
section.
    (i) Applicable IST Code: Initial 120-month interval. Inservice 
tests to verify operational readiness of pumps and valves, whose 
function is required for safety, conducted during the initial 120-month 
interval must comply with the requirements in the latest edition and 
addenda of the ASME OM Code incorporated by reference in paragraph 
(a)(1)(iv) of this section on the date 18 months before the date of 
issuance of the operating license under this part, or 18 months before 
the date scheduled for initial loading of fuel under a combined license 
under part 52 of this chapter (or the optional ASME OM Code Cases 
listed in NRC Regulatory Guide 1.192, as incorporated by reference in 
paragraph (a)(3)(iii) of this section, subject to the conditions listed 
in paragraph (b) of this section).
    (ii) Applicable IST Code: Successive 120-month intervals. Inservice 
tests to verify operational readiness of pumps and valves, whose 
function is required for safety, conducted during successive 120-month 
intervals must comply with the requirements of the latest edition and 
addenda of the ASME OM Code incorporated by reference in paragraph 
(a)(1)(iv) of this section 18 months before the start of the 120-month 
interval (or the optional ASME Code Cases listed in NRC Regulatory 
Guide 1.147 or NRC Regulatory Guide 1.192 as incorporated by reference 
in paragraphs (a)(3)(ii) and (iii) of this section, respectively), 
subject to the conditions listed in paragraph (b) of this section.
    (iii) [Reserved]
    (iv) Applicable IST Code: Use of later Code editions and addenda. 
Inservice tests of pumps and valves may meet the requirements set forth 
in subsequent editions and addenda that are incorporated by reference 
in paragraph (a)(1)(iv) of this section, subject to the conditions 
listed in paragraph (b) of this section, and subject to NRC approval. 
Portions of editions or addenda may be used, provided that all related 
requirements of the respective editions or addenda are met.
* * * * *
    (7) Inservice testing reporting requirements. Inservice Testing 
Program Test and Examination Plans (IST Plans) for pumps, valves, and 
dynamic restraints (snubbers) prepared to meet the requirements of the 
ASME OM Code must be submitted to the NRC as specified in Sec.  50.4. 
IST Plans must be submitted within 90 days of their implementation for 
the applicable 120-month IST Program interval. Electronic submission is 
preferred.
    (g) * * *
    (4) Inservice inspection standards requirement for operating 
plants. Throughout the service life of a boiling or pressurized water-
cooled nuclear power facility, components (including supports) that are 
classified as ASME Code Class 1, Class 2, and Class 3 must meet the 
requirements, except design and access provisions and preservice 
examination requirements, set forth in Section XI of editions and 
addenda of the ASME BPV Code that become effective subsequent to 
editions specified in paragraphs (g)(2) and (3) of this section and 
that are incorporated by reference in paragraph (a)(1)(ii) or (iv) of 
this section for snubber examination and testing of this section, to 
the extent practical within the limitations of design, geometry, and 
materials of construction of the components. Components that are 
classified as Class MC pressure retaining components and their integral 
attachments, and components that are classified as Class CC pressure 
retaining components and their integral attachments, must meet the 
requirements, except design and access provisions and preservice 
examination requirements, set forth in Section XI of the ASME BPV Code 
and addenda that are incorporated by reference in paragraph (a)(1)(ii) 
of this section subject to the condition listed in paragraph (b)(2)(vi) 
of this section and the conditions listed in paragraphs (b)(2)(viii) 
and (ix) of this section, to the extent practical within the limitation 
of design, geometry, and materials of construction of the components. 
When using the 2006 Addenda or later of the ASME BPV Code, Section XI, 
the inservice examination, testing, and service life monitoring 
requirements for dynamic restraints (snubbers) must meet the 
requirements set forth in the

[[Page 65157]]

applicable ASME OM Code as specified in paragraph (b)(3)(v)(B) of this 
section. When using the 2005 Addenda or earlier edition or addenda of 
the ASME BPV Code, Section XI, the inservice examination, testing, and 
service life monitoring requirements for dynamic restraints (snubbers) 
must meet the requirements set forth in either the applicable ASME OM 
Code or ASME BPV Code, Section XI as specified in paragraph (b)(3)(v) 
of this section.
* * * * *

    Dated October 20, 2022.

    For the Nuclear Regulatory Commission.
Andrea D. Veil,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 2022-23226 Filed 10-26-22; 8:45 am]
BILLING CODE 7590-01-P