[Federal Register Volume 86, Number 57 (Friday, March 26, 2021)]
[Proposed Rules]
[Pages 16087-16114]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2021-06085]


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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: Proposed rule.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is proposing to 
amend its regulations to incorporate by reference the 2019 Edition of 
the American Society of Mechanical Engineers Boiler and Pressure Vessel 
Code 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 
proposing to incorporate by reference 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: Submit comments by May 25, 2021. Comments received after this 
date will be considered if it is practical to do so, but the NRC is 
able to ensure consideration only for comments received on or before 
this date.

ADDRESSES: You may submit comments by any of the following methods 
(unless this document describes a different method for submitting 
comments on a specific subject):
     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.
     Email comments to: [email protected]. If you do 
not receive an automatic email reply confirming receipt, then contact 
us at 301-415-1677.

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    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Victoria V. Huckabay, Office of 
Nuclear Material Safety and Safeguards, telephone: 301-415-5183, email: 
[email protected]; or Keith Hoffman, Office of Nuclear Reactor 
Regulation, telephone: 301-415-1294, 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 proposing to amend 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 proposing to incorporate by reference 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.
    The ASME periodically revises and updates its codes for nuclear 
power plants by issuing new editions; this proposed rule is in 
accordance with the NRC's practice to incorporate those new editions 
into the NRC's regulations. This proposed 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. The ASME is a voluntary 
consensus standards organization, and the 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 VIII of this document, 
``Voluntary Consensus Standards.''

B. Major Provisions

    Major provisions of this proposed rule include the incorporation by 
reference with conditions of the following ASME Codes 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
 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 draft regulatory analysis to determine the 
expected costs and benefits of this proposed rule. The regulatory 
analysis identifies costs and benefits in both a quantitative fashion 
as well as in a qualitative fashion.
    The analysis concludes that this proposed rule would result in a 
net quantitative averted cost to the industry and the NRC. This 
proposed rule, relative to the regulatory baseline, would result in a 
net averted cost for industry of $6.26 million based on a 7 percent net 
present value (NPV) and $6.99 million based on a 3 percent NPV. The 
proposed 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 $0.49 
million based on a 7 percent NPV to $0.57 million based on a 3 percent 
NPV. Qualitative factors that were considered include regulatory 
stability and predictability, regulatory efficiency, and consistency 
with the NTTAA. The regulatory analysis shows that the rulemaking is 
justified because the total quantified benefits of the proposed 
regulatory action exceed the costs of the proposed 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 proposed 
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 
the 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 draft regulatory analysis 
(Accession No. ML20178A448 in the NRC's Agencywide Documents Access and 
Management System (ADAMS)).

Table of Contents

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

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2018-0290 when contacting the NRC 
about the availability of information for this proposed rule. You may 
obtain information related to this proposed rule by any of the 
following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2018-0290.
     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 ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public

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Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or 
by email to [email protected]. For the convenience of the reader, 
instructions about obtaining materials referenced in this document are 
provided in the ``Availability of Documents'' section.
     Attention: The PDR, where you may examine and order copies 
of public documents, is currently closed. You may submit your request 
to the PDR via email at [email protected] or call 1-800-397-4209 
between 8:00 a.m. and 4:00 p.m. (EST), Monday through Friday, except 
Federal holidays.
     Attention: The Technical Library, where you may examine 
industry codes and standards, is currently closed. You may submit your 
request to the Technical Library via email at [email protected] 
between 8:00 a.m. and 4:00 p.m. (EST), Monday through Friday, except 
Federal holidays.

B. Submitting Comments

    Please include Docket ID NRC-2018-0290 in your comment submission.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS.

II. Background

    The American Society of Mechanical Engineers 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, the 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, the 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 (no 
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 and addenda 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. The 
revisions to the editions and addenda 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).
    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 the 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 conditions are included in Sec.  50.55a, 
typically in paragraph (b) of that section. In a Staff Requirements 
Memorandum dated September 10, 1999, (ADAMS Accession No. ML003755050) 
the Commission indicated that NRC rulemakings adopting (incorporating 
by reference) a voluntary consensus standard must identify and justify 
each part of the standard that is not adopted. For this proposed 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 code cases that are the 
subject of this proposed 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 VIII of this 
document, ``Voluntary Consensus Standards.''

III. Discussion

    The NRC regulations incorporate by reference ASME Codes for nuclear 
power plants. This proposed rule is the latest in a series of 
rulemakings to amend the NRC's regulations to

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incorporate by reference revised and updated ASME Codes for nuclear 
power plants. This proposed 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 proposed 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. 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 
proposed 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 reviewed changes to the Codes in the editions identified in 
this proposed rule. The NRC concluded, in accordance with the process 
for review of changes to the Codes, that these editions of the Codes, 
are technically adequate, consistent with current NRC regulations, and 
approved for use with the specified conditions upon the conclusion of 
the rulemaking process.
    The NRC is proposing to amend 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 its use.
     The 2020 Edition to Division 1 of the ASME OM Code, with 
conditions on its 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 Editions of ASME NQA-1, with conditions on its 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 proposed rule would revise 
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 1976 
Winter Addenda; and 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). This proposed rule would revise 
Sec.  50.55a(a)(1)(ii) to incorporate by reference the 2019 Edition 
(Division 1) of the ASME BPV Code, Section XI. It would also clarify 
the wording and add, remove, or revise some of the conditions as 
explained in this proposed rule.
    The current regulations in Sec.  50.55a(a)(1)(iv) incorporate by 
reference ASME OM Code, 1995 Edition through the 2017 Edition, subject 
to the conditions currently identified in Sec.  50.55a(b)(3)(i) through 
(xi). This proposed rule would revise 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 III.B of this document, this proposed 
rule would revise 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.
    The current regulations in Sec.  50.55a(a)(1)(v) incorporate by 
reference ASME NQA-1, Quality Assurance Requirements for Nuclear 
Facility Applications, subject to conditions identified in Sec.  
50.55a(b)(1)(iv) and (b)(2)(x). This proposed rule would revise Sec.  
50.55a(a)(1)(v)(B) 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. Each of 
the proposed NRC conditions and the reasons for each are discussed in 
the following sections of this document. The discussions are organized 
under the applicable ASME Code and Section.
    The NRC prepared an unofficial redline strikeout version of the 
proposed changes to regulatory text which is intended to help the 
reader identify the proposed changes. The unofficial redline strikeout 
version of the proposed rule is publicly available and is listed in the 
``Availability of Documents'' 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 proposes to revise 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 proposed rule would 
revise 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 proposes to revise the definition of Section III in Sec.  
50.55a(b)(1) to include the latest edition of the

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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 proposes to revise 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 proposing to revise this condition to apply to the latest 
edition incorporated by reference.
Section 50.55a(b)(1)(iii) Section III Condition: Seismic Design of 
Piping
    The NRC proposes to revise Sec.  50.55a(b)(1)(iii) 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 proposing to revise 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 proposing to revise 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. 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 and later Editions of Section III, which this rule is also 
incorporating by reference.
Section 50.55a(b)(1)(vii) Section III Condition: Capacity Certification 
and Demonstration of Function of Incompressible-Fluid Pressure-Relief 
Valves
    The NRC proposes to revise 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 proposing to revise 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 proposes to revise 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 proposing to revise 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 proposing to add 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 proposing to add 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 provides 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.

B. ASME BPV Code, Section XI

Section 50.55a(a)(1)(ii) ASME Boiler and Pressure Vessel Code, Section 
XI
    The NRC proposes to remove and reserve Sec.  50.55a(a)(1)(ii)(A), 
remove Sec.  50.55a(a)(1)(ii)(B)(5) through (7), and remove and reserve 
Sec.  50.55a(a)(1)(ii)(C)(1) through (32) and (37) through (40) because 
they 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 
proposes to amend regulations in Sec.  50.55a(b)(2)(viii), (ix), (xii), 
(xiv), and (xv), (b)(2)(xviii)(A), and (b)(2)(xix), and (b)(2)(xx)(A) 
to remove references to these older editions and addenda.
    The NRC proposes to amend 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 proposed amendment would revise 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.

[[Page 16092]]

Section 50.55a(b)(2) Conditions on ASME BPV Code Section XI
    The NRC proposes to revise 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 proposes to amend 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 proposes to delete 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 proposes to amend the regulations in Sec.  
50.55a(b)(2)(ix) to remove references to Section XI editions and 
addenda prior to the 2001 Edition. With the removal of these earlier 
editions the NRC also proposes to delete 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 proposes to revise 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 proposed rule would also incorporate by 
reference.
    The NRC is proposing to revise 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, and the 
2012 and 2015 Edition of NQA-1 when using the 2019 and later Editions 
of Section XI, which this rule is also incorporating by reference.
    The NRC also proposes to revise 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) NDE Personnel Certification: Fourth 
Provision
    The NRC proposes to amend 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 (ADAMS Accession No. ML20079E343), 
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 proposes to amend 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 proposes to amend 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) Table IWB-2500-1 Examination
    The NRC proposes to amend 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) Mitigation of Defects by Modification: 
Second Provision
    The NRC proposes to amend 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 proposes to amend 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 proposes 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 (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 asset 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 proposes to delete 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 proposes to delete the refueling 
outage interval examinations and only require the examination to occur 
at half the modification's expected life or, if the modification has an 
expected life greater

[[Page 16093]]

than 19 years, once per interval. The NRC has concluded that the 2 
times multiplier for known loss of material rates or 4 times multiplier 
for estimated loss of material rates provides sufficient conservatism 
to allow a followup 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 proposed in paragraph (b)(2)(xxv)(B)(3)(i) are 
editorial. The NRC proposes to delete 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 as well as any other level of wall 
loss.
    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 proposes to revise 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 proposes to amend Sec.  50.55a(b)(2)(xxvi) to to remove 
references to Section XI pressure test and VT-2 examination. The NRC 
proposes to relax 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 (ADAMS Accession No. 
ML20163A609). 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 (ADAMS Accession No. ML031430208) 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 (ADAMS Accession No. ML20189A286).
    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) the twice daily walkdowns in 
all 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 
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 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.
    Therefore, the NRC is proposing to amend Sec.  50.55a(b)(2)(xxvi) 
to require a licensee defined leak test to demonstrate the leak 
tightness of Class 1, 2, and 3 mechanical joints. The proposed change 
would require that the owner establish the type of leak test, test 
medium, test pressure, and acceptance criteria that would demonstrate 
the joint's leak tightness. Because the condition would no longer 
require an ASME Code pressure test, the ASME Code NDE examiner 
qualification requirements would no longer apply. Therefore the NRC is 
also removing the requirement for the NDE examiners to meet the 
requirements of the licensee's current ISI code of record. The licensee 
must also specifiy the qualifications of the person performing the leak 
test.

[[Page 16094]]

    Requiring the licensee defined leak test ensures the tests are done 
in accordance with the licensee's appendix B program as described by 
commenters in the past. The licensee defined test 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.
    This licensee defined leak test must be performed on 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 or replacement activity requiring documentation on a 
Form NIS-2. The licensee defined leak test should be of sufficient 
rigor to ensure leak tightness under operational conditions of 
mechanical joints affected by repair/replacement activities. The 
licensee defined leak test will achieve what the imposition of the 
original condition in the 2004 rulemaking sought to achieve, which was 
leak tightness of mechanical joints impacted by repair/replacement 
activities. 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 proposes to amend 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 
Decisionmaking for Inservice Inspection of Piping,'' (ADAMS Accession 
No. ML032510128), RG 1.200, ``An Approach for Determining the Technical 
Adequacy of Probabilistic Risk Assessment Results for Risk-Informed 
Activities,'' (ADAMS Accession No. ML090410014), and NRC Standard 
Review Plan Chapter 3.9.8, ``Review of Risk-Informed Inservice 
Inspection of Piping,'' (ADAMS Accession No. ML032510135). 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 proposes to amend 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 proposes 
to relax the requirement for all licensees.
Section 50.55a(b)(2)(xxxvi) Section XI Condition: Fracture Toughness of 
Irradiated Materials
    The NRC proposes to amend 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 proposes to amend 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 proposes to amend the regulations in Sec.  50.55a(b)(2)(xl) 
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 proposes to add prohibitions 
on the use of ASME BPV Code, Section XI, IWC-3510.5(b)(4), IWC-
3510.5(b)(5), and Tables A-4200-1 and G-2110-1. This proposed condition 
does not change the current requirements. Rather, it maintains existing 
testing requirements that licensees/applicants may use to show that the 
ASME Section XI toughness curve is applicable to high-strength ferritic 
steels.
    ASME has revised certain provisions to extend methods for 
characterizing fracture tougness of high-strength ferritic steels and 
associated flaw acceptance standards that the NRC prohibited in a 
previous rulemaking (85 FR 26540: May 4, 2020) to IWC-3510.5 and Tables 
A-4200-1 and G-2110-1 (for SA-533 Type B Class 2). The NRC proposes to 
extend the application of this condition to these revised provisions 
for the same reasons as outlined in the previous rulemaking. In 
addition to amending the text of Sec.  50.55a(b)(2)(xl), the NRC 
proposes to change the heading of the paragraph to read: ``Section 
50.55a(b)(2)(xl) Section XI Condition: Prohibitions and Restrictions 
Related to Fracture Toughness of Certain High-Strength Ferritic 
Steels.''
Section 50.55a(b)(2)(xliii) Section XI Condition: Regulatory Submittal 
Requirements
    The NRC proposes to add 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),

[[Page 16095]]

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 proposed condition would simply retain 
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)(iv), ASME Operation and Maintenance Code
    The NRC proposes to amend the regulations in Sec.  
50.55a(a)(1)(iv)(B) to incorporate by reference 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 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 proposes to remove the incorporation by reference of 
the 2011 Addenda of the ASME OM Code from Sec.  50.55a(a)(1)(iv)(B)(2), 
which would allow 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 proposes to remove 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 useable for applicants or 
updating licensees.
Section 50.55a(b)(3) Conditions on ASME OM Code
    The NRC proposes to simplify Sec.  50.55a(b)(3) to be consistent 
with the proposal to remove specific editions or addenda from Sec.  
50.55a(a)(1)(iv) as previously mentioned and further discussed in the 
following.
Section 50.55a(b)(3)(iii) OM Condition: New Reactors
    The NRC proposes to simplify 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 proposes to replace 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 proposes to amend 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 would become 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 proposes to remove 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 would become unnecessary because the NRC 
also proposes to amend 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 proposes to reserve 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 has revised the subsection to be 
acceptable in the 2020 Edition of the ASME OM Code. Therefore, the NRC 
proposes to not to extend 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

[[Page 16096]]

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 proposes to amend 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 proposes to amend Sec.  
50.55a(a)(1)(iv)(B)(2) to remove the incorporation by reference of the 
2011 Addenda and amend 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 would become 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 proposes to amend 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 proposes to amend Sec.  50.55a(b)(3)(xi) to 
allow schedule flexibility for valves not susceptible to stem-disk 
separation by specifying that position verification testing required by 
paragraph ISTC-3700 may be performed on a 10-year interval (rather than 
the 2-year interval specified in ISTC-3700) where justification is 
documented and available for NRC review. Such documentation would be 
required to demonstrate that the stem-disk connection is not 
susceptible to separation based on the internal design and evaluation 
of the stem-disk connection using plant-specific and industry operating 
experience, and vendor recommendations. This allows design information 
and performance data to be applied in demonstrating that a valve is not 
susceptible to stem-disk separation. For example, some valves with a 
threaded stem-disk connection are susceptible to stem-disk separation 
based on industry operating experience. In the event of unsuccessful 
position verification testing, the valve would no longer be considered 
to be not susceptible to stem-disk separation, and would return to the 
ISTC-3700 testing interval together with the results of the extent of 
condition review under the corrective action program. The ASME OM Code 
committees are considering increased schedule flexibility for position 
verification testing as part of a proposed Code Case. The NRC is 
proposing to allow up to 10 years in this condition for valve position 
verification testing in line with other 10-year/120-month testing 
intervals in the ASME OM Code and Sec.  50.55a. However, the NRC is 
aware that the ASME committees are considering allowing up to 12 years 
as the maximum interval for valve position verification testing in a 
Code Case. If that Code Case is issued before the final rule is 
published, the NRC may adopt the 12-year maximum interval in that Code 
Case.
Section 50.55a(f)(4): Inservice Testing Standards Requirement for 
Operating Plants
    The NRC proposes to modify 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 proposes to include 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.
Section 50.55a(f)(7), Inservice Testing Reporting Requirements
    The NRC proposes to add Sec.  50.55a(f)(7) to require nuclear power 
plant applicants and licensees to submit their IST Plans and interim 
IST Plan updates related to pumps and valves, and IST Plans and interim 
Plan updates 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, the 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 
proposed condition retains a requirement from previous editions of the 
ASME OM Code.
Section 50.55a(g)(4), Inservice Inspection Standards Requirement for 
Operating Plants
    The NRC proposes to modify 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 examination, testing, and service life 
monitoring requirements for dynamic restraints (snubbers) with either 
the ASME OM Code or ASME BPV Code, Section XI.
    As discussed in public meetings on August 21, 2020, September 24, 
2020, and January 19, 2021, the NRC also considered revising Sec.  
50.55a(g)(4) to clarify requirements for operational leakage. (Meeting 
summaries for the first two are available at ADAMS Accession Nos. 
ML20265A083 and ML20338A553; the summary for the January meeting is not 
yet available). The intent of the revision being considered was to 
clarify that ASME Code methodologies, or approved alternatives, must be 
used to evaluate structural integrity when operational leakage occurs 
regardless of the plant operating state during which the through-wall 
leakage is discovered. This has been the NRC's longstanding

[[Page 16097]]

position on this issue. Because there is no change in agency position 
or interpretation of this requirement, the NRC determined that the 
issuance of a generic communication, rather than a rule change, should 
be sufficient to communicate the agency's requirements. Therefore, the 
NRC decided not to propose revisions to clarify the existing 
operational leakage requirements in the proposed rule. The NRC will 
follow its established procedures for development of any generic 
communications, including appropriate opportunities for stakeholder 
input.

IV. Section-by-Section Analysis

Paragraph (a)(1)(i)(E)

    This proposed rule would revise paragraphs (a)(1)(i)(E)(18) and 
(19) and add new paragraph (a)(1)(i)(E)(20) to include the 2019 Edition 
of the ASME BPV Code.

Paragraph (a)(1)(ii)(A)

    This proposed rule would remove and reserve paragraph 
(a)(1)(ii)(A).

Paragraph (a)(1)(ii)(B)

    This proposed rule would revise paragraph (a)(1)(ii)(B) and remove 
paragraphs (a)(1)(ii)(B)(5) through (7).

Paragraph (a)(1)(ii)(C)

    This proposed rule would remove and reserve paragraphs 
(a)(1)(ii)(C)(1) through (32) and paragraphs (a)(1)(ii)(C)(37) through 
(40), revise paragraphs (a)(1)(ii)(C)(54) and (55), and add new 
paragraph (a)(1)(ii)(C)(56) to include the 2019 Edition of the ASME BPV 
Code.

Paragraph (a)(1)(iv)

    This proposed rule would revise paragraph (a)(1)(iv)(B)(1) and 
remove and reserve paragraph (a)(1)(iv)(B)(2) and it would revise 
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 proposed rule would revise paragraphs (a)(1)(v)(B)(2) and (3) 
and add 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 proposed rule would revise paragraphs (b)(1) introductory 
text, Table 1 in paragraphs (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 would also revise 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 would also be added.

Paragraph (b)(2)

    This proposed rule would revise 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 proposed rule would remove and reserve paragraphs 
(b)(2)(viii)(A) through (D).

Paragraph (b)(2)(ix)

    This proposed rule would revise 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 proposed rule 
would also revise paragraph (b)(2)(ix)(B) to remove references to 
Section XI editions and addenda prior to the 2001 Edition. This 
proposed rule would also remove and reserve paragraphs (b)(2)(ix)(C) 
through (E).

Paragraph (b)(2)(x)

    This proposed rule would revise 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. The proposed rule would also remove the 
reference to IWA-1400.

Paragraph (b)(2)(xii)

    This proposed rule would revise 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 proposed rule would revise paragraph (b)(2)(xiv) to replace 
the reference to the 1999 Addenda with the reference to the 2001 
Edition.

Paragraph (b)(2)(xv)

    This proposed rule would revise paragraph (b)(2)(xv) to remove the 
phrase ``the 1995 Edition through.''

Paragraph (b)(2)(xviii)

    This proposed rule would revise 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 proposed rule 
would also revise 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 proposed rule would revise paragraph (b)(2)(xix) to remove 
references to Section XI editions and addenda prior to the 2001 
Edition.

Paragraph (b)(2)(xx)

    This proposed rule would revise paragraph (b)(2)(xx)(A) to replace 
the reference to the 1997 Addenda with the reference to the 2001 
Edition. This proposed rule would also revise paragraph (b)(2)(xx)(C) 
to retain the applicability to users of the latest edition incorporated 
by reference in paragraph (a)(1)(ii) and remove reference to IWB-
5210(c).

Paragraph (b)(2)(xxi)

    This proposed rule would revise 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 proposed rule would revise paragraph (b)(2)(xxv) introductory 
text and revise paragraph (b)(2)(xxv)(B) to extend the applicability to 
users of the latest edition incorporated by reference in paragraph 
(a)(1)(ii). This proposed rule would also revise 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 proposed rule would also revise 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 proposed rule would 
also revise paragraph (b)(2)(xxv)(B)(3)(i) to make editorial changes 
and revise 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.

[[Page 16098]]

Paragraph (b)(2)(xxvi)

    This proposed rule would revise paragraph (b)(2)(xxvi) to remove 
the requirements for pressure testing in accordance with IWA-5211(a) 
and NDE examination. This proposed rule would also revise paragraph 
(b)(2)(xxvi) to add a requirement for the owner to establish the type 
of leak test, test medium, test pressure, and acceptance criteria that 
would demonstrate the joint's leak tightness.

Paragraph (b)(2)(xxix)

    This proposed rule would revise 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 proposed rule would revise 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 proposed rule would revise 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 proposed rule would revise 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 proposed rule would revise paragraph (b)(2)(xl) to extend 
applicability to users of the latest edition incorporated by reference 
in paragraph (a)(1)(ii) and to extend the prohibitions and restrictions 
on the use of certain characteristics of high-strength steels in IWB-
3510.4(b) to IWC-3510.5(b), Table A-4200-1, and Table G-2110-1 in the 
2020 Edition of ASME Code, Section XI.

Paragraph (b)(2)(xliii)

    This proposed rule would add new paragraph (b)(2)(xliii) to require 
submission of certain analyses to the NRC for review.

Paragraph (b)(3)

    This proposed rule would revise 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 proposed rule would revise paragraph (b)(3)(iii) for clarity 
of the date of application of this condition.

Paragraph (b)(3)(iv)

    This proposed rule would revise 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 revise the paragraph for clarity.

Paragraph (b)(3)(vii)

    This proposed rule would remove and reserve paragraph (b)(3)(vii).

Paragraph (b)(3)(viii)

    This proposed rule would revise 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 proposed rule would revise paragraph (b)(3)(ix) to remove the 
reference to Subsection ISTF of the 2011 Addenda and 2015 Edition.

Paragraph (b)(3)(xi)

    This proposed rule would revise paragraph (b)(3)(xi) to remove 
reference to ASME OM Code addenda, revise the paragraph for clarity, 
and allow increased flexibility in the schedule for position 
verification testing of valves not susceptible to stem-disk separation.

Paragraph (f)(4)

    This proposed rule would revise paragraph (f)(4) to clarify the 
relationship between paragraphs (f)(4) and (g)(4) regarding the IST and 
ISI programs for dynamic restraints.

Paragraph (f)(7)

    This proposed rule would add new paragraph (f)(7) to include the 
requirements for inservice testing reporting.

Paragraph (g)(4)

    This proposed rule would revise paragraph (g)(4) to clarify the 
relationship between paragraphs (f)(4) and (g)(4) regarding the IST and 
ISI programs for dynamic restraints.

V. Generic Aging Lessons Learned Report

Background

    In December 2010, the NRC issued ``Generic Aging Lessons Learned 
(GALL) Report,'' NUREG-1801, Revision 2 (ADAMS Accession No. 
ML103490041), 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 
(ADAMS Accession No. ML103490036), 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 aging management programs 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 (ADAMS Accession No. 
ML11116A062), 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

[[Page 16099]]

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 2017 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 (ADAMS 
Accession Nos. ML17187A031 and ML17187A204), 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 (ADAMS Accession No. ML17188A158). 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 proposed 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 proposed 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 the 2019 Edition of the ASME BPV Code, as subject 
to the conditions in this proposed 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 kilopound per square inch (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.

VI. 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). The NRC requests comment on this document with respect to the 
clarity and effectiveness of the language used.

VII. 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 proposed rule, the NRC is continuing its existing practice 
of establishing requirements for the design,

[[Page 16100]]

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.
    As discussed in Section III of this document, this proposed rule 
would condition 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. In addition, the NRC proposes not to adopt (exclude) certain 
provisions of the ASME Codes as discussed in this document, and in the 
regulatory and backfit analysis for this proposed rule. The NRC finds 
that this proposed 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, addenda, 
and code cases, 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 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 as 
proposed in this proposed 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 Cases that are the subject of this proposed 
rule are acceptable for use (in some cases with conditions). For these 
reasons, the NRC concludes that this proposed rule's treatment of ASME 
Code editions and addenda, and code cases and 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 proposed rule satisfies the requirements of the 
NTTAA and OMB Circular A-119.

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

    The NRC proposes to incorporate by reference two recent editions to 
the ASME Codes for nuclear power plants. The NRC is also proposing to 
incorporate by reference 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 include in a proposed rule a discussion of the 
ways that the materials the agency proposes to incorporate by reference 
are reasonably available to interested parties or how it worked to make 
those materials reasonably available to interested parties. The 
discussion in this section complies with the requirement for proposed 
rules as set forth in Sec.  51.5(a)(1).
    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 Sec.  
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 
Sec.  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.

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

[[Page 16101]]

     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 proposes to incorporate by reference by 
rulemaking in order to participate in the rulemaking process.
    The Technical Library, where you may examine industry codes and 
standards, is currently closed. You may submit your request to the 
Technical Library via email at [email protected] between 8:00 
a.m. and 4:00 p.m. (EST), Monday through Friday, except Federal 
holidays.
    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 Dr., 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 to be 
incorporated by reference in order to participate in the 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 proposed rule, 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 (ADAMS Accession No. ML20127H677). On April 
14, 2020, the ASME agreed to make the materials available online in a 
read-only electronic access format during the public comment period 
(ADAMS Accession No. ML20127H684). Therefore, 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 
proposes to incorporate by reference in this rulemaking are available 
in read-only format at the ASME website http://go.asme.org/NRC-ASME.
    The materials are available to all interested parties in multiple 
ways and in a manner consistent with their interest in this proposed 
rule. Therefore, the NRC concludes that the materials the NRC proposes 
to incorporate by reference in this proposed rule are reasonably 
available to all interested parties.

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

    This proposed 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 
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 proposed 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 proposed 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.

X. Paperwork Reduction Act Statement

    This proposed rule contains new or amended collections of 
information subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 
3501 et seq). This proposed rule has been submitted to the Office of 
Management and Budget for review and approval of the information 
collections.
    Type of submission, new or revision: Revision.
    The title of the information collection: Domestic Licensing of 
Production and Utilization Facilities: Incorporation by Reference of 
American Society of Mechanical Engineers Codes and Code Cases.
    The form number if applicable: Not applicable.
    How often the collection is required or requested: On occasion.
    Who will be required or asked to respond: Power reactor licensees 
and applicants for power reactors under construction.
    An estimate of the number of annual responses: -22 (reduction).
    The estimated number of annual respondents: -22 (reduction).
    An estimate of the total number of hours needed annually to comply 
with the information collection requirement or request: -5,280 
(reduction or reporting hours).
    Abstract: This proposed 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.
    The U.S. Nuclear Regulatory Commission is seeking public comment on 
the potential impact of the information collections contained in this 
proposed rule and on the following issues:
    1. Is the proposed information collection necessary for the proper 
performance of the functions of the NRC, including whether the 
information will have practical utility?
    2. Is the estimate of the burden of the proposed information 
collection accurate?
    3. Is there a way to enhance the quality, utility, and clarity of 
the information to be collected?
    4. How can the burden of the proposed information collection on 
respondents be minimized, including the use of automated collection 
techniques or other forms of information technology?
    A copy of the OMB clearance package and proposed rule is available 
in ADAMS (Accession Nos. ML20178A449 and ML20178A439) or may be viewed 
free of charge at the NRC's PDR, One White Flint North, 11555 Rockville 
Pike, Room O-1 F21, Rockville, MD 20852. You may obtain information and 
comment submissions related to the OMB clearance package by searching 
on https://www.regulations.gov under Docket ID NRC-2018-0290.

[[Page 16102]]

    You may submit comments on any aspect of these proposed information 
collection(s), including suggestions for reducing the burden and on the 
previously stated issues, by the following methods:
     Federal Rulemaking Website: 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].
    Submit comments by April 26, 2021. Comments received after this 
date will be considered if it is practical to do so, but the NRC staff 
is able to ensure consideration only for comments received on or before 
this date.

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.

XI. Regulatory Analysis

    The NRC has prepared a draft regulatory analysis on this proposed 
rule. The analysis examines the costs and benefits of the alternatives 
considered by the Commission. The NRC requests public comments on the 
draft regulatory analysis, (ADAMS Accession No. ML20178A448). Comments 
on the draft analysis may be submitted to the NRC by any method 
provided in the ADDRESSES section of this document.

XII. 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 rulemaking proposes to incorporate 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.

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).

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 shall 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 rulemaking, 
the NRC's proposal to eliminate some older Section XI editions and 
addenda from the regulations these revisions would not be 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

[[Page 16103]]

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 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: Proposed 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 
proposed 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 proposed 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 proposed change is 
not a backfit.
    2. Add Sec.  50.55a(b)(1)(xiii)(A) through (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 restore 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 
proposal to remove 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 proposal 
to remove 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 proposal to 
remove specific editions and addenda from Sec.  50.55a(a)(1)(ii). These 
changes to Sec.  50.55a(b)(2)(ix) 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.
    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 proposed 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 proposed 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 proposed 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 proposed 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

[[Page 16104]]

2019 and future editions of the code. The proposed condition represents 
a relaxation from the current requirements. Therefore, the revision of 
this condition is not a backfit.
    11. Revise Sec.  50.55a(b)(2)(xl) to prohibit the use of the ASME 
BPV Code, Section XI, 2017 and 2019 Editions, Subparagraphs IWB-
3510.4(b)(4) and IWB-3510.4(b)(5). Further, revise Sec.  
50.55a(b)(2)(xl) to prohibit the use of the ASME BPV Code, Section XI, 
2019 Edition, Tables A-4200-1 and G-2110-1. The proposed updated 
condition on the use of IWC-3510.5(b) and the new tables does not 
constitute a new or changed NRC position. Therefore, the addition of 
this proposed 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 
proposed condition on regulatory submittal requirements does not 
constitute a new or changed NRC position. Therefore, the addition of 
this proposed 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 proposal to 
remove 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 
proposed rule change would allow 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. This proposed change would allow 
increased flexibility in the testing interval where justified and, 
therefore, is 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 and interim IST 
Plan updates 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 the 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 continuing 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.

XIV. Regulatory Flexibility Certification

    Under the Regulatory Flexibility Act of 1980 (5 U.S.C. 605(b)), the 
NRC certifies that this proposed rule does not impose a significant 
economical impact on a substantial number of small entities. This 
proposed rule affects only the licensing and operation of commercial 
nuclear power plants. A licensee who is a subsidiary of a large entity 
does not qualify as a small entity. The companies that own these plants 
are not ``small entities'' as defined in the Regulatory Flexibility Act 
or the size standards established by the NRC (Sec.  2.810), as the 
companies:
     Provide services that are not engaged in manufacturing, 
and have average gross receipts of more than $6.5 million over their 
last 3 completed fiscal years, and have more than 500 employees;
     Are not governments of a city, county, town, township or 
village;
     Are not school districts or special districts with 
populations of less than 50; and
     Are not small educational institutions.

XV. Availability of Documents

    The NRC is making the documents identified in Table 1 available to 
interested persons through one or more of the following methods, as 
indicated. To access documents related to this action, see the 
ADDRESSES section of this document.

                                       Table 1--Availability of Documents
----------------------------------------------------------------------------------------------------------------
                         Document                                           ADAMS Accession No.
----------------------------------------------------------------------------------------------------------------
                                             Proposed Rule Documents
----------------------------------------------------------------------------------------------------------------
Rulemaking: Proposed Rule: Regulatory Analysis RE:         ML20178A448
 Proposed Rule to Incorporate by Reference American
 Society of Mechanical Engineers Codes.
Rulemaking: Proposed Rule: Unofficial Redline Strikeout    ML20178A464
 of the NRC's Proposed Rule: RE: Proposed Rule to
 Incorporate by Reference American Society of Mechanical
 Engineers Codes.
----------------------------------------------------------------------------------------------------------------
                                                Related Documents
----------------------------------------------------------------------------------------------------------------
Email from Louise Lund, NRC, to Allyson B. Byk, ASME,      ML21014A012
 ``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. Byk, ASME,      ML20308A511
 ``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.

[[Page 16105]]

 
Email from Louise Lund, NRC, to Christian A. Sanna, ASME,  ML20127H677
 ``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 Louise Lund, NRC,  ML20127H684
 ``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 June 4, 2020, Public Meeting with the       ML20163A609
 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 Meeting with the       ML20189A286
 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--Affirmation Session, 11:30 a.m.,       ML003755050
 Friday, September 10, 1999, Commissioners' Conference
 Room, One White Flint North, Rockville, Maryland (Open
 to Public Attendance).
Enforcement Guidance Memorandum 14-003, ``Enforcement      ML14169A582
 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 Inspection      ML031140549
 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 of Later       ML042590067
 Editions and Addenda to ASME Code Section XI for Repair/
 Replacement Activities,'' October 19, 2004.
Regulatory Guide 1.28, Revision 5,``Quality Assurance      ML17207A293
 Program Criteria (Design and Construction),'' October
 2017.
Regulatory Guide 1.147, Revision 19, ``Inservice           ML19128A244
 Inspection Code Case Acceptability, ASME Section XI,
 Division 1,'' October 2019.
Regulatory Guide 1.178, Revision 1, ``An Approach for      ML032510128
 Plant-Specific Risk-Informed Decisionmaking for
 Inservice Inspection of Piping,'' September 2003.
Regulatory Guide 1.200, Revision 2, ``An Approach for      ML090410014
 Determining the Technical Adequacy of Probabilistic Risk
 Assessment Results for Risk-Informed Activities,'' March
 2009.
NUREG-0800, NRC Standard Review Plan for the Review of     ML032510135
 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 Issue 29:       ML031430208
 Bolting Degradation or Failure in Nuclear Power
 Plants,'' June 1990.
NUREG-1801, Revision 2, ``Generic Aging Lessons Learned    ML103490041
 (GALL) Report,'' December 2010.
NUREG-1800, Revision 2, ``Standard Review Plan for Review  ML103490036
 of License Renewal Applications for Nuclear Power
 Plants,'' December 2010.
NUREG-2191, ``Generic Aging Lessons Learned for            ML17187A031
 Subsequent License Renewal (GALL-SLR) Report,'' July      ML17187A204
 2017.
NUREG-1950, ``Disposition of Public Comments and           ML11116A062
 Technical Bases for Changes in the License Renewal
 Guidance Documents NUREG-1801 and NUREG-1800,'' April
 2011.
NUREG-2192, ``Standard Review Plan for Review of           ML17188A158
 Subsequent License Renewal Applications for Nuclear
 Power Plants,'' July 2017.
Report Number PNNL-29761, ``Nondestructive Examination     ML20079E343
 (NDE) Training and Qualifications: Implications of
 Research on Human Learning and Memory, Instruction and
 Expertise,'' March 2020.
----------------------------------------------------------------------------------------------------------------
                                      ASME Codes, Standards, and Code Cases
----------------------------------------------------------------------------------------------------------------
ASME BPV Code, Section III, Division 1: 2019 Edition.....  http://go.asme.org/NRC-ASME
ASME BPV Code, Section XI, Division 1: 2019 Edition......  http://go.asme.org/NRC-ASME
ASME OM Code, Division 1: 2020 Edition...................  http://go.asme.org/NRC-ASME
ASME NQA-1b-2011.........................................  http://go.asme.org/NRC-ASME
ASME NQA-1-2012..........................................  http://go.asme.org/NRC-ASME
ASME NQA-1-2015..........................................  http://go.asme.org/NRC-ASME
----------------------------------------------------------------------------------------------------------------

    Throughout the development of this rulemaking, the NRC may post 
documents related to this proposed rule, including public comments, on 
the Federal rulemaking website at https://www.regulations.gov under 
Docket ID NRC-2018-0290. The Federal rulemaking website allows you to 
receive alerts when changes or additions occur in a docket folder. To 
subscribe: (1) Navigate to the docket folder for NRC-2018-0290; (2) 
click the ``Sign up for Email Alerts'' link; and (3) enter your email 
address and select how frequently you would like to receive emails 
(daily, weekly, or monthly).

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. 553, the NRC proposes to adopt 
the following amendments to 10 CFR part 50:

[[Page 16106]]

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) and (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 phrase ``the 
1995 Edition through'';
0
e. Revise and republish paragraphs (b)(2)(xviii) through (xxi), (xxv), 
(xxvi), (xxix), (xxxii), (xxxvi), (xxxix), and (xl);
0
f. Add paragraph (b)(2)(xliii);
0
g. In paragraph (b)(3) introductory text, remove the phrase ``1995 
Edition through the latest edition'' and add in its place the word 
``editions'';
0
h. Revise and republish paragraph (b)(3)(iii);
0
i. 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;
0
j. Revise and republish paragraphs (b)(3)(vii) through (xi) and (f)(4);
0
k. Add paragraph (f)(7); and
0
l. 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.
* * * * *
    (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 Edition; and
    (6) NQA-1--2015 Edition.
* * * * *
    (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 I of this 
section for welds with leg size less than 1.09 tn:

                   Table I--Prohibited Code Provisions
------------------------------------------------------------------------
          Editions and addenda                    Code provision
------------------------------------------------------------------------
1989 Addenda through the latest edition  Subparagraph NB-3683.4(c)(1);
 and addenda incorporated by reference    Subparagraph NB-3683.4(c)(2).
 in paragraph (a)(1)(i) of this section.

[[Page 16107]]

 
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 edition  Footnote 11 to Table NC-
 and addenda incorporated by reference    3673.2(b)-1; Note 11 to Table
 in paragraph (a)(1)(i) of this section.  ND-3673.2(b)-1.
------------------------------------------------------------------------

    (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) 
through (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-
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

[[Page 16108]]

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) through (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 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:

[[Page 16109]]

    (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 
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

[[Page 16110]]

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 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

[[Page 16111]]

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, 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 
first full 10-year 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 which are disassembled

[[Page 16112]]

and reassembled during the performance of a Section XI repair/
replacement activity requiring documentation on a Form NIS-2 shall be 
leak tested to ensure leak tightness. The owner shall establish the 
type of leak test, test medium, test pressure, acceptance criteria that 
would demonstrate the joint's leak tightness, and the qualifications of 
the personnel who will perform the leak test.
* * * * *
    (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.
    (xl) Section XI condition: Prohibitions and Restrictions on use of 
IWB-3510.4(b), IWC-3510.5(b), Table A-4200-1, and Table G-2110-1. The 
use of Subparagraphs IWB-3510.4(b)(4) and IWB-3510.4(b)(5) of ASME BPV 
Code, Section XI, 2017 Edition through the latest edition incorporated 
by reference in paragraph (a)(1)(ii) of this section is prohibited. The 
use of ASME BPV Code, Section XI, 2019 Edition, Subparagraphs IWC-
3510.5(b)(4) and IWC-3510.5(b)(5), is prohibited. For ASME BPV Code, 
Section XI, 2019 Edition, Table A-4200-1 and Table G-2110-1, use of 
Figure A-4200-1 and Figure G-2210-1 to describe the toughness of 
material SA-533 Type B Class 2 is prohibited without satisfying the 
requirements of IWB-3510.4(c) or IWC-3510.5(c).
* * * * *
    (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.
* * * * *
    (vii) [Reserved]
    (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

[[Page 16113]]

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, the position verification testing specified in 
paragraph ISTC-3700 may be performed on a 10-year interval where the 
licensee documents a justification, which is made available for NRC 
review, demonstrating that the stem-disk connection is not susceptible 
to separation based on the internal design and evaluation of the stem-
disk connection using plant-specific and industry operating experience 
and vendor recommendations.
* * * * *
    (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 in accordance with paragraph 
(f)(6)(ii) of this section. This use of an augmented IST program may be 
acceptable 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. IST Plan revisions must 
be submitted when the final safety analysis report for the applicable 
nuclear power plant is updated. 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 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

[[Page 16114]]

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 March 18, 2021.

    For the Nuclear Regulatory Commission.
Andrea D. Veil,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 2021-06085 Filed 3-25-21; 8:45 am]
BILLING CODE 7590-01-P