American Society of Mechanical Engineers (ASME) Codes and New and Revised ASME Code Cases, 24324-24361 [2010-9700]
Download as PDF
24324
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 50
RIN 3150–AI35
[NRC 2008–0554]
American Society of Mechanical
Engineers (ASME) Codes and New and
Revised ASME Code Cases
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
AGENCY: Nuclear Regulatory
Commission (NRC).
ACTION: Proposed rule.
SUMMARY: The NRC proposes to amend
its regulations to incorporate by
reference the 2005 Addenda through
2008 Addenda of Section III, Division 1,
and the 2005 Addenda through 2008
Addenda of Section XI, Division 1, of
the ASME Boiler and Pressure Vessel
Code (ASME B&PV Code); and the 2005
Addenda and 2006 Addenda of the
ASME Code for Operation and
Maintenance of Nuclear Power Plants
(ASME OM Code). The NRC also
proposes to incorporate by reference
ASME Code Case N–722–1, ‘‘Additional
Examinations for PWR Pressure
Retaining Welds in Class 1 Components
Fabricated With Alloy 600/82/182
Materials Section XI, Division 1,’’ and
Code Case N–770, ‘‘Alternative
Examination Requirements and
Acceptance Standards for Class 1 PWR
[Pressurized-Water Reactor] Piping and
Vessel Nozzle Butt Welds Fabricated
with UNS N06082 or UNS W86182
Weld Filler Material with or without
Application of Listed Mitigation
Activities.’’
DATES: Submit comments by July 19,
2010. Comments received after this date
will be considered if it is practical to do
so, but the NRC is able to ensure
consideration only of comments
received on or before this date.
ADDRESSES: Please include Docket ID
NRC–2008–0554 in the subject line of
your comments For instructions on
submitting comments and accessing
documents related to this action, see
Section I, ‘‘Submitting Comments and
Accessing Information’’ in the
SUPPLEMENTARY INFORMATION section of
this document. You may submit
comments by any one of the following
methods.
Federal Rulemaking Web Site: Go to
https://www.regulations.gov and search
for documents filed under Docket ID
NRC–2008–0554. Address questions
about NRC dockets to Carol Gallagher,
telephone 301–492–3668, e-mail
Carol.Gallager@nrc.gov.
Mail comments to: Secretary, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, ATTN:
Rulemakings and Adjudications Staff.
E-mail comments to:
Rulemaking.Comments@nrc.gov. If you
do not receive a reply e-mail confirming
that we have received your comments,
contact us directly at 301–415–1677.
Hand-deliver comments to: 11555
Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m.
Federal workdays. (Telephone 301–415–
1677)
Fax comments to: Secretary, U.S.
Nuclear Regulatory Commission at 301–
415–1101.
You may submit comments on the
information collections by the methods
indicated in the Paperwork Reduction
Act Statement.
FOR FURTHER INFORMATION CONTACT: L.
Mark Padovan, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone 301–415–
1423, e-mail Mark.Padovan@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Submitting Comments and Accessing
Information
II. Background
III. Discussion of NRC Approval of New
Edition and Addenda to the Code, ASME
Code Cases N–722–1 and N–770, and
Other Proposed Changes to 10 CFR
50.55a
a. Quality Standards, ASME Codes and
Institute of Electrical and Electronics
Engineers (IEEE) Standards, and
Alternatives
b. Applicant/Licensee-Proposed
Alternatives to the Requirements of 10
CFR 50.55a
c. Standards Approved for Incorporation
by Reference
d. ASME B&PV Code, Section III
e. ASME B&PV Code, Section XI
f. ASME OM Code
g. Reactor Coolant Pressure Boundary,
Quality Group B Components, and
Quality Group C Components
h. Inservice Testing Requirements
i. Inservice Inspection Requirements
j. Substitution of the Term ‘‘Condition’’ in
10 CFR 50.55a
IV. Paragraph-by-Paragraph Discussion
V. Generic Aging Lessons Learned (GALL)
Report
VI. Specific Request for Comments
VII. Voluntary Consensus Standards
VIII. Finding of No Significant
Environmental Impact: Environmental
Assessment
IX. Paperwork Reduction Act Statement
X. Regulatory and Backfit Analysis
XI. Regulatory Flexibility Certification
I. Submitting Comments and Accessing
Information
Comments submitted in writing or in
electronic form will be posted on the
NRC Web site and on the Federal
rulemaking Web site Regulations.gov.
Because your comments will not be
edited to remove any identifying or
contact information, the NRC cautions
you against including any information
in your submission that you do not want
to be publicly disclosed. The NRC
requests that any party soliciting or
aggregating comments received from
other persons for submission to the NRC
inform those persons that the NRC will
not edit their comments to remove any
identifying or contact information, and
therefore, they should not include any
information in their comments that they
do not want publicly disclosed.
You can access publicly available
documents related to this document,
including the following documents,
using the following methods:
NRC’s Public Document Room (PDR):
The public may examine, and have
copied for a fee, publicly-available
documents at the NRC’s PDR, Room O1–
F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland.
NRC’s Agencywide Documents Access
and Management System (ADAMS):
Publicly available documents created or
received at the NRC are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this page,
the public can gain entry into ADAMS,
which provides text and image files of
NRC’s public documents. If you do not
have access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC’s
PDR reference staff at 1–800–397–4209,
301–415–4737, or by e-mail to
pdr.resource@nrc.gov.
Federal Rulemaking Web Site: Public
comments and supporting materials
related to this proposed rule can be
found at https://www.regulations.gov by
searching on Docket ID NRC–2008–
0554.
Document
PDR
Rulemaking
Web site
Reading room
ASME B&PV Code* .....................................................................................................................
ASME Code Case N–770* ..........................................................................................................
ASME Code Case N–772–1* ......................................................................................................
X
X
X
........................
........................
........................
........................
........................
........................
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
PO 00000
Frm 00002
Fmt 4701
Sfmt 4702
E:\FR\FM\04MYP3.SGM
04MYP3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
24325
Document
PDR
Rulemaking
Web site
Reading room
ASME OM Code* .........................................................................................................................
EPRI Report NP–5151**, ‘‘Evaluation of Reactor Vessel Beltline Integrity Following Unanticipated Operating Events,’’ April 1987 .......................................................................................
Final Safety Evaluation by the Office of Nuclear Reactor Regulation on Topical Report NEI
94–01, Revision 2, ‘‘Industry Guideline for Implementing Performance-Based Option of 10
CFR Part 50, Appendix J,’’ June 25, 2008 ..............................................................................
GALL Report, NUREG–1801, Rev.1, September 2005:
Volume 1, .............................................................................................................................
Volume 2 ..............................................................................................................................
NQA–1*, ‘‘Quality Assurance Requirements for Nuclear Facilities,’’ 1994 Edition .....................
NUREG–1800, Rev. 1, ‘‘Standard Review Plan for Review of License Renewal Applications
for Nuclear Power Plants, September 2005 ............................................................................
Regulatory and Backfit Analysis for proposed rule .....................................................................
Regulatory Guide 1.178, ‘‘An Approach for Plant-Specific Risk-Informed Decisionmaking for
Inservice Inspection of Piping’’ .................................................................................................
Regulatory Guide 1.193, Revision 2, ‘‘ASME Code Cases not Approved for Use.’’ ..................
Regulatory Guide 1.200, ‘‘An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities’’ ..............................................
Standard Review Plan 3.9.8, ‘‘Risk-Informed Inservice Inspection of Piping’’ ............................
X
........................
........................
........................
........................
........................
X
........................
ML081140105
X
X
........................
........................
........................
........................
ML052770419
ML052780376
........................
X
X
........................
X
ML052770566
ML092510270
X
X
........................
........................
........................
ML072470294
X
X
........................
........................
........................
........................
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
* Available on the ASME Web site.
** Available on the EPRI Web site.
II. Background
The ASME develops and publishes
the ASME B&PV Code, which contains
requirements for the design,
construction, and inservice inspection
(ISI) of nuclear power plant
components; and the ASME OM Code,
which contains requirements for
inservice testing (IST) of nuclear power
plant components. The ASME issues
new editions of the ASME B&PV Code
every 3 years and issues addenda to the
editions yearly except in years when a
new edition is issued. Periodically, the
ASME publishes new editions and
addenda of the ASME OM Code. The
new editions and addenda typically
revise provisions of the 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 Codes do not
significantly change Code philosophy or
approach.
The ASME B&PV and OM Codes are
national voluntary consensus standards,
and are required by the National
Technology Transfer and Advancement
Act of 1995, Public Law 104–113, to be
used by government agencies instead of
government-unique standards, unless
the use of such a standard is
inconsistent with applicable law or is
otherwise impractical. It has been the
NRC’s practice to review new editions
and addenda of the ASME B&PV and
OM Codes and periodically update 10
CFR 50.55a to incorporate newer
editions and addenda by reference. The
NRC approves and/or mandates the use
of editions and addenda of the Codes in
10 CFR 50.55a through the rulemaking
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
process of ‘‘incorporation by reference.’’
As such, each provision of the Codes
incorporated by reference into, and
mandated by, 10 CFR 50.55a constitutes
a legally-binding NRC requirement
imposed by rule. As the Codes are
consensus documents, there may be
disagreement among the technical
experts regarding what constitutes an
acceptable level of safety. The NRC
proposed conditions enhance the
provisions in the Code in instances
where the NRC has determined that the
provisions do not provide an acceptable
level of safety. In other instances,
research data or experience has shown
that certain Code provisions are
unnecessarily conservative, and the
NRC has determined that the Code
revisions are acceptable. This
rulemaking is the latest in a series of
rulemakings which incorporate by
reference new editions and/or addenda
of the Codes which are approved for
use, either unconditionally or with
conditions. The editions and addenda of
the ASME B&PV and OM Codes were
last incorporated by reference into the
regulations in a final rule dated
September 10, 2008 (73 FR 52730), as
corrected on October 2, 2008 (73 FR
57235), incorporating Section III of the
2004 Edition of the ASME B&PV Code,
Section XI of the 2004 Edition of the
ASME B&PV Code, and the 2004 Edition
of the ASME OM Code, subject to NRC
conditions.
PO 00000
Frm 00003
Fmt 4701
Sfmt 4702
III. Discussion of NRC Approval of New
Edition and Addenda to the Codes,
ASME Code Cases N–722–1 and N–770,
and Other Proposed Changes to 10 CFR
50.55a
The NRC proposes to amend its
regulations to incorporate by reference
the 2005 Addenda through 2008
Addenda of Section III, Division 1, and
Section XI, Division 1 of the ASME
B&PV Code; and the 2005 Addenda and
2006 Addenda of the ASME OM Code
into 10 CFR 50.55a. The NRC also
proposes to incorporate by reference
Code Case N–770, and revision 1 to
Code Case N–722, which was
incorporated by reference into the
NRC’s regulations on September 10,
2008 (73 FR 52729).
The NRC follows a three-step process
to determine acceptability of new
provisions in new editions and addenda
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, 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 in support of each
new or revised Code. Second, the NRC
committee representatives discuss the
Codes and technical justifications with
other cognizant NRC staff to ensure an
adequate technical review. Finally, the
proposed NRC position on each Code is
reviewed and approved by NRC
management as part of the rulemaking
amending 10 CFR 50.55a to incorporate
by reference new editions and addenda
of the ASME Codes, and conditions on
E:\FR\FM\04MYP3.SGM
04MYP3
24326
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
their use. This regulatory process, when
considered together with the ASME’s
own process for developing and
approving ASME Codes provides
reasonable assurances 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 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 and addenda of
the Codes identified in this rulemaking.
The NRC concluded, in accordance with
the process for review of changes to the
Codes, that each of the editions and
addenda of the Codes, and the 1994
Edition of NQA–1, are technically
adequate, consistent with current NRC
regulations, and approved for use with
the specified conditions. Table 1
identifies where the NRC proposes to
change (clarify the regulation; or impose
new, revise existing, or remove
conditions in) 10 CFR 50.55a. Due to the
extent of the proposed revisions to 10
CFR 50.55a(b)(2), the NRC is proposing
to revise this portion of the regulations
in its entirety, including the
redesignation of paragraphs within the
section. These proposed redesignations
are also outlined in Table 1 of this
document.
TABLE 1—REDESIGNATION OF PARAGRAPHS AND DESCRIPTION OF PROPOSED CHANGES TO 10 CFR 50.55a
Proposed regulation
Current regulation
Description of proposed changes
Applicant/Licensee-Proposed Alternatives to the Requirements of 10 CFR 50.55a
Paragraph (a) ..................................
Paragraph (a) ................................
Paragraph (a)(3) ..............................
Paragraph (a)(3) ............................
Revise to title the paragraph Quality standards, ASME Codes and
IEEE standards, and alternatives.
Revise to clarify that an alternative is to be submitted to, and approved by, the NRC prior to implementing the alternative.
Standards Approved for Incorporation by Reference
Introductory text to paragraph (b) ...
Introductory text to paragraph (b)
Revise to title the paragraph Standards approved for incorporation by
reference. Revise to incorporate by reference the ASME B&PV
Code, Section III, Division 1 (excluding Non-mandatory Appendices), and Section XI, Division 1, and ASME OM Code, which are
referenced in paragraphs (b)(1), (b)(2), and (b)(3) of this section. In
addition, ASME Code Cases N–722–1 and N-770 would be incorporated by reference.
ASME B&PV Code, Section III
Introductory text to paragraph (b)(1)
Introductory
(b)(1).
Paragraph (b)(1)(ii) ..........................
Paragraph (b)(1)(ii), ‘‘Weld leg dimensions’’.
Introductory
(b)(1)(iii).
paragraph
Introductory text to paragraph
(b)(1)(iii), ‘‘Seismic design of
piping’’.
Paragraphs
(b)(1)(iii)(A),
(b)(1)(iii)(B), and (b)(1)(iii)(C).
........................................................
Paragraph (b)(1)(iv) .........................
Paragraph (b)(1)(iv) ‘‘Quality assurance’’.
........................................................
text
to
Paragraph (b)(1)(vii) ........................
text
to
paragraph
Revise to clarify the wording and include the 1974 Edition (Division 1)
through the 2008 Addenda (Division 1), subject to conditions.
Change ‘‘limitations and modifications’’ to ‘‘conditions.’’
Revise the current conditions on the use of stress indices used for
welds in piping design under Subarticles NB–3600, NC–3600, and
ND–3600. Make editorial corrections and additions.
Revise to include the latest addenda to Section III of the ASME
B&PV Code (2006 Addenda through the 2008 Addenda) and Subarticle NB–3200 of the 2004 Edition through the 2008 Addenda of
the ASME B&PV Code subject to the condition outlined in paragraph (b)(1)(iii)(B). Change ‘‘limitation’’ to ‘‘condition.’’
Add new conditions on the use of Subarticles NB–3200, NB–3600,
NC–3600 and ND–3600 identified in the introductory text to paragraph (b)(1)(iii).
Revise to incorporate by reference the 1994 Edition of NQA–1,
‘‘Quality Assurance Requirements for Nuclear Facilities.’’
Add a new condition to prohibit the use of paragraph NB–7742 of the
2006 Addenda up to and including the 2007 Edition and 2008 Addenda of the ASME B&PV Code, Section III.
ASME B&PV Code, Section XI
Introductory
(b)(2).
NA ...................................................
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Introductory text to paragraph (b)(2)
Paragraph (b)(2)(i), ‘‘Limitations on
specific editions and addenda’’.
Paragraph (b)(2)(ii), ‘‘Pressure-retaining welds in ASME Code
Class 1 piping (applies to Table
IWB–2500 and IWB–2500–1
and Category B–J’’.
Paragraph (b)(2)(iii), ‘‘Steam generator tubing (modifies Article
IWB–2000)’’.
Paragraph (b)(2)(i) ..........................
NA ...................................................
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
PO 00000
text
to
Frm 00004
paragraph
Fmt 4701
Revise to clarify the wording and incorporate by reference the 2005
Addenda through 2008 Addenda of the ASME B&PV Code into
§ 50.55a; only Subsections IWA, IWB, IWC, IWD, IWE, IWF, IWL;
Mandatory and Non-Mandatory Appendices of Division 1 are incorporated by reference into 10 CFR 50.55a, with conditions. Change
‘‘limitations and modifications’’ to ‘‘conditions.’’
Remove because licensees are no longer using the 1974 and 1977
Editions and addenda of the ASME B&PV Code.
Redesignate paragraph (b)(2)(ii) as paragraph (b)(2)(i).
Remove because the condition in the paragraph is redundant to the
1989 Edition through the 2008 Addenda of Section XI.
Sfmt 4702
E:\FR\FM\04MYP3.SGM
04MYP3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
24327
TABLE 1—REDESIGNATION OF PARAGRAPHS AND DESCRIPTION OF PROPOSED CHANGES TO 10 CFR 50.55a—Continued
Proposed regulation
Current regulation
Description of proposed changes
NA ...................................................
Paragraph (b)(2)(iv), ‘‘Pressure retaining welds in ASME Code
Class 2 piping’’.
Paragraph (b)(2)(v), re: Evaluation
procedures and acceptance criteria for austenitic piping.
Paragraph (b)(2)(vi), ‘‘Effective edition and addenda of Subsection
IWE and Subsection IWL, Section XI’’.
Paragraph (b)(2)(vii), ‘‘Section XI
references to OM Part 4, OM
Part 6 and OM Part 10 (Table
IWA–1600–1)’’.
Paragraph (b)(2)(viii), ‘‘Examination of concrete containments’’.
Remove because licensees are no longer using these older editions
and addenda of the code.
NA ...................................................
Paragraph (b)(2)(ii) ..........................
Paragraph (b)(2)(iii) .........................
Paragraph (b)(2)(iv) .........................
Paragraph (b)(2)(v) .........................
Paragraph (b)(2)(ix), ‘‘Examination
of metal containments and the
liners of concrete containments’’.
Paragraph (b)(2)(vi) .........................
Paragraph (b)(2)(x), ‘‘Quality assurance’’.
Paragraph (b)(2)(xi) [Reserved] ....
Paragraph (b)(2)(xii), ‘‘Underwater
welding’’.
Paragraph (b)(2)(xiii) [Reserved] ...
Paragraph (b)(2)(xiv), ‘‘Appendix
VIII personnel qualification’’.
Paragraph (b)(2)(xv), ‘‘Appendix
VIII specimen set and qualification requirements’’.
Paragraph (b)(2)(vii) ........................
Paragraph (b)(2)(viii) .......................
Paragraph (b)(2)(ix) .........................
Paragraph (b)(2)(x) .........................
Paragraph (b)(2)(xi) .........................
Paragraph (b)(2)(xii) ........................
Paragraph (b)(2)(xiii) .......................
Paragraph (b)(2)(xiv)(A) ..................
Paragraph (b)(2)(xiv)(B) ..................
Paragraph (b)(2)(xvi), ‘‘Appendix
VIII single side ferritic vessel
and piping and stainless steel
piping examination’’.
Paragraph (b)(2)(xvii), ‘‘Reconciliation of Quality Requirements’’.
Paragraph (b)(2)(xviii)(A), ‘‘Certification of NDE personnel’’.
Paragraph (b)(2)(xviii)(B), ‘‘Certification of NDE personnel’’.
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Paragraph (b)(2)(xiv)(C) ..................
Paragraph (b)(2)(xviii)(C), ‘‘Certification of NDE personnel’’.
Paragraph (b)(2)(xv) ........................
Paragraph (b)(2)(xix), ‘‘Substitution
of alternative methods’’.
Paragraph (b)(2)(xvi) .......................
Paragraph (b)(2)(xx), ‘‘System
leakage tests’’.
Paragraph (b)(2)(xxi), ‘‘Table IWB–
2500–1 examination requirements’’.
Paragraph (b)(2)(xvii) ......................
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
PO 00000
Frm 00005
Fmt 4701
Remove because licensees are no longer using the Winter 1983 Addenda and the Winter 1984 Addenda of Section XI.
Redesignate paragraph (b)(2)(vi) as paragraph (b)(2)(ii). Change
‘‘modified and supplemented’’ to ‘‘conditioned.’’
Redesignate paragraph (b)(2)(vii) as paragraph (b)(2)(iii).
Redesignate paragraph (b)(2)(viii) as paragraph (b)(2)(iv), and revise
the introductory text to remove the conditions in redesignated paragraphs (b)(2)(iv)(F) and (b)(2)(iv)(G) when using the 2007 Edition
with 2008 Addenda of the ASME Code, Section XI.
Redesignate paragraph (b)(2)(ix) as paragraph (b)(2)(v), and revise
the introductory text to remove the conditions in redesignated paragraphs (b)(2)(v)(F), (b)(2)(v)(G), (b)(2)(v)(H) and (b)(2)(v)(I) when
applying the 2004 Edition with 2006 Addenda through the 2007
Edition with 2008 Addenda of the ASME Code, Section XI and remove the condition in redesignated paragraph (b)(2)(v)(I) when applying the 2004 Edition, up to and including, the 2005 Addenda.
Add a new condition as paragraph (b)(2)(v)(J) on the use of Article
IWE–5000 of Subsection IWE when applying the 2007 Edition up
to and including the 2008 Addenda of the ASME Code, Section XI.
Redesignate paragraph (b)(2)(x) as paragraph (b)(2)(vi).
Redesignate paragraph (b)(2)(xi) as paragraph (b)(2)(vii).
Redesignate paragraph (b)(2)(xii) as paragraph (b)(2)(viii).
Redesignate paragraph (b)(2)(xiii) as paragraph (b)(2)(ix).
Redesignate paragraph (b)(2)(xiv) as paragraph (b)(2)(x).
Redesignate paragraph (b)(2)(xv) as paragraph (b)(2)(xi) and revise it
so that existing conditions would not apply to the 2007 Edition
through the 2008 Addenda of Section XI. Change ‘‘provisions’’ to
‘‘conditions’’ in the introductory text to redesignated paragraphs
(b)(2)(xi), (b)(2)(xi)(B), (b)(2)(xi)(C), (b)(2)(xi)(D), (b)(2)(xi)(E),
(b)(2)(xi)(F), (b)(2)(xi)(G), (b)(2)(xi)(K), and (b)(2)(xi)(K)(1). Change
‘‘provisions of’’ to ‘‘conditions in’’ in paragraph (b)(2)(xi)(G)(3).
Change ‘‘modified’’ and ‘‘modification’’ to ‘‘conditioned’’ and ‘‘condition’’ in (b)(2)(xi)(K)(2)(i), (b)(2)(xi)(K)(2)(iii), (b)(2)(xi)(K)(3)(i),
(b)(2)(xi)(K)(3)(ii), (b)(2)(xi)(K)(4), and (b)(2)(xi)(L), where applicable.
Redesignate paragraph (b)(2)(xvi) as paragraph (b)(2)(xii). Change
‘‘modified’’ to ‘‘conditioned’’ in redesignated paragraphs
(b)(2)(xii)(A) and (b)(2)(xii)(B).
Redesignate paragraph (b)(2)(xvii) as paragraph (b)(2)(xiii).
Redesignate paragraph (b)(2)(xviii)(A) as paragraph (b)(2)(xiv)(A).
Redesignate paragraph (b)(2)(xviii)(B) as paragraph (b)(2)(xiv)(B),
and revise it so that existing condition would not apply to the 2007
Edition through the 2008 Addenda of Section XI.
Redesignate paragraph (b)(2)(xviii)(C) as paragraph (b)(2)(xiv)(C),
and revise it such that the existing conditions on the qualification of
VT–3 examination personnel would not apply to the 2005 Addenda
through the 2008 Addenda of Section XI.
Redesignate paragraph (b)(2)(xix) as paragraph (b)(2)(xv), and revise
it so that existing conditions for the substitution of alternative examination methods would not apply when using the 2005 Addenda
through the 2008 Addenda.
Redesignate paragraph (b)(2)(xx) as paragraph (b)(2)(xvi).
Redesignate paragraph (b)(2)(xxi) as paragraph (b)(2)(xvii).
Sfmt 4702
E:\FR\FM\04MYP3.SGM
04MYP3
24328
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
TABLE 1—REDESIGNATION OF PARAGRAPHS AND DESCRIPTION OF PROPOSED CHANGES TO 10 CFR 50.55a—Continued
Proposed regulation
Current regulation
Paragraph (b)(2)(xviii) .....................
Paragraph (b)(2)(xxii), ‘‘Surface
examination’’.
Paragraph (b)(2)(xxiii), ‘‘Evaluation
of thermally cut surfaces’’.
Paragraph (b)(2)(xxiv), ‘‘Incorporation of the performance demonstration initiative and addition
of ultrasonic examination criteria’’.
Paragraph (b)(2)(xxv), ‘‘Mitigation
of defects by modification’’.
Paragraph (b)(2)(xxvi), ‘‘Pressure
testing class 1, 2, and 3 mechanical joints’’.
Paragraph (b)(2)(xxvii), ‘‘Removal
of insulation’’.
Paragraph (b)(2)(xix) .......................
Paragraph (b)(2)(xx) ........................
Paragraph (b)(2)(xxi) .......................
Paragraph (b)(2)(xxii) ......................
Paragraph (b)(2)(xxiii) .....................
New paragraph (b)(2)(xxiv), ‘‘Analysis of flaws’’.
New paragraph (b)(2)(xxv), ‘‘Evaluation of unanticipated operating
events’’.
New paragraph (b)(2)(xxvi), ‘‘Nonmandatory Appendix R’’.
Description of proposed changes
NA ..................................................
NA ..................................................
NA ..................................................
Redesignate paragraph (b)(2)(xxii) as paragraph (b)(2)(xviii).
Redesignate paragraph (b)(2)(xxiii) as paragraph (b)(2)(xix).
Redesignate paragraph (b)(2)(xxiv) as paragraph (b)(2)(xx), and revise it so that existing condition would not apply when using the
2007 Edition through the 2008 Addenda.
Redesignate paragraph (b)(2)(xxv) as paragraph (b)(2)(xxi).
Redesignate paragraph (b)(2)(xxvi) as paragraph (b)(2)(xxii).
Redesignate paragraph (b)(2)(xxvii) as paragraph (b)(2)(xxiii), and revise it to refer to IWA–5242 of the 2003 Addenda through the 2006
Addenda or IWA–5241 of the 2007 Edition through the 2008 Addenda of Section XI of the ASME B&PV Code for performing VT–2
visual examination of insulated components in systems borated for
the purpose of controlling reactivity.
Add to place conditions on the use of Section XI, Nonmandatory Appendix A, ‘‘Analysis of Flaws.’’
Add to place condition specifying that Section E–1200 of the ASME
B&PV Code, Section XI, Nonmandatory Appendix E, ‘‘Evaluation of
Unanticipated Operating Events,’’ is not acceptable for use.
Add condition that would require licensees to submit an alternative in
accordance with § 50.55a(a)(3), and obtain NRC authorization of
the proposed alternative prior to implementing Section XI,
Non-Mandatory Appendix R, RI–ISI programs.
ASME OM Code
Introductory text to paragraph (b)(3)
Introductory
(b)(3).
text
to
paragraph
Paragraph (b)(3)(v) .........................
Paragraph (b)(3)(v), ‘‘Subsection
ISTD’’.
Paragraph (b)(3)(vi) .........................
Paragraph (b)(3)(vi), ‘‘Exercise interval for manual valves’’.
Revise to incorporate by reference the 2005 and 2006 Addenda of
the ASME OM Code; Subsections ISTA, ISTB, ISTC, ISTD; Mandatory Appendices I and II; and Nonmandatory Appendices A
through H and J of the ASME OM Code into § 50.55a. Change
‘‘limitations and modifications’’ to ‘‘conditions.’’
Revise to recognize that snubbers are tested in accordance with Section ISTD of the ASME OM Code when using the 2006 Addenda
and later editions and addenda of Section XI of the ASME B&PV
Code.
Revise to state that this paragraph applies only when using the 1999
through 2005 Addenda of the ASME OM Code, as the 2006 Addenda of the ASME OM Code was revised to be consistent with
the conditions in paragraph (b)(3)(vi).
Reactor Coolant Pressure Boundary, Quality Group B Components, and Quality Group C Components
Paragraphs (c)(3), (d)(2) and (e)(2)
Paragraphs
(e)(2).
(c)(3),
(d)(2)
and
Revise to replace ‘‘but—’’ with ‘‘subject to the following conditions’’ at
the end of the introductory text to the paragraphs for clarity.
Inservice Testing
Paragraphs (f)(2), (f)(3)(v), and
(f)(4).
Paragraph (f)(5)(iv) ..........................
Paragraphs (f)(2), (f)(3)(v), and
(f)(4).
Paragraph (f)(5)(iv) ........................
Change ‘‘limitations and modifications’’ to ‘‘conditions.’’
Revise to clarify that licensees are required to submit requests for relief based on impracticality within 12 months after the expiration of
the IST interval for which relief is being sought.
Inservice Inspection
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Paragraph (g)(2) ..............................
Paragraph (g)(2) ............................
Paragraph (g)(3)(i) ..........................
Paragraph (g)(3)(i) .........................
Paragraph (g)(3)(ii) ..........................
Paragraph (g)(3)(ii) ........................
Paragraph (g)(3)(v) .........................
Paragraph (g)(3)(v) ........................
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
PO 00000
Frm 00006
Fmt 4701
Revise to include provisions for examination and testing snubbers in
Subsection ISTD of the ASME OM Code, and the optional ASME
code cases listed in Regulatory Guide 1.192. Change ‘‘limitations
and modifications’’ to ‘‘conditions.’’
Revise to include provisions for examination and testing snubbers in
Subsection ISTD of the ASME OM Code, and the optional ASME
code cases listed in Regulatory Guide 1.192.
Revise to include the provisions for examination and testing snubbers
in Subsection ISTD of the ASME OM Code, and the optional
ASME code cases listed in Regulatory Guide 1.192.
Change ‘‘limitations and modifications’’ to ‘‘conditions.’’
Sfmt 4702
E:\FR\FM\04MYP3.SGM
04MYP3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
24329
TABLE 1—REDESIGNATION OF PARAGRAPHS AND DESCRIPTION OF PROPOSED CHANGES TO 10 CFR 50.55a—Continued
Proposed regulation
Current regulation
Introductory text to paragraph (g)(4)
Introductory
(g)(4).
Paragraph (g)(4)(i) ..........................
Paragraph (g)(4)(i) .........................
Paragraph (g)(4)(ii) ..........................
Paragraph (g)(4)(ii) ........................
Paragraph (g)(4)(iii) .........................
Paragraph (g)(4)(iii) .......................
Paragraph (g)(4)(iv) .........................
Paragraph (g)(5)(iii) .........................
Paragraph (g)(4)(iv) .......................
Paragraph (g)(5)(iii) .......................
Paragraph (g)(5)(iv) .........................
Paragraph (g)(5)(iv) .......................
Paragraph (g)(6)(ii)(B) .....................
Paragraphs
(g)(6)(ii)(E)(1),
(g)(6)(ii)(E)(2), and (g)(6)(ii)(E)(3).
Paragraph (g)(6)(ii)(B) ...................
Paragraphs
(g)(6)(ii)(E)(1),
(g)(6)(ii)(E)(2),
and
(g)(6)(ii)(E)(3), ‘‘Reactor coolant
pressure boundary visual inspections’’.
NA ..................................................
New paragraph (g)(6)(ii)(F), ‘‘Inspection requirements for class 1
pressurized water reactor piping
and vessel nozzle butt welds’’.
Footnote 1 .......................................
text
to
Description of proposed changes
paragraph
Footnote 1 .....................................
For redesignated paragraphs in 10
CFR 50.55a, Table 2 cross-references the
Revise to include the provisions for examination and testing snubbers
in Subsection ISTD of the ASME OM Code. Change ‘‘limitation’’ to
‘‘condition’’ and ‘‘modifications’’ to ‘‘conditions.’’
Revise to include the provisions for examination and testing snubbers
in Subsection ISTD of the ASME OM Code, and the optional
ASME code cases listed in Regulatory Guide 1.192. Change ‘‘limitations and modifications’’ to ‘‘conditions.’’
Revise to include the provisions for examination and testing snubbers
in Subsection ISTD of the ASME OM Code, and the optional
ASME code cases listed in Regulatory Guide 1.192. Change ‘‘limitations and modifications’’ to ‘‘conditions.’’
Revise to provide the proper references to Section XI, Table IWB–
2500–1, ‘‘Examination Category B–J,’’ Item Numbers B9.20, B9.21
and B9.22.
Change ‘‘limitations and modifications’’ to ‘‘conditions.’’
Revise to clarify that a request for relief must be submitted to the
NRC no later than 12 months after the examination has been attempted during a given ISI interval and the ASME B&PV Code requirement determined to be impractical.
Revise to clarify that licensees are required to submit requests for relief based on impracticality within 12 months after the expiration of
the ISI interval for which relief is being sought.
Change ‘‘modifications and limitations’’ to ‘‘conditions.’’
Revise to update the requirements to Code Case N–722–1.
Add to incorporate ASME Code Case N–770, ‘‘Alternative Examination Requirements and Acceptance Standards for Class 1 PWR
Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082
or UNS W86182 Weld Filler Material With or Without Application of
Listed Mitigation Activities, Section XI, Division 1,’’ with conditions,
into 10 CFR 50.55a.
Revise footnote 1 to clarify what portion of welds has to be inspected
during the plant interval that remains after January 1, 2009.
proposed regulations with the current
regulations, and Table 3 cross-references
the current regulations with the
proposed regulations.
TABLE 2—CROSS REFERENCE OF PROPOSED REGULATIONS WITH CURRENT REGULATIONS
Proposed regulation
Current regulation
Description of proposed redesignations
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
ASME B&PV Code, Section XI
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
(b)(2)(i) ..........................
(b)(2)(ii) ..........................
(b)(2)(iii) .........................
(b)(2)(iv) .........................
(b)(2)(v) .........................
(b)(2)(vi) .........................
(b)(2)(vii) ........................
(b)(2)(viii) .......................
(b)(2)(ix) .........................
(b)(2)(x) .........................
(b)(2)(xi) .........................
(b)(2)(xii) ........................
(b)(2)(xiii) .......................
(b)(2)(xiv)(A) ..................
(b)(2)(xiv)(B) ..................
(b)(2)(xiv)(C) ..................
(b)(2)(xv) ........................
(b)(2)(xvi) .......................
(b)(2)(xvii) ......................
(b)(2)(xviii) .....................
(b)(2)(xix) .......................
(b)(2)(xx) ........................
(b)(2)(xxi) .......................
(b)(2)(xxii) ......................
VerDate Mar<15>2010
21:08 May 03, 2010
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Jkt 220001
(b)(2)(ii) ........................
(b)(2)(vi) .......................
(b)(2)(vii) ......................
(b)(2)(viii) .....................
(b)(2)(ix) .......................
(b)(2)(x) ........................
(b)(2)(xi) .......................
(b)(2)(xii) ......................
(b)(2)(xiii) .....................
(b)(2)(xiv) .....................
(b)(2)(xv) ......................
(b)(2)(xvi) .....................
(b)(2)(xvii) ....................
(b)(2)(xviii)(A) ...............
(b)(2)(xviii)(B) ...............
(b)(2)(xviii)(C) ...............
(b)(2)(xix) .....................
(b)(2)(xx) ......................
(b)(2)(xxi) .....................
(b)(2)(xxii) ....................
(b)(2)(xxiii) ....................
(b)(2)(xxiv) ...................
(b)(2)(xxv) ....................
(b)(2)(xxvi) ...................
PO 00000
Frm 00007
Fmt 4701
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Sfmt 4702
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
(b)(2)(ii) as paragraph (b)(2)(i).
(b)(2)(vi) as paragraph (b)(2)(ii).
(b)(2)(vii) as paragraph (b)(2)(iii).
(b)(2)(viii) as paragraph (b)(2)(iv).
(b)(2)(ix) as paragraph (b)(2)(v).
(b)(2)(x) as paragraph (b)(2)(vi).
(b)(2)(xi) as paragraph (b)(2)(vii).
(b)(2)(xii) as paragraph (b)(2)(viii).
(b)(2)(xiii) as paragraph (b)(2)(ix).
(b)(2)(xiv) as paragraph (b)(2)(x).
(b)(2)(xv) as paragraph (b)(2)(xi).
(b)(2)(xvi) as paragraph (b)(2)(xii).
(b)(2)(xvii) as paragraph (b)(2)(xiii).
(b)(2)(xviii)(A) as paragraph (b)(2)(xiv)(A).
(b)(2)(xviii)(B) as paragraph (b)(2)(xiv)(B).
(b)(2)(xviii)(C) as paragraph (b)(2)(xiv)(C).
(b)(2)(xix) as paragraph (b)(2)(xv).
(b)(2)(xx) as paragraph (b)(2)(xvi).
(b)(2)(xxi) as paragraph (b)(2)(xvii).
(b)(2)(xxii) as paragraph (b)(2)(xviii).
(b)(2)(xxiii) as paragraph (b)(2)(xix).
(b)(2)(xxiv) as paragraph (b)(2)(xx).
(b)(2)(xxv) as paragraph (b)(2)(xxi).
(b)(2)(xxvi) as paragraph (b)(2)(xxii).
E:\FR\FM\04MYP3.SGM
04MYP3
24330
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
TABLE 2—CROSS REFERENCE OF PROPOSED REGULATIONS WITH CURRENT REGULATIONS—Continued
Proposed regulation
Current regulation
Description of proposed redesignations
Paragraph (b)(2)(xxiii) .....................
Paragraph (b)(2)(xxvii) ...................
Redesignate paragraph (b)(2)(xxvii) as paragraph (b)(2)(xxiii).
TABLE 3—CROSS REFERENCE OF CURRENT REGULATIONS WITH PROPOSED REGULATIONS
Current regulation
Proposed regulation
Description of proposed redesignations
ASME B&PV Code, Section XI
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
(b)(2)(ii) ..........................
(b)(2)(vi) .........................
(b)(2)(vii) ........................
(b)(2)(viii) .......................
(b)(2)(ix) .........................
(b)(2)(x) .........................
(b)(2)(xi) .........................
(b)(2)(xii) ........................
(b)(2)(xiii) .......................
(b)(2)(xiv) .......................
(b)(2)(xv) ........................
(b)(2)(xvi) .......................
(b)(2)(xvii) ......................
(b)(2)(xviii)(A) ................
(b)(2)(xviii)(B) ................
(b)(2)(xviii)(C) ................
(b)(2)(xix) .......................
(b)(2)(xx) ........................
(b)(2)(xxi) .......................
(b)(2)(xxii) ......................
(b)(2)(xxiii) .....................
(b)(2)(xxiv) .....................
(b)(2)(xxv) ......................
(b)(2)(xxvi) .....................
(b)(2)(xxvii) ....................
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
Paragraph
The following paragraphs contain the
NRC’s evaluation of the changes to the
Code editions and addenda (including
new Code provisions) and Code Cases
N–722–1 and N–770, where the NRC
proposes to add new, revise existing, or
remove conditions in 10 CFR 50.55a.
Quality Standards, ASME Codes and
Institute of Electrical and Electronics
Engineers (IEEE) Standards, and
Alternatives
10 CFR 50.55a(a)
The NRC proposes to add the
paragraph heading ‘‘Quality standards,
ASME Codes and IEEE standards, and
alternatives’’ to § 50.55a(a). This will be
consistent with paragraph headings
throughout 10 CFR 50.55a.
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Applicant/Licensee-Proposed
Alternatives to the Requirements of 10
CFR 50.55a
10 CFR 50.55a(a)(3)
The current regulations at
§ 50.55a(a)(3) do not clearly convey that
alternatives to the requirements of
§§ 50.55a(c), (d), (e), (f), (g), and (h) must
be submitted to, and authorized by, the
NRC prior to implementing the
alternatives. Licensees have
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
(b)(2)(i) .........................
(b)(2)(ii) ........................
(b)(2)(iii) .......................
(b)(2)(iv) .......................
(b)(2)(v) ........................
(b)(2)(vi) .......................
(b)(2)(vii) ......................
(b)(2)(viii) .....................
(b)(2)(ix) .......................
(b)(2)(x) ........................
(b)(2)(xi) .......................
(b)(2)(xii) ......................
(b)(2)(xiii) .....................
(b)(2)(xiv)(A) ................
(b)(2)(xiv)(B) ................
(b)(2)(xiv)(C) ................
(b)(2)(xv) ......................
(b)(2)(xvi) .....................
(b)(2)(xvii) ....................
(b)(2)(xviii) ....................
(b)(2)(xix) .....................
(b)(2)(xx) ......................
(b)(2)(xxi) .....................
(b)(2)(xxii) ....................
(b)(2)(xxiii) ....................
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
Redesignate
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
paragraph
misinterpreted § 50.55a(a)(3) and
erroneously concluded that it is
permissible to obtain NRC authorization
of an alternative after its
implementation. The NRC proposes to
add a sentence to § 50.55a(a)(3) to
clarify that an alternative must be
submitted to, and authorized by, the
NRC prior to implementing the
alternative.
Standards Approved for Incorporation
by Reference
10 CFR 50.55a(b)
The NRC proposes to add the
paragraph heading ‘‘Standards approved
for incorporation by reference’’ to
§ 50.55a(b). This will be consistent with
paragraph headings throughout 10 CFR
50.55a.
The question has arisen many times
in the past of whether Subsection NE,
‘‘Class MC Components;’’ Subsection
NF, ‘‘Supports;’’ Subsection NG, ‘‘Core
Support Structures;’’ and Appendices of
the ASME B&PV Code, Section III, are
NRC requirements. The NRC is
clarifying in this section how the
regulations in 10 CFR 50.55a apply to
these Section III subsections and
appendices. This discussion sets forth
PO 00000
Frm 00008
Fmt 4701
Sfmt 4702
(b)(2)(ii) as paragraph (b)(2)(i).
(b)(2)(vi) as paragraph (b)(2)(ii).
(b)(2)(vii) as paragraph (b)(2)(iii).
(b)(2)(viii) as paragraph (b)(2)(iv).
(b)(2)(ix) as paragraph (b)(2)(v).
(b)(2)(x) as paragraph (b)(2)(vi).
(b)(2)(xi) as paragraph (b)(2)(vii).
(b)(2)(xii) as paragraph (b)(2)(viii).
(b)(2)(xiii) as paragraph (b)(2)(ix).
(b)(2)(xiv) as paragraph (b)(2)(x).
(b)(2)(xv) as paragraph (b)(2)(xi).
(b)(2)(xvi) as paragraph (b)(2)(xii).
(b)(2)(xvii) as paragraph (b)(2)(xiii).
(b)(2)(xviii)(A) as paragraph (b)(2)(xiv)(A).
(b)(2)(xviii)(B) as paragraph (b)(2)(xiv)(B).
(b)(2)(xviii)(C) as paragraph (b)(2)(xiv)(C).
(b)(2)(xix) as paragraph (b)(2)(xv).
(b)(2)(xx) as paragraph (b)(2)(xvi).
(b)(2)(xxi) as paragraph (b)(2)(xvii).
(b)(2)(xxii) as paragraph (b)(2)(xviii).
(b)(2)(xxiii) as paragraph (b)(2)(xix).
(b)(2)(xxiv) as paragraph (b)(2)(xx).
(b)(2)(xxv) as paragraph (b)(2)(xxi).
(b)(2)(xxvi) as paragraph (b)(2)(xxii).
(b)(2)(xxvii) as paragraph (b)(2)(xxiii).
the NRC’s views regarding the
applicable NRC requirements, clarifies
which portions of Section III are
approved for use by applicants and
licensees, identifies which portions of
Section III are NRC requirements, and
which portions of Section III are not
covered by the regulations in 10 CFR
50.55a. The requirements of Subsection
NH, ‘‘Class 1 Components in Elevated
Temperature Service,’’ of Section III are
already addressed in § 50.55a(b)(1)(vi),
and the bases for these requirements
have been discussed in the final rule (69
FR 58804) issued on October 1, 2004,
that amended 10 CFR 50.55a to
incorporate by reference the 2001
Edition up to and including the 2003
Addenda of the ASME Code, Section III.
First, it should be noted that in 10
CFR 50.55a, the NRC mandates the use
of Section III, Division 1, rules for
ASME Code Class 1, 2, and 3
components in 10 CFR 50.55a(c), (d)
and (e), respectively. Specifically, 10
CFR 50.55a(c), (d) and (e) state that for
applicants constructing a nuclear power
plant, those components which are part
of the reactor coolant pressure boundary
must meet the requirements for Class 1
components in Section III (e.g.,
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
Subsection NB, ‘‘Class 1 Components’’);
components classified as Quality Group
B must meet the requirements for Class
2 components (e.g., Subsection NC,
‘‘Class 2 Components’’); and components
classified as Quality Group C must meet
the requirements for Class 3
components (e.g., Subsection ND, ‘‘Class
3 Components’’). The NRC considers the
rules of Subsection NCA and Section III
mandatory appendices to be mandated
as well, but only as they apply to Class
1, 2, and 3 components because the
language in 10 CFR 50.55a(c), (d) and (e)
also covers general requirements in
Subsection NCA and mandatory
appendices in Section III that are
applicable to Class 1, 2, and 3
components.
In addition, the introductory text of
10 CFR 50.55a(b) states, in part, that the
ASME Code, Section III, is approved for
incorporation by reference by the
Director of the Federal Register pursuant
to 5 U.S.C. 552(a) and 1 CFR part 51.
However, the regulatory language does
not identify specific subsections in
Section III that are incorporated by
reference, and one can only assume that
all of Section III (including all
subsections, appendices and Division 2
and 3 rules) are incorporated by
reference. Although it is clear that
Subsections NB, NC and ND are
regulatory requirements because they
are mandated by 10 CFR 50.55a(c), (d)
and (e) as discussed in this document,
the lack of specific rule language in 10
CFR 50.55a mandating the use of
Subsections NE, NF, and NG have
created confusion about the regulatory
requirements applicable to Subsections
NE, NF, and NG. Subsection NE
provides rules for constructing metal
containment components (Class MC).
Subsection NF provides rules for
constructing supports for Class 1, 2, 3,
and MC components. Subsection NG
provides rules for constructing reactor
core support structures. In this sense,
‘‘constructing’’ is an all-inclusive term
that comprises the design, fabrication,
installation, examination, testing,
inspection and selection of materials for
nuclear power plant components.
The NRC is, therefore, clarifying that
when Subsections NE, NF and NG are
incorporated by reference, but not
mandated, these subsections are not
NRC requirements. Rather, the NRC
considers Subsections NE, NF and NG
to be approved by the NRC for use by
applicants and licensees of nuclear
power plants by virtue of the NRC’s
overall approval of Section III, Division
1 rules without condition. In this
manner, approval of the rules in
Subsections NE, NF and NG is similar
to regulatory guidance provided in NRC
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
regulatory guides in that it provides an
acceptable method for meeting NRC
requirements and, in this particular
case, in 10 CFR Part 50, Appendix A,
General Design Criterion (GDC) 1,
‘‘Quality standards and records.’’
Applicants and licensees may propose
means other than those specified by the
provisions in Subsections NE, NF and
NG for meeting the applicable
regulation. It should be noted that the
NRC reviews an applicant’s proposed
means of meeting the requirements of
GDC 1 as part of its review of an
application for each manufacturing
license, standard design approval,
standard design certification and
combined license under 10 CFR part 52
and for each construction permit and
operating license under 10 CFR part 50
using the guidelines of NRC NUREG–
0800, ‘‘Standard Review Plan [SRP] for
the Review of Safety Analysis Reports
for Nuclear Power Plants—LWR
Edition.’’ During its review of new
reactor designs under 10 CFR part 52,
the NRC is reviewing the criteria and
extent of compliance of standard plant
designs and combined licenses with the
rules of the specific edition and
addenda to Subsections NE, NF and NG
for applicability to these new reactor
designs. The process being used by the
NRC in the review of Subsections NE,
NF, and NG for new reactors as
described in this document is
essentially the same process used by the
NRC for the licensing of all nuclear
power plants since the SRP was first
issued in 1975. Therefore, this
clarification does not establish new
positions or requirements in the
regulatory application of Subsections
NE, NF and NG to the construction of
nuclear power plants.
Because the NRC staff participates on
the ASME Code committees in the
development of and revisions to
Subsections NE, NF and NG, the NRC is
cognizant of the acceptability of the
Code rules applicable to Subsections
NE, NF and NG. NRC use of consensus
technical standards meets the
requirements of Public Law 104–113,
‘‘National Technology Transfer and
Advancement Act of 1995,’’ which
requires Federal agencies to use
technical standards that are developed
by voluntary consensus standards
bodies, instead of government-unique
standards, as a means to carry out policy
objectives or activities determined by
Federal agencies, unless contrary to law
or the use of the standard is impractical.
Consistent with this discussion, the
NRC does not propose to substantially
change the language in the introductory
text to 10 CFR 50.55a(b). The NRC
proposes to modify the regulatory
PO 00000
Frm 00009
Fmt 4701
Sfmt 4702
24331
language in the introductory text of 10
CFR 50.55a(b) to clarify that nonmandatory appendices are excluded
from Section III rules that are
incorporated by reference because the
NRC does not review the acceptability
of non-mandatory Section III
appendices. Similarly, the NRC
proposes to clarify in the introductory
text of 10 CFR 50.55a(b) that only
Division 1 rules of Section III and
Section XI are incorporated by reference
(i.e., Divisions 2 and 3 rules are not
incorporated by reference and are not
approved by the NRC regulations in 10
CFR 50.55a). The NRC is also proposing
to incorporate by reference ASME Code
Case N–722–1, ‘‘Additional
Examinations for PWR Pressure
Retaining Welds in Class 1 Components
Fabricated With Alloy 600/82/182
Materials Section XI, Division 1,’’ and
Code Case N–770, ‘‘Alternative
Examination Requirements and
Acceptance Standards for Class 1 PWR
[Pressurized-Water Reactor] Piping and
Vessel Nozzle Butt Welds Fabricated
with UNS N06082 or UNS W86182
Weld Filler Material with or without
Application of Listed Mitigation
Activities.’’
ASME B&PV Code, Section III
The NRC proposes to:
• Revise the current regulations in
§ 50.55a(b)(1), (b)(1)(ii), and (b)(1)(iii) to
detail the specific ASME B&PV Code,
Section III Subsections which are
referenced in the ensuing paragraphs.
• Revise the current requirements in
these paragraphs to include the latest
editions and addenda incorporated into
Section III of the ASME B&PV Code
with respect to the regulations regarding
seismic design.
• Clarify the current wording of the
introductory text of § 50.55a(b)(1).
• Modify the current conditions in
§ 50.55a(b)(1)(ii) on the use of stress
indices used for welds in piping design
under Subarticles NB–3600, NC–3600,
and ND–3600.
• Add three new requirements at
§ 50.55a(b)(1)(iii)(A), (b)(1)(iii)(B), and
(b)(1)(iii)(C) to impose conditions on the
use of Subarticles NB–3200, NB–3600,
NC–3600 and ND–3600 identified in
§ 50.55a(b)(1)(iii).
Introductory Text to 10 CFR 50.55a(b)(1)
The proposed amendment to the
introductory text of § 50.55a(b)(1) would
revise the language to clarify that
references to Section III refer to Section
III of the ASME Boiler and Pressure
Vessel Code.
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
24332
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
10 CFR 50.55a(b)(1)(ii) and (b)(1)(iii)
Weld-Leg Dimensions and Seismic
Design of Piping
The current requirements regarding
piping seismic rules in Section III the
ASME B&PV Code were first introduced
in the 1994 Addenda to the ASME
B&PV Code. These rules were
subsequently modified in the 2001
Edition and 2002 Addenda to the ASME
B&PV Code. The current regulations in
§ 50.55a(b)(1)(ii) outline the conditions
on the use of stress indices used for
welds in piping design under
Subarticles NB–3600, NC–3600, and
ND–3600. The current regulations in
§ 50.55a(b)(1)(iii) only allow the use of
ASME B&PV Code, Section III, 1993
Addenda and earlier editions with
respect to Subarticles NB–3200, NB–
3600, NC–3600, and ND–3600.
The current version of the ASME
B&PV Code does not adequately address
the seismic design requirements
specified in Subparagraphs NB–
3683.2(c), NB–3683.4(c)(1) and (c)(2),
and Paragraph NB–3656, Figures NB–
3222–1, NC–3673.2(b)–1, and ND–
3673.2(b)–1 and Table 3681(a)–1 of the
ASME B&PV Code. The proposed
amendment would modify
§ 50.55a(b)(1)(ii) to address the NRC’s
concern about the undersized weld-leg
dimension of less than 1.09t that makes
the weld weaker than the pipe.
Additional requirements regarding the
stress indices identified in the proposed
addition to the regulations (i.e.
§ 50.55a(b)(1)(iii)(A)) are warranted
based on industry testing which
supports the NRC’s position.
Additionally, the proposed requirement
in § 50.55a(b)(1)(iii)(B) would resolve an
issue identified by the NRC staff
regarding the inclusion of reversing
dynamic loads when calculating the
primary bending stresses for Level B
service limits. The proposed condition
in § 50.55a(b)(1)(iii)(C) is part of the
ASME B&PV Code requirements for
applying the seismic design rules in
Subarticles NB–3600, NC–3600, and
ND–3600 in the 2006 Addenda through
the 2008 Addenda.
The current regulations in
§ 50.55a(b)(1) and (b)(1)(iii) reference
the current seismic design requirements
of Section III of the ASME B&PV Code.
The proposed modification would allow
the use of the latest edition and addenda
of Section III of the ASME B&PV Code
with the three proposed additional
requirements at § 50.55a(b)(1)(iii)(A),
(b)(1)(iii)(B), and (b)(1)(iii)(C) which
would provide three conditions on the
use of the latest ASME B&PV Code
edition and addenda. The current
requirements in § 50.55a(b)(1)(ii) limit
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
the use of certain stress indices used for
welds in the piping design portions of
Section III of the ASME B&PV Code.
The proposed modification would also
revise the current conditions on the use
of the stress indices outlined in
§ 50.55a(b)(1)(ii).
The proposed condition identified in
§ 50.55a(b)(1)(ii) would address the NRC
concerns with the undersized welds (Cx
= 0.75 tn), which are not acceptable
because the current ASME Code design
rules would result in a circumferential,
fillet-welded or socket-welded joint
where the weld size is smaller than the
adjoining pipe wall thickness. An
editorial addition would also be
included in the proposed condition and
would reflect the addition of a condition
on the use of paragraph NB–
3683.4(c)(2). The use of paragraph NB–
3683.4(c)(1) is currently not allowed
and would continue to be prohibited in
the proposed rulemaking. The addition
of the condition on the use of paragraph
NB–3683.4(c)(2) is purely editorial in
nature since, by imposing a condition
on the use of NB–3683.4(c)(1), the
regulations would inherently impose a
condition on the use of NB–3683.4(c)(2)
given their use within Section III of the
ASME B&PV Code. Therefore, this
condition would not be new from a
technical standpoint. Also, an editorial
correction would be made regarding
Footnote 11, which should be the
Footnote 13 for the 2004 Edition
through the 2008 Addenda in Figure
NC–3673.2(b)–1 and Figure ND–
3673.2(b)–1.
The proposed addition identified as
§ 50.55a(b)(1)(iii)(A) would address the
NRC’s position regarding the B2’ indices
in paragraph NB–3656 of Section III of
the ASME B&PV Code. The NRC
proposes this condition to capture the
dynamic strain aging effects that were
reflected in the testing performed by
Battelle Columbus Laboratories which
concluded that ferritic steels tend to
have lower margins and a decrease in
toughness at higher temperatures due to
dynamic strain aging. (See NUREG/CR–
6226, ‘‘Effect of Dynamic Strain Aging
on the Strength and Toughness of
Nuclear Ferritic Piping at LWR
Temperatures’’ for the Battelle testing
results). Therefore, this additional
requirement would provide the means
necessary to prevent significant
reductions in the margins of ferritic
steel components (elbows and tees) at
high temperatures, thus providing better
assurance of the materials’ structural
integrity.
The proposed addition identified as
§ 50.55a(b)(1)(iii)(B) would address the
NRC’s position regarding Note (1) of
Figure NB–3222–1 of Section III of the
PO 00000
Frm 00010
Fmt 4701
Sfmt 4702
ASME B&PV Code. The NRC proposes
this condition based on the premise that
while the inclusion of reversing
dynamic loads in the calculation of
primary bending stresses for Level B
service limits may not be warranted
when the Operating Basis Earthquake is
not included in the design basis for the
facility, at other times these loads must
be considered. Such is the case when a
licensee’s Operating Basis Earthquake
level is more than one-third the value of
the Safe Shutdown Earthquake.
However, the current wording of Note
(1) in Figure NB–3222–1 of Section III
of the ASME B&PV Code does not
account for this situation. Therefore, the
NRC proposes to include this condition
on the use of the latest addenda of
Section III of the ASME B&PV Code.
The proposed addition identified as
§ 50.55a(b)(1)(iii)(C) would address the
NRC’s position regarding the limitation
of Do/t ratio of ASME Class 1, 2 and 3
piping when applying Subarticles NB–
3600, NC–3600 and ND–3600 in the
2006 Addenda through the 2008
Addenda of Section III of the ASME
B&PV Code. In the 1994 Addenda, the
Do/t ratio was identified by ASME Code
Committee to be 50 or less for applying
the seismic rules in Subarticles NB–
3600, NC–3600 and ND–3600. This
upper limit for Do/t was revised to be 40
in the 2002 Addenda through the 2008
Addenda based on EPRI testing
associated with reversing dynamic
seismic loading. However, the 2007
Edition allows Do/t to be greater than 50
in Note 1 to Table NB 3681(a)–1 and
Note 3 to Figures NC/ND–3673.2(b)–1.
NUREG–1367 limits Do/t to no more
than 50 for functional capability
considerations. To ensure consistency
with ASME B&PV Code requirements
found in paragraphs NB–3656, NC–
3655, and ND–3655, Do/t should be
limited to no more than 40.
Furthermore, the use of Do/t larger than
40 would be beyond the piping
configuration included in the EPRI
testing, and thus is not justified for
design considerations. Therefore, the
NRC concludes that the applicable Do/
t for the seismic design of piping as
limited by the ASME B&PV Code in
Subarticles NB–3600, NC–3600, and
ND–3600 in the 2006 Addenda through
the 2008 Addenda must not be greater
than 40 as addressed in
§ 50.55a(b)(1)(iii)(C).
10 CFR 50.55a(b)(1)(iv) Quality
Assurance
The proposed amendment would
revise § 50.55a(b)(1)(iv) to be consistent
with a revised quality assurance
provision in the 2006 Addenda of the
ASME B&PV Code, Section III,
E:\FR\FM\04MYP3.SGM
04MYP3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Subsection NCA. The proposed
amendment would allow the use of
1994 Edition of NQA–1, ‘‘Quality
Assurance Requirements for Nuclear
Facility Applications,’’ when using the
2006 Addenda of Section III of the
ASME B&PV Code and later editions
and addenda. The reference to ASME
NQA–1 in Article 4000 of the ASME
B&PV Code, Section III was updated to
a later edition of NQA–1 in the 2006
Addenda. NCA–4110(b) was revised to
require that the N–Type Certificate
Holders comply with the Basic
Requirements and Supplements of the
ASME NQA–1–1994 Edition. Previous
editions/addenda of the ASME B&PV
Code, Section III referenced earlier
editions and addenda of ASME NQA–1.
There are no significant differences
between of NQA–1–1994 Edition and
the editions and addenda of NQA–1
currently referenced in the regulation.
The NRC has reviewed and found the
changes to Subsection NCA that
reference the 1994 Edition of NQA–1 to
be acceptable.
10 CFR 50.55a(b)(1)(vii) Capacity
Certification and Demonstration of
Function of Incompressible-Fluid
Pressure-Relief Valves (New)
The proposed addition identified as
§ 50.55a(b)(1)(vii) would modify
requirements in Subsection NB of the
ASME B&PV Code, Section III, for
certifying the capacity of
incompressible-fluid, pressure-relief
valves when the testing facility has less
than the full range of pressure capability
necessary for achieving valve setpressure conditions during the testing.
In the 2006 Addenda, new requirements
were added to the ASME B&PV Code,
Section III, that have a parallel structure
in paragraphs NB–7742, NC–7742, and
ND–7742 for Class 1, 2, and 3
incompressible-fluid, pressure-relief
valves, respectively. These new
paragraphs address new valve designs
having a range of possible sizes and setpressure conditions. The method
described in these paragraphs for
performing the tests and evaluating data
involves performing tests at less than
the highest value of the set-pressure
range, and establishing an
incompressible fluid flow coefficient of
discharge that then allows extrapolation
of capacities to higher pressures.
These paragraphs are new, and did
not exist in prior editions or addenda of
the ASME B&PV Code, Section III.
These new paragraphs address
circumstances in which a certified test
facility lacks the fluid-pressure
capability at the necessary flow rate for
testing a new, incompressible-fluid,
pressure-relief valve design. The NRC
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
has identified no issues with performing
the tests at less than the highest value
of the set-pressure range for
incompressible-fluid, pressure-relief
valves, and finds these new
requirements for Class 2 and 3
components acceptable as described in
paragraphs NC–7742 and ND–7742.
However, the NRC has identified
missing words from paragraph NB–7742
for Class 1 components. The parallel
structure of the counterpart paragraphs
(NC–7742 and ND–7742) reveals that
the words ‘‘for the design and the
maximum set pressure’’ are missing
from subparagraph NB–7742(a)(2).
Without these words, the paragraph is
confusing, illogical, and could lead to a
non-conservative interpretation of the
required test pressures for new Class 1
incompressible-fluid, pressure-relief
valve designs. Because the new
paragraph NB–7742 does not contain
the above-described words, the NRC
finds that the paragraph is not
acceptable for use. New Class 1
incompressible-fluid, pressure-relief
valve designs must be tested at the
highest values of set-pressure ranges as
required by prior editions and addenda
of the ASME B&PV Code, Section III.
ASME B&PV Code, Section XI
The current regulations in
§ 50.55a(b)(2) incorporate by reference
ASME B&PV Code, Section XI, 1970
Edition through the 1976 Winter
Addenda; and the 1977 Edition
(Division 1) through the 2004 Addenda
(Division 1), subject to the conditions
identified in current § 50.55a(b)(2)(i)
through (b)(2)(xxvii). The proposed
amendment would revise the
introductory text to § 50.55a(b)(2) to
incorporate by reference the 2005
Addenda (Division 1) through the 2008
Addenda (Division 1) of the ASME
B&PV Code, Section XI, clarify the
wording, and remove or revise some of
the conditions as explained in this
document.
Introductory Text of 10 CFR 50.55a(b)(2)
The proposed amendment to the
introductory text of § 50.55a(b)(2) would
revise the language to clarify that
references to Section XI refer to Section
XI of the ASME Boiler and Pressure
Vessel Code.
10 CFR 50.55a(b)(2)(i) Limitations on
Specific Editions and Addenda
(Current)
The NRC proposes to remove
§ 50.55a(b)(2)(i) from the current
regulations. This paragraph currently
specifies which addenda may be used
when applying the 1974 and 1977
Editions of Section XI of the ASME
PO 00000
Frm 00011
Fmt 4701
Sfmt 4702
24333
B&PV Code. Section 50.55a(g)(4)(ii)
requires that licensees’ successive 120month inspection intervals comply with
the requirements of the latest edition
and addenda of the code incorporated
by reference in § 50.55a(b)(2).
Subsequently, licensees are no longer
using these older editions (1974 and
1977 Editions) and addenda of the
ASME B&PV Code, and therefore the
NRC proposes to remove this paragraph.
This paragraph will be replaced by
the current § 50.55a(b)(2)(ii) which
describes a method for determining the
extent of examination of Code Class 1
piping welds for facilities where the
application for a construction permit
was docketed prior to July 1, 1978.
10 CFR 50.55a(b)(2)(iii) Steam Generator
Tubing (Current)
The NRC proposes to remove
§ 50.55a(b)(2)(iii) from the current
regulations. The current regulations in
§ 50.55a(b)(2)(iii) state that if the
technical specifications of a nuclear
power plant include surveillance
requirements for steam generators
different than those in Section XI,
Article IWB–2000, the ISI program of
steam generator tubing is governed by
the requirements in the technical
specifications. The 1989 Edition
through the 2008 Addenda of Section XI
IWB–2413, ‘‘Inspection Program for
Steam Generator Tubing,’’ state that
‘‘The examinations shall be governed by
the plant Technical Specification.’’
Since the condition in § 50.55a(b)(2)(iii)
is redundant to the 1989 Edition
through the 2008 Addenda of Section
XI, the NRC proposes to remove this
condition.
This paragraph will be replaced by
the current § 50.55a(b)(2)(vii) which
describes Section XI references to OM
Part 4, OM Part 6 and OM Part 10 of the
ASME OM Code.
10 CFR 50.55a(b)(2)(iv) PressureRetaining Welds in ASME Code Class 2
Piping (Current)
The NRC proposes to remove
§ 50.55a(b)(2)(iv) from the current
regulations. This paragraph states how
to select appropriate Code Class 2 pipe
welds in residual heat removal systems,
emergency core cooling systems, and
containment heat removal systems
when applying editions and addenda up
to the 1983 Edition through the Summer
1983 Addenda of Section XI of the
ASME B&PV Code. Section
50.55a(g)(4)(ii) requires that licensee’s
successive 120-month inspection
intervals comply with the requirements
of the latest edition and addenda of the
code incorporated by reference in
§ 50.55a(b)(2). Subsequently, licensees
E:\FR\FM\04MYP3.SGM
04MYP3
24334
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
are no longer using these older editions
and addenda of the code (editions and
addenda up to the 1983 Edition through
the Summer 1983 Addenda of Section
XI), and therefore, the NRC proposes to
remove the requirements of current
§ 50.55a(b)(2)(iv).
This paragraph will be replaced by
the current § 50.55a(b)(2)(viii) which
describes examinations of concrete
containments.
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
10 CFR 50.55a(b)(2)(v) Evaluation
Procedure and Acceptance Criteria for
Austenitic Piping (Current)
The NRC proposes to remove
§ 50.55a(b)(2)(v) from the current
regulations. This paragraph deals with
evaluation procedures and acceptance
criteria for austenitic piping when
applying the Winter 1983 Addenda and
the Winter 1984 Addenda of Section XI.
Section 50.55a(g)(4)(ii) requires that
licensees’ successive 120-month
inspection intervals comply with the
requirements of the latest edition and
addenda of the code incorporated by
reference in § 50.55a(b)(2).
Subsequently, licensees are no longer
using these older editions and addenda
of the code (editions and addenda up to
the 1983 Edition through the Summer
1983 Addenda of Section XI), and
therefore, the NRC proposes to remove
the requirements of current
§ 50.55a(b)(2)(iv). This paragraph will be
replaced by the current § 50.55a(b)(2)(ix)
which describes examination of metal
containments and the liners of concrete
containments.
10 CFR 50.55a(b)(2)(vi) Effective Edition
and Addenda of Subsection IWE and
Subsection IWL, Section XI (Current);
10 CFR 50.55a(b)(2)(ii) (Redesignated)
The NRC proposes to redesignate
§ 50.55a(b)(2)(vi) in the current rule to
§ 50.55a(b)(2)(ii) in the proposed rule.
This paragraph stipulates the editions
and addenda of Subsection IWE and
Subsection IWL of Section XI of the
ASME B&PV Code which are approved
for use when licensees are
implementing the initial 120-month
inspection interval for containment
inservice inspection requirements found
in Section XI of the Code. The current
paragraph also indicates that the use of
these applicable editions and addenda
is subject to the conditions found in
§ 50.55a(b)(2)(viii) and (b)(2)(ix) for
Subsection IWL and Subsection IWE,
respectively. The proposed rule would
redesignate § 50.55a(b)(2)(viii) and
(b)(2)(ix) as § 50.55a(b)(2)(iv) and
(b)(2)(v), respectively, and conforming
changes would be made to the
references contained in redesignated
§ 50.55a(b)(2)(ii). Additionally, the
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
proposed rule would change the words
‘‘modified and supplemented’’ to
‘‘conditioned’’ for clarification purposes.
10 CFR 50.55a(b)(2)(viii) Examination of
Concrete Containments (Current); 10
CFR 50.55a(b)(2)(iv) (Redesignated)
The NRC proposes to redesignate
§ 50.55a(b)(2)(viii) in the current rule to
§ 50.55a(b)(2)(iv) in the proposed rule.
This paragraph stipulates the conditions
that apply to the inservice examination
of concrete containments using
Subsection IWL of various editions and
addenda of the ASME B&PV Code,
Section XI, incorporated by reference in
§ 50.55a(b)(2). The current regulations,
in part, require that licensees applying
Subsection IWL, 2001 Edition through
the 2004 Edition shall apply the
conditions in § 50.55a(b)(2)(viii)(E)
through (b)(2)(viii)(G). The NRC
proposes to remove the conditions in
redesignated § 50.55a(b)(2)(iv)(F) and
(b)(2)(iv)(G) of the proposed rule when
applying Subsection IWL of the 2007
Edition with 2008 addenda of the ASME
B&PV Code, Section XI because the
intent of these conditions has been
incorporated into the 2007 Edition with
the 2008 addenda of the ASME B&PV
Code, as explained in this document.
Accordingly, the proposed rule would
require that licensees applying
Subsection IWL, 2007 Edition with the
2008 Addenda shall apply only the
condition in redesignated
§ 50.55a(b)(2)(iv)(E). Further, in the
proposed rule, the conditions in
redesignated § 50.55a(b)(2)(iv)(E)
through (b)(2)(iv)(G) remain applicable
to licensees applying Subsection IWL,
2004 Edition through the 2006
Addenda.
The condition in the redesignated
§ 50.55a(b)(2)(iv)(F) relates to
qualification of personnel that examine
containment concrete surfaces and
tendon hardware, wires, or strands. This
condition in the current regulations
states that personnel that examine
containment concrete surfaces and
tendon hardware, wires, or strands must
meet the qualification provisions in
IWA–2300, and that the ‘‘ownerdefined’’ personnel qualification
provisions in IWL–2310(d) are not
approved for use. IWA–2300 stipulates
qualification provisions for personnel
performing nondestructive examination,
including VT–1, VT–2, and VT–3 visual
examinations. Paragraph IWA–2312(c)
requires training, qualification, and
certification of visual examination
personnel to comply with the
requirements of Appendix VI of the
Code, which makes reference to ANSI/
ASNT CP–189, and allows for limited
certification (for personnel who are
PO 00000
Frm 00012
Fmt 4701
Sfmt 4702
restricted to performing examinations of
limited or specific scope, i.e., limited
operations or limited techniques) per
IWA–2350.
In Subsection IWL of the 2007
Edition, the ASME revised paragraph
IWL–2100 to state, in part, that except
as noted in IWL–2320, the requirements
of IWA–2300 do not apply. Also, the
2007 Edition deleted subparagraphs
IWL–2310(d) and IWL–2310(e), which
allowed certain requirements (i.e.,
requirements for personnel qualification
and requirements for visual examination
of concrete and tendon anchorage
hardware, wires, or strands) to be
owner-defined. Further, the 2007
Edition with 2008 Addenda added a
new paragraph IWL–2320 ‘‘Personnel
Qualifications’’ and re-designated the
former IWL–2320 ‘‘Responsible
Engineer’’ as IWL–2330 ‘‘Responsible
Engineer.’’
The new paragraph IWL–2320
stipulates specific plant experience,
training, written and practical
examination and frequency of
administration to demonstrate training
proficiency, and vision test
requirements for qualification of
personnel approved by the Responsible
Engineer for performing general or
detailed visual examinations of
structural concrete, reinforcing steel and
post-tensioning system components
(i.e., wires, strands, anchorage
hardware, corrosion protection medium
and free water) of Class CC
containments. The provision requires
documentation of qualification
requirements in the Employer’s written
practice. The Responsible Engineer is
responsible for approval, instruction
and training of personnel performing
general and detailed visual
examinations. The new provision also
provided the requisite detailed
requirements for the instruction
material to be used to qualify personnel
performing IWL inspections.
Specifically, the addition included
requirements for preservice and
inservice inspections for concrete
(references American Concrete Institute
201.1R), reinforcing steel, and posttensioning items such as wires, strands,
anchorage hardware, corrosion
protection medium, and free water.
Thus, the qualification requirements
adequately include the areas and extent
of required plant experience,
instructional topics for classroom
training in IWL requirements and plantspecific IWL visual examination
procedures, and require the vision test
requirements of IWA–2321. The new
paragraph IWL–2320, ‘‘Personnel
Qualifications,’’ details specific
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
guidance for personnel qualification for
containment concrete and reinforcing
steel and post-tensioning system visual
inspections that provide an acceptable
level of quality and safety similar to the
requirements in IWA–2300 and
therefore, addressed the intent of the
conditions in § 50.55a(b)(2)(viii)(F) of
the current regulations. Therefore, the
condition in redesignated
§ 50.55a(b)(2)(iv)(F) is not required to be
applied for licensees using Subsection
IWL, 2007 Edition with the 2008
Addenda. It is noted that the NRC’s
acceptance of the new code provision
IWL–2320, ‘‘Personnel Qualifications,’’
is based on paragraph IWL–2320 of the
2007 Edition as supplemented by the
addition by errata in the 2008 addenda.
The condition in redesignated
§ 50.55a(b)(2)(iv)(G) of the proposed rule
requires that corrosion protection
material be restored following concrete
containment post-tensioning system
repair and replacement activities in
accordance with the quality assurance
program requirements specified in
IWA–1400.’’ In the 2007 Edition of
Subsection IWL, the following revisions
were made related to corrosion
protection medium for post-tensioning
systems:
1. The revised paragraph IWL 4110
added footnote 1 which states that the
corrosion protection medium is exempt
from the requirements of IWL–4000.
However, corrosion protection medium
must be restored in accordance with
IWL–2526 following concrete
containment post-tensioning system
repair/replacement activities.
2. The revised Line Item L2.40
‘‘Corrosion Protection Medium’’ of Table
IWL–2500–1 added reference to
paragraph IWL–2526 in the columns for
Test or Examination Requirement, Test
or Examination Method, and Extent of
Examination.
3. In the revised paragraph IWL–2526,
subparagraph (b) requires that following
the completion of tests and
examinations required by Examination
Category L–B, Items L2.10, L.2.20, and
L2.30, the corrosion protection medium
must be replaced to ensure sufficient
coverage of anchorage hardware, wires,
and strands. The total amount replaced
in each tendon sheath must be recorded
and differences between amount
removed and amount replaced must be
documented.
4. In the revised paragraph IWL–2526,
subparagraph (d) requires that the
Responsible Engineer specify the
method for corrosion protection
medium.
With the understanding that the
Responsible Engineer (who per IWL–
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
2320 is a Registered Professional
Engineer) will ensure that the corrosion
protection medium is restored in
accordance with the applicable Quality
Assurance Program, the revised
paragraphs IWL–4110(b)(3) [with
footnote 1] and IWL–2526, and revised
line item L2.40 in Table IWL–2500–1 of
Subsection IWL, 2007 Edition through
the 2008 Addenda adequately
incorporated the intent of the condition
in § 50.55a(b)(2)(viii)(G) of the current
regulations and is acceptable to the
NRC. Therefore, the condition in
redesignated § 50.55a(b)(2)(iv)(G) is not
required to be applied for licensees
using Subsection IWL, 2007 Edition
through the 2008 Addenda.
10 CFR 50.55a(b)(2)(ix) Examination of
Metal Containments and the Liners of
Concrete Containments (Current); 10
CFR 50.55a(b)(2)(v) (Redesignated)
The NRC proposes to redesignate
§ 50.55a(b)(2)(ix) as § 50.55a(b)(2)(v).
This paragraph stipulates the conditions
that apply to the inservice examination
of metal containments and liners of
concrete containments using Subsection
IWE of various editions and addenda of
the ASME B&PV Code, Section XI,
incorporated by reference in
§ 50.55a(b)(2). The NRC proposes to
remove the conditions in newly
redesignated § 50.55a(b)(2)(v)(F),
(b)(2)(v)(G), (b)(2)(v)(H) and (b)(2)(v)(I)
when applying the 2004 Edition with
2006 Addenda through the 2007 Edition
with 2008 Addenda of the ASME Code,
Section XI because these conditions
have now been incorporated into the
Code. The NRC further proposes to
remove the condition in redesignated
§ 50.55a(b)(2)(v)(I) when applying the
2004 Edition, up to and including, the
2005 Addenda. The NRC also proposes
to add a new condition as
§ 50.55a(b)(2)(v)(J) on the use of Article
IWE–5000 of Subsection IWE when
applying the 2007 Edition, up to and
including the 2008 Addenda of the
ASME Code, Section XI. These
proposed changes are further explained
in this document.
The current regulations, in part,
require that licensees applying
Subsection IWE, 1998 Edition through
the 2004 Edition apply the conditions in
§ 50.55a(b)(2)(ix)(A), (b)(2)(ix)(B), and
(b)(2)(ix)(F) through (b)(2)(ix)(I). In the
proposed rule, the conditions in newly
redesignated § 50.55a(b)(2)(v)(F) through
(b)(2)(v)(I) would remain applicable to
licensees applying Subsection IWL,
1998 Edition through the 2001 Edition
with the 2003 Addenda. As a minor
correction to the current regulations, the
proposed rule would require that
licensees applying Subsection IWE of
PO 00000
Frm 00013
Fmt 4701
Sfmt 4702
24335
the 2004 Edition through the 2005
Addenda of the ASME B&PV Code,
satisfy the requirements of newly
redesignated § 50.55a(b)(2)(v)(A),
(b)(2)(v)(B), and (b)(2)(v)(F) through
(b)(2)(v)(H). This correction is being
made since paragraph IWE–3511.3 of
the 2004 Edition of the ASME B&PV
Code incorporated the condition in
newly redesignated § 50.55a(b)(2)(v)(I),
which requires that 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. Further, the proposed rule
would require that licensees applying
Subsection IWE, 2004 Edition with the
2006 Addenda through the latest edition
and addenda incorporated by reference
in § 50.55a(b)(2) satisfy the requirements
of newly redesignated
§ 50.55a(b)(2)(v)(A) and (b)(2)(v)(B).
This is because the intent of the
conditions in newly redesignated
§ 50.55a(b)(2)(v)(F) through (b)(2)(v)(H)
were incorporated into Subsection IWE,
2004 Edition with the 2006 addenda,
and the condition in newly redesignated
§ 50.55a(b)(2)(v)(I) was incorporated
into Subsection IWE, 2004 Edition, as
explained in this document.
The condition in redesignated
§ 50.55a(b)(2)(ix)(F) of the proposed rule
requires that VT–1 and VT–3
examinations 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, and the ‘‘ownerdefined’’ personnel qualification
provisions in IWE–2330(a) for personnel
that conduct VT–1 and VT–3
examinations are not approved for use.
This condition defines the code
provision (IWA–2200) and personnel
qualification (IWA–2300) requirements
for personnel performing visual
examinations by the VT–1 or VT–3
method, as specified in the conditions
in redesignated § 50.55a(b)(2)(v)(G) and
(b)(2)(v)(H) of the proposed rule. The
condition does not allow use of the
‘‘owner-defined’’ personnel qualification
provisions in IWA–2330(a) for
personnel that conduct VT–1 and VT–
3 examinations. The revised code
provision in IWE–2330(a) of the 2006
Addenda requires that personnel
performing VT–1 and VT–3 visual
examinations shall meet the
qualification requirements of IWA–
2300. The revised code provision in
IWL–2100 of the 2006 Addenda states
that IWA–2000 applies with the
exception that IWA–2210 and IWA–
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
24336
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
2300 do not apply to general visual
examination only (except as required by
2330(b) for vision test requirements).
Therefore, the code provisions in IWA–
2200 and IWA–2300 will apply to VT–
1 and VT–3 examinations. Thus, the
revised code provisions in IWE–2330(a)
and IWE–2100 of the 2006 through 2008
Addenda fully incorporates the
condition in newly redesignated
§ 50.55a(b)(2)(v)(F). Therefore, the
condition in newly redesignated
§ 50.55a(b)(2)(v)(F) is not required to be
applied for licensees using Subsection
IWE, 2004 Edition with the 2006
Addenda and the 2007 Edition through
the 2008 Addenda.
The condition in redesignated
§ 50.55a(b)(2)(v)(G) of the proposed rule
requires that the VT–3 examination
method be used to conduct the
examinations in Items E1.12 and E1.20
of Table IWE 2500–1, and the VT–1
examination method 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. This condition,
applicable in the current regulations to
the 1998 Edition through the 2004
Edition, requires that the VT–3 and VT–
1 examination methods be used in lieu
of the ‘‘General Visual’’ and ‘‘Detailed
Visual’’ methods, respectively, as
specified in Table IWE–2500–1 for the
Item Numbers listed in the condition,
and that the owner-defined visual
examination provisions in IWE–2310(a)
cannot be used for VT–1 and VT–3
examinations. In the 2006 Addenda
through the 2008 Addenda, Table IWE–
2500–1 was revised to change the
examination method for Item Numbers
E1.12 and E1.20 to the VT–3 method
and for Item E4.11 to the VT–1 method.
Also, a new Examination Category E–G
was added for pressure-retaining bolting
with Item No. E8.10 which requires 100
percent of each bolted connection to be
examined, using the VT–1 method and
the acceptance standard in the newly
added paragraph IWE–3530, once
during each Inspection Interval with the
connection assembled and bolting inplace, provided the connection is not
disassembled during the interval, or in
the disassembled configuration if the
connection is disassembled for any
reason during the interval. This VT–1
examination, which is more stringent
than the VT–3 method specified in the
condition, is in addition to the general
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
visual examination of 100 percent of the
pressure-retaining bolted connections
during each inspection period required
to be performed under Item No. E1.11 of
Table IWE–2500–1. Further, the revised
IWL–2310 does not have any ownerdefined provisions for performing visual
examinations including VT–1 and VT–
3 examinations. Thus, the provisions in
the revised Table IWE–2500–1 and the
revised paragraph IWE–2310 addressed
the intent of the condition in newly
redesignated § 50.55a(b)(2)(v)(G).
Therefore, the condition in newly
redesignated § 50.55a(b)(2)(v)(G) is not
required to be applied for licensees
using Subsection IWE, 2004 Edition
with the 2006 Addenda and the 2007
Edition through the 2008 Addenda.
The condition in redesignated
§ 50.55a(b)(2)(v)(H) of the proposed rule
requires that containment bolted
connections that are disassembled
during the scheduled performance of
the examinations in Item E1.11 of Table
IWE–2500–1 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, and 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. The condition in newly
redesignated § 50.55a(b)(2)(v)(H) is
similar to the condition for bolted
connections in newly redesignated
§ 50.55a(b)(2)(v)(G), but applies only to
examination of pressure-retaining bolted
connections that are disassembled. The
condition requires flaws or degradation
identified during the VT–3 examination
to be examined using the VT–1 method.
The NRC notes that the VT–1 (and not
VT–3) examination method is the
method specified in the new Item E8.10
for pressure-retaining bolted
connections in the revised Table IWE–
2500–1 in the 2006 Addenda through
2008 Addenda of the ASME B&PV Code.
Further, the acceptance standard for the
VT–1 examination of pressure-retaining
bolting in the new paragraph IWE–3530
requires that the relevant conditions, as
defined in IWA–9000, and listed in
IWB–3517.1, shall be corrected or
evaluated to meet the requirements of
IWE–3122, prior to continued service.
PO 00000
Frm 00014
Fmt 4701
Sfmt 4702
Therefore, the new provision for
pressure-retaining bolting in Table IWE
2500–1, as discussed in this document,
and the new acceptance standard
specified in IWE–3530, as discussed in
this document, fully addressed the
intent of the condition in newly
redesignated § 50.55a(b)(2)(v)(H).
Therefore, the condition in newly
redesignated § 50.55a(b)(2)(v)(H) is not
required to be applied for licensees
using Subsection IWE, 2004 Edition
with the 2006 Addenda and the 2007
Edition through the 2008 Addenda.
The condition in redesignated
§ 50.55a(b)(2)(ix)(I) of the proposed rule
requires that the ultrasonic examination
acceptance standard specified in IWE–
3511.3 for Class MC pressure-retaining
components also be applied to metallic
liners of Class CC pressure-retaining
components. This condition requires
that the acceptance standard in IWE–
3511.3 also apply to the metallic shell
and penetration liners of Class CC
pressure-retaining components in the redesignated paragraph IWE–3522,
‘‘Ultrasonic Examination,’’ in the 2004
Edition through the 2007 Edition and
2008 Addenda. Therefore, the condition
in newly redesignated
§ 50.55a(b)(2)(v)(I) is not required to be
applied for licensees using Subsection
IWE, 2004 Edition through the 2007
Edition and the 2008 Addenda.
Although the revised paragraph IWE–
2310 (IWE–2313 to be specific) and new
subparagraphs IWE–2420(c) and IWE–
2500(d), in the 2006 Addenda through
the 2008 Addenda, address the
condition in newly redesignated
§ 50.55a(b)(2)(v)(A) of the proposed rule
with regard to requiring evaluation of
acceptability of inaccessible areas when
conditions exists in accessible areas that
could indicate the presence or result in
degradation to such inaccessible areas,
the NRC has retained the condition in
the proposed rule, since the information
specified in the condition to be
provided in the ISI Summary Report are
not explicitly addressed in the ASME
B&PV Code.
10 CFR 50.55a(b)(2)(v)(J) (New)
The NRC proposes to add a new
§ 50.55a(b)(2)(v)(J) to place a condition
on the use of Article IWE–5000, ‘‘System
Pressure Tests,’’ of Subsection IWE
when applying the 2007 Edition up to
and including the 2008 Addenda of the
ASME Code, Section XI. The revised
Article IWE–5000 does not make a
distinction between ‘‘major’’ and ‘‘minor’’
modification (or repair/replacement)
with regard to the type of pneumatic
leakage tests specified following repair/
replacement activities. It requires a
pneumatic leakage test to be performed
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
following welding or brazing associated
with repair or replacement activities,
prior to returning the component to
service. However, it allows a licensee
the option of only performing a local
bubble test even for a ‘‘major’’
containment modification or repair/
replacement. Following ‘‘major’’
containment repair/replacement
activities, it makes the performance of
the appropriate pneumatic leakage test
(which is a Type A test) in accordance
with 10 CFR part 50, appendix J,
optional, and hence the NRC proposes
to add a new condition in this rule. It
is the NRC’s position that a 10 CFR part
50, appendix J, Type A test or
alternatively, a short duration structural
test, must be performed following a
‘‘major’’ containment modification or
repair/replacement, prior to returning
the containment to operation. This is
because a ‘‘major’’ containment
modification such as the replacement of
a large penetration or the creation of
large construction opening(s) for
equipment replacement results in the
breach of the containment pressure
boundary that invalidates the periodic
verification of structural and leak tight
integrity provided by the previous Type
A test as required by the Containment
Leakage Rate Testing Program in 10 CFR
part 50, appendix J. Further, the breach
of pressure boundary of the magnitude
resulting from a ‘‘major’’ containment
modification has a global effect on
containment structural integrity and not
a localized effect. Therefore, performing
a Type A test or an alternate short
duration structural test, prior to
returning to operation, is necessary to
provide a reasonable assurance and
verification of containment structural
and leakage integrity following
restoration of a breach in the
containment pressure boundary due to a
‘‘major’’ repair/replacement activity.
Thus, the new condition in
§ 50.55a(b)(2)(v)(J) of the proposed rule
will require the performance of Type A
test, or short duration structural test,
following a ‘‘major’’ containment
modification.
The proposed new condition would
provide a general, qualitative definition
of what constitutes a ‘‘major’’
modification or repair/replacement
activity for containments. The proposed
condition would also define the
combination of actions that would
constitute an acceptable, alternate shortduration structural test that may be
performed in lieu of a Type A test
following a major containment
modification. These proposed
requirements to perform a Type A test,
or alternate short-duration structural
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
test, following a ‘‘major’’ containment
modification are consistent with the
NRC’s position and condition in Section
4.1.4 and Section 3.1.4 of the Final
Safety Evaluation by the Office Of
Nuclear Reactor Regulation dated June
25, 2008 (ADAMS No. ML081140105),
on Topical Report NEI 94–01, Revision
2, ‘‘Industry Guideline for Implementing
Performance-Based Option of 10 CFR
Part 50, Appendix J.’’ The new condition
would also require that, when applying
IWE–5000, if a Type A, B or C test is
performed in accordance with 10 CFR
part 50, appendix J, the acceptance
standard for the test shall also be in
accordance with 10 CFR part 50,
appendix J. This is because the
acceptance standard for leakage in IWE–
5223.5 is based only on Section V,
Article 10, for any pneumatic leakage
test performed when applying IWE–
5000 of the 2007 Edition up to and
including the 2008 Addenda of Section
XI of the ASME Code. The requirement
in the new condition for performing a
Type A test or an alternate short
duration structural test, prior to
returning to operation following a major
containment modification, is necessary
to provide a reasonable assurance and
verification of containment structural
and leakage integrity following
restoration of a breach in the
containment pressure boundary due to
the ‘‘major’’ repair/replacement activity.
10 CFR 50.55a(b)(2)(xv) Appendix VIII
Specimen Set and Qualification
Requirements (Current); 10 CFR
50.55a(b)(2)(xi) (Redesignated)
The NRC proposes to redesignate
§ 50.55a(b)(2)(xv) as § 50.55a(b)(2)(xi)
and revise the current regulations so the
current conditions in that paragraph
would not apply to the 2007 Edition
through the 2008 Addenda of Section XI
of the ASME B&PV Code. The current
regulation has conditions that may be
used to modify Appendix VIII of Section
XI, 1995 Edition through the 2001
Edition. The ASME Boiler and Pressure
Vessel Code Committees took action to
address these conditions in the 2007
Edition of the Code and revised
Appendix VIII to address the NRC’s
concerns with specimen sets and
qualification requirements. Therefore,
the conditions are not required when
using the 2007 Edition through the 2008
Addenda of the ASME B&PV Code, and
the NRC is proposing that the current
§ 50.55a(b)(2)(xv) should be revised not
to apply these conditions when using
the 2007 Edition through the 2008
Addenda of the ASME B&PV Code.
PO 00000
Frm 00015
Fmt 4701
Sfmt 4702
24337
10 CFR 50.55a(b)(2)(xviii) Certification
of NDE Personnel (Current); 10 CFR
50.55a(b)(2)(xiv) (Redesignated)
The NRC proposes to redesignate
§ 50.55a(b)(2)(xviii)(B) as
§ 50.55a(b)(2)(xiv)(B) and revise the
current regulations so the current
condition in that paragraph would not
apply to the 2007 Edition through the
2008 Addenda of Section XI of the
ASME B&PV Code. Section
50.55a(b)(2)(xviii)(B) in the current
regulations limits the activities that can
be performed by NDE personnel
certified in accordance with IWA–2316
of the 1998 Edition through the 2004
Addenda of the ASME B&PV Code.
These personnel are limited to
observing for leakage during system
leakage and hydrostatic tests conducted
in accordance with IWA–5211(a) and
(b). The ASME Boiler and Pressure
Vessel Code Committees took action to
address this, and modified IWA 2316 in
the 2005 Addenda and the 2007 Edition
to limit the activities performed by
personnel qualified in accordance with
IWA–2316. Therefore, the condition is
not required when using the 2007
Edition through the 2008 Addenda.
Accordingly, the NRC is proposing that
the current § 50.55a(b)(2)(xviii)(B) be
revised for this condition not to apply
when using the 2007 Edition through
the 2008 Addenda of the ASME B&PV
Code.
The NRC proposes to redesignate
§ 50.55a(b)(2)(xviii)(C) as
§ 50.55a(b)(2)(xiv)(C) and revise the
current requirement so the current
condition in that paragraph would not
apply to the 2005 Addenda through the
2008 Addenda of Section XI of the
ASME B&PV Code. This paragraph in
the current regulations places
conditions on the qualification of VT–3
examination personnel certified under
paragraph IWA–2317 of the 1998
Edition through the 2004 Addenda. The
regulation requires the administering of
an initial qualification examination to
demonstrate proficiency of this training,
and administering subsequent
examinations on a 3-year interval. The
ASME Boiler and Pressure Vessel Code
Committees took action to address this
condition and modified IWA–2317 in
the 2005 Addenda of the ASME B&PV
Code to require a written examination
for initial qualification and at least
every 3 years thereafter for VT–3
qualification. Therefore, the condition is
not required when using the 2005
Addenda through the 2008 Addenda.
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
24338
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
10 CFR 50.55a(b)(2)(xix) Substitution of
Alternative Methods (Current); 10 CFR
50.55a(b)(2)(xv) (Redesignated)
The NRC proposes to redesignate
§ 50.55a(b)(2)(xix) as § 50.55a(b)(2)(xv)
and revise the current regulations so the
current conditions for the substitution
of alternative examination methods in
that paragraph would not apply when
using the 2005 Addenda through the
2008 Addenda. The conditions in
current § 50.55a(b)(2)(xix) do not allow
the use of Section XI, IWA 2240 of the
1998 Edition through the 2004 Edition
of the ASME B&PV Code. These
conditions also do not allow the use of
IWA–4520(c) of the 1997 Addenda
through the 2004 Edition of Section XI
of the ASME B&PV Code. In 2005, the
ASME Boiler and Pressure Vessel Code
Committees took action to address these
conditions and modified IWA–2240 and
deleted IWA–4520(c) in the 2005
Addenda, such that, alternative
examination methods or newly
developed techniques are not allowed to
be substituted for the methods specified
in the construction code. Therefore,
these conditions are not required when
using the 2005 Addenda through the
2008 Addenda.
In newly redesignated
§ 50.55a(b)(2)(xv), the NRC is also
proposing to impose the condition that
paragraphs IWA–4520(b)(2) and IWA–
4521 of the 2007 Edition of Section XI,
Division 1, of the ASME B&PV Code,
with the 2008 Addenda are not
approved for use. In the 2008 Addenda
of Section XI of the ASME B&PV Code,
the ASME added new provisions in
IWA 4520(b)(2) and IWA–4521 that
allow the substitution of ultrasonic
examination (UT) for radiographic
examination (RT) specified in the
Construction Code. Substitution of UT
for RT as addressed in paragraph IWA–
4520(b)(2) of the ASME B&PV Code,
Section XI, for the repair/replacement
welds in 2008 Addenda is of a concern
to the NRC because, depending on flaw
type (i.e., volumetric or planar) and
orientation, UT and RT are not equally
effective for flaw detection and
characterization. The NRC had
originally identified concerns relative to
the calibration blocks to be used, and
developed two conditions that appear in
Regulatory Guide 1.84, ‘‘Design,
Fabrication, and Materials Code Case
Acceptability, ASME Section III,
Proposed Revision 34.’’
RT is effective in detecting
volumetric-type flaws (e.g., slag,
porosity, root concavity, and
misalignment), planar type flaws with
large openings (e.g., lack of fusion and
large cracks in high stressed areas), and
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
those flaws that are oriented in a plane
parallel to the X-ray beam. RT is
effective in all materials common to the
nuclear industry for detecting the type
of flaws generated during construction,
due to workmanship issues and,
therefore, ensures an acceptable level of
weld quality and safety at the time of
construction. In contrast, UT is most
effective in detecting and sizing planartype flaws associated with inservice
degradation due to, for example, fatigue
or stress corrosion cracking. Significant
advances have recently been made
regarding the use of UT to detect flaws
in cast stainless steel. However, the
ASME Code provisions addressing the
inspection of cast stainless steels are
still under development and are,
therefore, not yet published for use.
Finally, UT requires more surface
scanning area than RT to perform
examinations.
To ensure that a UT technique would
be capable of detecting typical
construction flaws, the NRC would
require a licensee to demonstrate,
through performance-based ASME
B&PV Code, Section XI, Appendix VIIIlike requirements, its capability of
identifying the construction flaws
which are easily detected by RT.
Performance-based qualifications
require demonstrations on mockups
having flaws with realistic UT responses
and with a statistically sufficient
number of representative flaws and nonflawed volumes to establish procedure
effectiveness and personnel skill. The
statistical approach to qualification has
been shown to improve the reliability of
inspections, to improve the probability
of flaw detection, and to reduce the
number of false calls. The addition of
only two or three construction flaws to
a demonstration is not sufficient to
capture the variety of flaws common to
construction or to statistically evaluate
procedure effectiveness and personnel
skills.
The NRC is concerned that using the
second leg of the ultrasound metal path
(V-path) to achieve two direction
scanning from only one side of the weld
may not be adequate in detecting
construction flaws. Single side
examinations have not been
demonstrated for construction flaws for
any material. Single side examinations
of welds have been successfully
qualified for planar flaws in ferritic
carbon and low alloy steels but have not
been reliably demonstrated for
austenitic stainless steel and nickel
alloys.
Based on this information, the NRC
concludes that the substitution of UT for
RT may not be adequate for detecting
some construction flaws, specifically in
PO 00000
Frm 00016
Fmt 4701
Sfmt 4702
single-V full penetration groove welds.
Therefore, substitution of UT for RT is
not generically acceptable. This position
is consistent with the NRC’s previous
position with respect to the review of
ASME Code Case N–659–1, which is
published in Regulatory Guide 1.193,
Revision 2, ‘‘ASME Code Cases not
Approved for Use.’’ Accordingly, the
NRC proposes to impose the condition
that paragraphs IWA–4520(b)(2), and
IWA–4521 of the 2007 Edition of
Section XI, Division 1, with 2008
Addenda are not approved for use.
10 CFR 50.55a(b)(2)(xxiv) Incorporation
of the Performance Demonstration
Initiative and Addition of Ultrasonic
Examination Criteria (Current); 10 CFR
50.55a(b)(2)(xx) (Redesignated)
The NRC proposes to redesignate
§ 50.55a(b)(2)(xxiv) as § 50.55a(b)(2)(xx)
and revise the current regulations not to
apply the current condition when using
the 2007 Edition through the 2008
Addenda. Current § 50.55a(b)(2)(xxiv)
prohibits the use of Appendix VIII, the
supplements of Appendix VIII and
Article I–3000 of ASME B&PV Code,
2002 Addenda through the 2004
Edition. In 2007, the ASME Boiler and
Pressure Vessel Code Committees took
action to address this condition and
modified Appendix VIII and its
Supplements in the 2007 Edition.
Therefore, the condition is not required
when using the 2007 Edition through
the 2008 Addenda, and the NRC
proposes to eliminate this condition
when using the 2007 Edition through
the 2008 Addenda.
10 CFR 50.55a(b)(2)(xxvii) Removal of
Insulation (Current); 10 CFR
50.55a(b)(2)(xxii) (Redesignated)
The NRC proposes to redesignate
§ 50.55a(b)(2)(xxvii) as
§ 50.55a(b)(2)(xxiii) and revise the
paragraph to refer to IWA–5242 of the
2003 Addenda through the 2006
Addenda or IWA–5241 of the 2007
Edition through the 2008 Addenda of
Section XI of the ASME B&PV Code for
performing VT–2 visual examination of
insulated components in systems
borated for the purpose of controlling
reactivity. The current regulations at
§ 50.55a(b)(2)(xxvii) place specific
requirements on when insulation must
be removed to visually examine
insulated components in accordance
with IWA–5242. In the 2007 Edition of
the ASME B&PV Code, Section XI,
paragraph IWA–5242 was deleted and
these requirements were included in
paragraph IWA–5241.
E:\FR\FM\04MYP3.SGM
04MYP3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
10 CFR 50.55a(b)(2)(xxiv) Analysis of
Flaws (New)
The NRC proposes to add a new
§ 50.55a(b)(2)(xxiv) to place conditions
on the use of Section XI, Nonmandatory
Appendix A, ‘‘Analysis of Flaws.’’ The
proposed regulation would place a
condition on the use of Appendix A
related to the fatigue crack growth rate
calculation for subsurface flaws defined
in paragraph A–4300(b)(1) when the
ratio of the minimum cyclic stress to the
maximum cyclic stress (R) is less than
zero. The fatigue crack growth rate, da/
dN, is defined as follows when using
Equation (1) in paragraph A–4300(a)
and Equation (2) in paragraph A–
4300(b)(1):
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
da/dN = 1.99 × 10¥10 S (DKI)3.07, where S is
a scaling parameter and DKI is the range
of applied stress intensity factor
S and DKI are defined in A–4300(b)(1) of the
ASME B&PV Code, Section XI, Appendix
A as follows:
For ¥2 ≤ R ≤ 0 and Kmax¥Kmin ≤ 1.12 sf
√(πa), S = 1 and DKI = Kmax
For R < ¥2 and Kmax¥Kmin ≤ 1.12 sf √(πa),
S = 1 and DKI = (1–R) Kmax/3
For R < 0 and Kmax¥Kmin > 1.12 sf √(πa),
S = 1 and DKI = Kmax—Kmin
The above guidelines permit
reduction of DKI from the value of
(Kmax¥Kmin) when Kmax¥Kmin ≤ 1.12 sf
√(πa). This is adequate if the material
property sf is from test-based data of the
component material and if the geometry
of the cracked component can be
modeled as an edge crack in a half
plane, so that the formula K = 1.12 s
√(πa) applies. In most ASME B&PV
Code, Section XI, Appendix A
applications, test-based sf is not
available, and the generic value from the
ASME B&PV Code tabulations is used.
Further, the geometry of a subsurface
flaw in a plate differs significantly from
the model of an edge crack in a half
plane. Consequently, for the case where
full DKI should be used, the calculation
in accordance with ASME B&PV Code,
Section XI, Appendix A may show that
Kmax¥Kmin ≤ 1.12 sf √(πa) and prompt
a wrongful reduction of DKI.
To address the use of the generic sf
value instead of the test-based value for
the cracked component and the
significant difference between the
cracked component geometry and the
cracked test-specimen geometry on
which the criterion of 1.12 sf √(πa) is
derived, the NRC proposes to revise the
criterion of 1.12 sf √(πa) to 0.8 times
1.12 sf √(πa). By doing so, reduction of
DKI will not take place during the range
of Kmax¥Kmin from 0.8 ×1.12 sf √(πa) to
1.12 sf √(πa), erasing the nonconservatism from the two sources
mentioned above. Selection of a
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
24339
multiplying factor of 0.8 is based on the
following:
• The 10 percent error that could be
introduced for the subsurface flaw
configurations having membrane stress
correction factors less than 1.12 as
indicated in Appendix A, Figure A–
3310–1, and
• Another 10-percent error that
accounts for the uncertainty in the sf
value.
Applying the revised criterion of 0.8
× 1.12 sf √(πa), results in the proposed
following condition on the use of the
fatigue crack growth rate calculation for
subsurface flaws defined in paragraph
A–4300(b)(1) of Section XI,
Nonmandatory Appendix A when R is
less than zero:
Where KIm, KIr, and KIt are the applied
primary, residual, and thermal stresses,
respectively, and KIc is plane-strain
fracture toughness. Both are based on a
postulated flaw of 1-inch in depth. The
details regarding these criteria are
documented in the Electric Power
Research Institute’s (EPRI) report NP–
5151, ‘‘Evaluation of Reactor Vessel
Beltline Integrity Following
Unanticipated Operating Events,’’ dated
April 1987. The justification for selecting
the 1-inch deep flaw is given in the EPRI
report as follows:
The crack size range has an upper limit of
one inch. Experience shows that the
fabrication practice and inspection
requirements for nuclear pressure vessels
generally preclude the undetected presence
of larger flaws.
da/dN = 1.99 × 10¥10 S (DKI)3.07
For R < 0, DKI depends on the crack depth,
a, and the flow stress, sf. The flow stress
is defined by sf = 1⁄2(sys + sult), where sys
is the yield strength and sult is the
ultimate tensile strength in units ksi
(MPa) and a is in units in. (mm).
For ¥2 ≤ R ≤ 0 and Kmax¥Kmin ≤ 0.8 × 1.12
sf √(πa), S = 1 and DKI = Kmax.
For R < ¥2 and Kmax¥Kmin ≤ 0.8 × 1.12 sf
√(πa), S = 1 and DKI = (1–R) Kmax/3.
For R < 0 and Kmax¥Kmin > 0.8 × 1.12 sf
√(πa), S = 1 and DKI = Kmax¥Kmin.
The above qualitative justification for
selecting the 1-inch depth for the
postulated flaw is not sufficient. The
ASME B&PV Code, Section XI,
Appendix G, ‘‘Fracture Toughness
Criteria for Protection Against Failure,’’
analysis, which can be considered as the
first ‘‘screening’’ criterion for safe
operation of an RPV, is based on a
postulated flaw of one-quarter of the
RPV wall thickness (1/4T). The Section
XI, Appendix E analysis is employed
when the ASME B&PV Code, Appendix
G requirements are exceeded due to an
out-of-limit condition. Hence, it is
considered as the second ‘‘screening’’
criterion, i.e., once satisfied, a refined
analysis or a special RPV inspection is
not needed. As the second screening
tool, the Section XI, Appendix E
analysis has to be conservative. In
addition, the following three concerns
prompt the NRC to propose the use of
a 1/4T flaw in the Appendix E, Section
E–1300 analysis:
• In the probabilistic fracture
mechanics (PFM) analyses supporting
the proposed PTS rule, the truncated
flaw depth for a repair weld flaw is 2
inches. For a deterministic analysis, the
possibility of having a repair weld flaw
line up with a clad flaw to become a
surface flaw cannot be ruled out.
• The Pressure Vessel Research User’s
Facility (PVRUF) and Shoreham RPV
flaw data, used to develop generic flaw
distributions for the proposed PTS rule,
identified flaws that were consistently
smaller than the proposed bounding
flaw. However, the PVRUF and
Shoreham data represent only a limited
sampling of all RPV welds and may not
directly provide an adequate bounding
flaw size for a deterministic analysis
like that of ASME B&PV Code, Section
XI, Appendix E.
• The use of a 1/4T flaw assumption
also provides additional assurance that
10 CFR 50.55a(b)(2)(xxv) Evaluation of
Unanticipated Operating Events (New)
The NRC proposes to add a new
§ 50.55a(b)(2)(xxv) to condition the use
of ASME B&PV Code, Section XI,
Nonmandatory Appendix E, ‘‘Evaluation
of Unanticipated Operating Events.’’
Appendix E provides acceptance criteria
and guidance evaluating the effects of
out-of-limit conditions on structural
integrity of the reactor vessel beltline
region. The NRC proposes to specify
that Section E–1200 is not acceptable,
and to set forth two conditions on the
use of Section E–1300. One proposed
condition would require that a 1/4T
flaw be used in the linear elastic
fracture mechanics (LEFM) evaluation
with a margin of 1.4 applying to KIm in
the two LEFM criteria. The other
proposed condition would also use KIc
instead of KIR in the Appendix E
analysis.
Appendix E of the ASME B&PV Code,
Section XI, addresses the evaluation of
the structural integrity of the reactor
pressure vessel (RPV) after an out-oflimit condition occurs using LEFM
based on a postulated surface flaw. The
underlying Appendix E methodology is
based on the following two LEFM
criteria:
1.6(KIm) + KIr = KIc for the low temperature
overpressure (LTOP) condition
1.6(KIm + KIt) + KIr = KIc, for the pressurized
thermal transient (PTT) condition
PO 00000
Frm 00017
Fmt 4701
Sfmt 4702
E:\FR\FM\04MYP3.SGM
04MYP3
24340
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
any service-induced growth of current
fabrication flaws will be bounded for
any RPVs having experienced severe
transients over the course of their
operating lifetimes.
Requiring that a 1/4T flaw be used in
the LEFM evaluation with a margin of
1.4 applying to KIm in the two LEFM
criteria establishes a consistent
approach regarding the postulated flaw
size in the two deterministic LEFM
analyses in ASME B&PV Code, Section
XI, Appendices E and G. Applying the
margin of 1.4 only to KIm is consistent
with the ASME B&PV Code, Section XI,
Appendix G approach, making the
decreased margin between the two
appendices traceable. The proposed use
of a smaller margin of 1.4 in the ASME
B&PV Code, Section XI, Appendix E
analysis is justified because all
significant stress intensity factors
resulting from an actual transient are
considered. Further, using a 1/4T flaw
is also consistent with prior NRC
approaches for evaluation of RPV
structural integrity after out-of-limit
events. The EPRI NP–5151 report
mentioned that reference toughness KIR
has been used in the LEFM evaluation
in the prior NRC evaluation of RPV
structural integrity after out-of-limit
events. Consistent with the evolution of
the ASME B&PV Code, Section XI,
Appendix G analysis, the NRC now
proposes to use KIc instead of KIR in the
ASME B&PV Code, Section XI,
Appendix E analysis.
10 CFR 50.55a(b)(2)(xxvi) Risk-Informed
Inservice Inspection (New)
The NRC proposes to add a new
condition in § 50.55a(b)(2)(xxvi) to
condition the use of ASME B&PV Code,
Section XI, Non-Mandatory Appendix
R, ‘‘Risk-Informed Inspection
Requirements of Piping.’’ The proposed
condition would require licensees to
submit an alternative in accordance
with § 50.55a(a)(3) and obtain NRC
authorization of the proposed
alternative prior to implementing
Appendix R, RI–ISI programs. The 2004
Edition of the ASME B&PV Code,
Section XI currently incorporated by
reference in the regulations did not
contain provisions for Risk-Informed
Inservice Inspection (RI–ISI). The 2005
Addenda introduced Non-Mandatory
Appendix R into Section XI to provide
risk-informed requirements for the ISI of
ASME B&PV Code Class 1, 2 and 3
piping. The addition of Appendix R to
Section XI was essentially the
incorporation of ASME Code Cases N–
577 and N–578 into the ASME B&PV
Code. The NRC determined that ASME
Code Cases N–577 and N–578 were
unacceptable for use and are currently
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
listed in Regulatory Guide 1.193,’’ASME
Code Cases Not Approved for Use,’’
Revision 2. Licensees have been
implementing RI–ISI requirements for
piping as an alternative to the ASME
B&PV Code, Section XI requirements of
Tables IWB–2500–1, IWC–2500–1 and
IWD–2500–1 submitted in accordance
with § 50.55a(a)(3). Adding a condition
as § 50.55a(b)(2)(xxvi) that would
require licensees to submit an
alternative in accordance with
§ 50.55a(a)(3) and obtain NRC
authorization of the proposed
alternative prior to implementing
Appendix R, RI–ISI programs would
ensure that future RI–ISI programs
continue to comply with RG 1.178, ‘‘An
Approach for Plant-Specific RiskInformed Decisionmaking for Inservice
Inspection of Piping,’’ RG1.200, ‘‘An
Approach for Determining the Technical
Adequacy of Probabilistic Risk
Assessment Results for Risk-Informed
Activities,’’ and NRC Standard Review
Plan 3.9.8, ‘‘Risk-Informed Inservice
Inspection of Piping.’’
ASME OM Code
The proposed amendment would
revise the introductory text in
§ 50.55a(b)(3) to incorporate by
reference the 2005 and 2006 Addenda of
the ASME OM Code into 10 CFR 50.55a.
The proposed amendment to
§ 50.55a(b)(3) would also clarify that
Subsections ISTA, ISTB, ISTC, and
ISTD, Mandatory Appendices I and II,
and Nonmandatory Appendices A
through H and J of the ASME OM Code
would be incorporated by reference.
The conditions in § 50.55a(b)(3)(i),
(b)(3)(ii), and (b)(3)(iv) would continue
to apply to the 2005 and 2006 Addenda
because the earlier ASME B&PV Code
provisions that these regulations are
based on were not revised in the 2005
and 2006 Addenda of the ASME B&PV
Code to address the underlying issues
which led the NRC to impose the
conditions on the ASME B&PV Code.
The NRC proposes to revise the
current requirements in § 50.55a(b)(3)(v)
to be consistent with the revised
snubber ISI provisions in the 2006
Addenda of the ASME B&PV Code,
Section XI. To accomplish this
§ 50.55a(b)(3)(v) will be divided into
§ 50.55a(b)(3)(v)(A) and
§ 50.55a(b)(3)(v)(B). Where
§ 50.55a(b)(3)(v)(A) allows licensees
using editions and addenda up to the
2005 Addenda of ASME Section XI to
optionally use Subsection ISTD, ASME
OM Code in place of the requirements
for snubbers in Section XI. Section
50.55a(b)(3)(v)(B) would require
licensees using the 2006 Addenda and
later editions and addenda of Section XI
PO 00000
Frm 00018
Fmt 4701
Sfmt 4702
to follow the requirements of Subsection
ISTD of the ASME OM Code for
snubbers. Provisions for the ISI of
snubbers have been in Subsection ISTD
since the ASME OM Code was first
issued in 1990.
10 CFR 50.55a(b)(3)(v) Subsection ISTD
The current requirement in
§ 50.55a(b)(3)(v) allows licensees using
editions and addenda up to the 2004
Edition of the ASME B&PV Code,
Section XI to optionally use Subsection
ISTD, ASME OM Code in place of the
requirements for snubbers in Section XI,
and states that snubber preservice and
inservice examinations must be
performed using the VT–3 visual
examination method when using
Subsection ISTD of the ASME OM Code.
The NRC previously imposed this
requirement to ensure that an
appropriate visual examination method
was used for the inspection of integral
and non-integral snubber attachments,
such as lugs, bolting, and clamps when
using Subsection ISTD of the ASME OM
Code. The proposed § 50.55a(b)(3)(v)(A)
allows licensees using editions and
addenda up to the 2005 Addenda of
ASME B&PV Code, Section XI to
optionally use Subsection ISTD, ASME
OM Code in place of the requirements
for snubbers in Section XI and
continues to invoke the VT–3
requirement. This option does not apply
when using the 2006 Addenda and later
editions and addenda of Section XI of
the ASME B&PV Code. Figure IWF–
1300–1 was revised in the 2006
Addenda of Section XI to clarify that
integral and non-integral snubber
attachments are in the scope of Section
XI. Therefore, the visual examination
method specified in the 2006 Addenda
and later editions and addenda of
Section XI applies to the examination of
integral and non-integral snubber
attachments. The proposed
§ 50.55a(b)(3)(v)(B) would require
licensees using the 2006 Addenda and
later editions and addenda of Section XI
to follow the requirements of Subsection
ISTD of the ASME OM Code for
snubbers.
10 CFR 50.55a(b)(3)(vi) Exercise Interval
for Manual Valves
The NRC proposes to revise the
current requirement for exercising
manual valves in § 50.55a(b)(3)(vi) to
limit its application to the 1999 through
2005 Addenda of the ASME OM Code.
The current requirement would not
apply to the 2006 Addenda of the ASME
OM Code because the earlier ASME OM
Code provision that this regulation was
based on was revised in the 2006
E:\FR\FM\04MYP3.SGM
04MYP3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
Addenda of the ASME OM Code to
address the underlying issue which led
to the NRC to impose the condition. The
exercise interval in Subarticle ISTC–
3540 for manually operated valves was
revised in the 2006 Addenda of the
ASME OM Code to be the same as the
current requirement in
§ 50.55a(b)(3)(vi).
Reactor Coolant Pressure Boundary,
Quality Group B Components, and
Quality Group C Components
The NRC proposes to revise
§ 50.55a(c)(3), (d)(2), and (e)(2) to
replace ‘‘but—’’ with ‘‘subject to the
following conditions’’ at the end of the
introductory text to each paragraph for
clarity.
Inservice Testing Requirements
10 CFR 50.55a(f)(5)(iv) Requests for
Relief
The NRC proposes to modify the
wording of § 50.55a(f)(5)(iv) to clarify
that licensees are required to submit
requests for relief based on
impracticality within 12 months after
the expiration of the IST interval for
which relief is being sought. Section
50.55a(f)(5)(iv) in the current
regulations describes the licensee’s
responsibility to demonstrate to the
satisfaction of the NRC those items
determined to be impractical and
discusses the timeframe for this
determination. The NRC proposes to
clarify § 50.55a(f)(5)(iv) to more clearly
articulate the requirements for licensee
action when compliance with certain
code requirements is determined to be
impractical. Licensees have interpreted
the current language in § 50.55a(f)(5)(iv)
in a number of ways, especially
regarding NRC approval of their
submittal within the specified
timeframe. Since the licensee has little
or no control over the timeliness of NRC
action on their submittal, this
interpretation is problematic.
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Inservice Inspection Requirements
Snubber Examination and Testing
The current requirements at
§ 50.55a(g)(2), (g)(3)(i), (g)(3)(ii), the
introductory text of (g)(4), and (g)(4)(i)
and (g)(4)(ii) reference Section XI of the
ASME B&PV Code for component
support ISI (including snubber
examination and testing) provisions.
The current requirement at
§ 50.55a(b)(3)(v) allows licensees the
option of using Subsection ISTD of the
ASME OM Code in lieu of the ISI
provisions for snubbers in Article IWF–
5000 of Section XI. When using the
2005 Addenda to Section XI, Article
IWF–5000 is required to be used with
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
the option to use OM Code Subsection
ISTD noted. In the 2006 Addenda and
later editions and addenda of Section
XI, the snubber requirements in Article
IWF–5000 no longer exist because
Article IWF–5000 was deleted in the
2006 Addenda of Section XI. Therefore,
the proposed amendment would revise
§ 50.55a(b)(3)(v) to require that licensees
use the provisions for examination and
testing snubbers in Subsection ISTD of
the ASME OM Code when using the
2006 Addenda and later editions and
addenda of Section XI.
The NRC proposes to revise the
current regulations in § 50.55a(g)(2),
(g)(3)(i), (g)(3)(ii), (g)(4)(i) and (g)(4)(ii)
to require that licensees use the
provisions for preservice and inservice
examination and testing of snubbers in
Subsection ISTD of the ASME OM Code
when using the 2006 Addenda and later
edition of Section XI. Licensees may
also use optional code cases in RG 1.192
as approved by the NRC. The NRC
proposes to clarify that preservice
examination may meet preservice
examination requirements in Section III
as an alternative to preservice
examination of Section XI. The NRC
also proposes to revise the current
regulation in the introductory text of
§ 50.55a(g)(4) to require that licensees
using the ASME OM Code follow the
provision in Subsection ISTD for
examination and testing of snubbers.
Provisions for examinations and tests of
snubbers have been in Article IWF–5000
since Subsection IWF was first issued in
the Winter 1978 Addenda of Section XI.
Article IWF–5000 was deleted in the
2006 Addenda of Section XI. Subarticle
IWF–1220 in the 2006 Addenda of
Section XI states that the examination
and testing requirements for snubbers
are now outside the scope of Section XI,
and that the examination and test
requirements for snubbers can be found
in Subsection ISTD of the ASME OM
Code. Provisions for the examination
and testing of snubbers have been in
Subsection ISTD since the ASME OM
Code was first issued in 1990.
10 CFR 50.55a(g)(4)(iii) Surface
Examinations of High-Pressure Safety
Injection Systems
The current regulations at
§ 50.55a(g)(4)(iii) give licensees the
option of not performing surface
examinations of high-pressure safety
injection systems as specified in Section
XI, Table IWB–2500–1, ‘‘Examination
Category B–J,’’ Item Numbers B9.20,
B9.21 and B9.22. Later editions and
addenda of Section XI have been
modified and the surface examination
requirement no longer exists in Table
IWB–2500–1, and some of the Item
PO 00000
Frm 00019
Fmt 4701
Sfmt 4702
24341
Numbers have either changed or been
deleted. The surface examination
requirement was remove from Table
IWB–2500–1 in the 2003 Addenda.
Therefore, the paragraph needs to be
revised for this condition to apply to
those licensees using Code editions and
addenda prior to the 2003 Addenda.
10 CFR 50.55a(g)(5)(iii) and (g)(5)(iv)
Inservice Inspection Requests for Relief
Section 50.55a(g)(5)(iii) currently
requires the licensee to notify the NRC
if compliance with certain code
requirements are found to be
impractical. The NRC proposes to add a
sentence to § 50.55a(g)(5)(iii) to clarify
that a request for relief must be
submitted to the NRC no later than 12
months after the examination has been
attempted during a given ISI interval
and the ASME B&PV Code requirement
determined to be impractical. In the
past, licensees have submitted requests
under § 50.55a(g)(5)(iii) prior to
performing the ASME B&PV Code
examination in a given interval based on
limited examination coverage from
previous ISI 10-year intervals. The NRC
has concluded that this is an
inappropriate basis for a determination
of impracticality as new examination
techniques are often developed from
one interval to the next, which could
result in a reasonable expectation of
improved results. As a result, the NRC
has concluded that a licensee usually
cannot make the determination that an
examination is indeed impractical
without first attempting the examination
in the current ISI interval.
In addition, if the NRC were to grant
relief prior to the component having
been examined and the results of the
examination are less than stated in the
request for relief, the licensee would be
required to resubmit the request for
relief to address the actual examination.
This places an unnecessary burden on
the licensee and the NRC to review the
same issue twice. The proposed
amendment to the regulations attempts
to clarify that the determination of
impracticality should be based on actual
attempts to perform a requirement and
only submitted after the attempt to
perform a requirement has been
unsuccessful.
The NRC proposes to modify the
wording of § 50.55a(g)(5)(iv) to clarify
that licensees are required to submit
requests for relief based on
impracticality within 12 months after
the expiration of the ISI interval for
which relief is being sought. Section
50.55a(g)(5)(iv) in the current
regulations describe the licensee’s
responsibility to demonstrate to the
satisfaction of the NRC those items
E:\FR\FM\04MYP3.SGM
04MYP3
24342
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
determined to be impractical and
discusses the timeframe for this
determination. The NRC proposes to
clarify § 50.55a(g)(5)(iv) to more clearly
articulate the requirements for licensee
action when compliance with certain
code requirements is determined to be
impractical. It is the NRC’s experience
that licensees have interpreted the
current language in § 50.55a(g)(5)(iv) in
a number of ways, especially regarding
NRC approval of their submittal within
the specified timeframe. Since the
licensee has little or no control over the
timeliness of NRC action on their
submittal, this interpretation is
problematic.
such that the portion of welds to be
inspected in the remaining portion of
the interval be based on the portion of
the interval remaining as of January 1,
2009. Instead, the wording is being
incorrectly interpreted by some
licensees as requiring all the welds to be
distributed over, and inspected during,
the remaining periods and outages in
the interval. The NRC proposes to revise
footnote 1 to § 50.55a(g)(6)(ii)(E) to
clarify this issue.
10 CFR 50.55a(g)(6)(ii)(E) Reactor
Coolant Pressure Boundary Visual
Inspections
The NRC proposes to update
§ 50.55a(g)(6)(ii)(E)(1) through
(g)(6)(ii)(E)(3) to the requirements of
Code Case N–722–1, and to revise
footnote 1 to clarify requirements in that
paragraph that pertain to reactor coolant
pressure boundary visual inspections. In
the most recent update to 10 CFR
50.55a, the NRC added new
requirements in § 50.55a(g)(6)(ii)(E). The
new requirements were for all licensees
of PWRs to augment their ISI program
by implementing ASME Code Case N–
722, subject to the conditions specified
in § 50.55a(g)(6)(ii)(E)(2) through
(g)(6)(ii)(E)(4). ASME Code Case N–722–
1, ‘‘Additional Examinations for PWR
Pressure Retaining Welds in Class 1
Components Fabricated With Alloy 600/
82/182 Materials Section XI, Division
1,’’ was published in Supplement 8 of
the 2007 Edition of the ASME Boiler
and Pressure Vessel Code Nuclear Code
Case book. This revision of the code
case contains one additional note which
indicates that visual examination of
Alloy 600/82/182 materials in flange
seal leak-off lines is not required. This
change will eliminate the need for
licensees to submit relief requests for
flange seal leak-off lines which are not
normally exposed to a corrosive
environment and are inaccessible for
visual examination.
The wording in the second sentence
of footnote 1 to § 50.55a(g)(6)(ii)(E) has
generated some confusion, and has the
unintended consequence of some
licensees believing that they need to
submit additional relief requests related
to the percentage of inspections to be
completed during the current interval.
The second sentence in the footnote is
intended to specify what portion of
welds has to be inspected during a plant
interval that remains after January 1,
2009. The intent was to require
licensees to distribute the population
The NRC proposes to add a new
§ 50.55a(g)(6)(ii)(F) to require licensees
to implement ASME Code Case N–770,
‘‘Alternative Examination Requirements
and Acceptance Standards for Class 1
PWR Piping and Vessel Nozzle Butt
Welds Fabricated with UNS N06082 or
UNS W86182 Weld Filler Material With
or Without the Application of Listed
Mitigation Activities, Section XI,
Division 1,’’ with 15 conditions. Code
Case N–770 contains baseline and ISI
requirements for unmitigated butt welds
fabricated with Alloy 82/182 material
and preservice and ISI requirements for
mitigated butt welds.
The application of ASME Code Case
N–770 is necessary because the
inspections currently required by the
ASME Code, Section XI, were not
written to address degradation of Alloy
82/182 butt welds by primary water
stress corrosion cracking (PWSCC), and
the safety consequences of inadequate
inspections can be significant. NRC’s
determination that current inspections
of certain Class 1 butt welds are
inadequate is based upon operating
experience and analysis. The absence of
an effective inspection regime could,
over time, result in unacceptable
circumferential cracking or the
degradation of reactor coolant system
components by corrosion from leaks in
these welds. These degradation
mechanisms increase the probability of
a loss of coolant accident. The current
ASME Code requirements for inspection
of Alloy 82/182 butt welds are not
frequent enough to ensure that ASME
Code-allowable limits will continue to
be met in the event that PWSCC
initiates. The growth rate of PWSCC in
these welds is rapid enough that
PWSCC could lead to leakage or rupture
before the degradation would be
detected by the inspections in the
ASME Code, Section XI, currently
required by 10 CFR 50.55a or by the
2005 Addenda through the 2008
Addenda of Section XI.
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
10 CFR 50.55a(g)(6)(ii)(F) Examination
Requirements for Class 1 Piping and
Nozzle Dissimilar-Metal Butt Welds
(New)
PO 00000
Frm 00020
Fmt 4701
Sfmt 4702
In late 2005, the NRC sent a letter to
ASME requesting it to address the
inspection requirements for Class 1
PWR piping butt welds fabricated with
Alloy 82/182 weld materials. ASME
approved the development of an ASME
code case on appropriate inspection
frequency requirements for Class 1 butt
welds containing Alloy 82/182 to
address primary water stress-corrosion
cracking (PWSCC). The code case format
was chosen by ASME to address this
safety-significant issue because a code
case is a stand-alone set of provisions
that can be approved more quickly than
revisions to the ASME B&PV Code.
Code cases are voluntary, however, so
these provisions were developed with
the expectation that the NRC would
incorporate the code case by reference
into the regulations. ASME Code Case
N–770, was approved by ASME on
January 30, 2009, and was published in
Supplement 8 of the 2007 Edition of the
ASME Boiler and Pressure Vessel Code
Nuclear Code Cases book. ASME Code
Case N–770 provides inspection
frequencies and methods for Alloy 82/
182 butt welds that are unmitigated as
well as butt welds that have been
mitigated for PWSCC by any of several
mitigation methods. ASME Code Case
N–770, with proposed conditions,
resolves the deficiencies in the ASME
B&PV Code, Section XI, inspection
requirements for Alloy 82/182 butt
welds by providing inspection
requirements that ensure that ASME
Code-allowable limits will not be
exceeded and PWSCC will not lead to
leaks or ruptures of piping welds.
Therefore, the NRC proposes to require
the implementation of Code Case N–
770, with conditions.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(2)) to require that
welds mitigated by inlays, cladding, or
stress improvement by welding, be
categorized as unmitigated welds
pending plant-specific NRC review of
the mitigation techniques and NRC
authorization of an alternative ASME
Code Case N–770 Inspection Item for
the mitigated weld. ASME Code Case
N–770 provides inspection methods and
frequencies for welds mitigated by
certain specified techniques.
Inspections of mitigated welds are
performed much less frequently than
unmitigated welds. Requirements for
most of the mitigation methods are
contained in other ASME code cases
under development. The NRC has
typically approved the application of
pressure boundary weld mitigation
techniques on a case-by-case basis. This
condition is necessary to ensure that
appropriate mitigation techniques are
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
applied to welds before they are
categorized as mitigated under Code
Case N–770.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(3)) to require that
the baseline examination of welds in
Inspection Items A–1, A–2, and B
(unmitigated welds) be completed at the
next refueling outage after the effective
date of the final rule. Paragraph –2200
of Code Case N–770 permits welds in
Inspection Items A–1, A–2, and B
(unmitigated welds) that have not
received a baseline examination to be
examined within the next two refueling
outages from adoption of the Code Case.
Welds in Inspection Items A–1, A–2,
and B are the welds most likely to
experience PWSCC and some of these
welds may not have received a baseline
examination, even under the industry
initiative, MRP–139. This condition is
necessary to ensure the integrity of these
welds by requiring that all welds in
Inspection Items A–1, A–2 and B be
inspected at the first opportunity to
perform the inspections.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(4)) to require
essentially 100 percent coverage for
axial flaws. Paragraph –2500(c) of Code
Case N–770 permits examination of
axial flaws with inspection coverage
limitations provided essentially 100
percent coverage for circumferential
flaws is achieved and the maximum
coverage practical is achieved for axial
flaws. This requirement on inspection
limitations is inconsistent with
comparable inspection requirements of
the ASME B&PV Code, Section XI. Axial
flaws can lead to through wall cracks
and leakage of reactor coolant, which is
a safety concern. This condition is
necessary for the NRC to ensure that,
through NRC review of an authorization
of alternative inspection coverage,
appropriate actions are being taken to
address potential inspection limitations
for axial flaws.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(5)) to reword
Paragraph –3132.3(b) on determining
flaw growth using wording consistent
with that used in the ASME B&PV Code,
Section XI. Paragraph –3132.3(b)
contains the statement that a ‘‘flaw is not
considered to have grown if the size
difference (from a previous
examination) is within the measurement
accuracy of the nondestructive
examination (NDE) technique
employed.’’ The ‘‘measurement accuracy
of the NDE technique employed’’ is not
defined in the code case or in the ASME
B&PV Code. Use of this terminology
may result in a departure from the past
practice when applying ASME B&PV
Code, Section XI. Under the
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
requirements of Section XI, one
concludes that flaw growth has not
occurred when a ‘‘previously evaluated
flaw has remained essentially
unchanged.’’ The proposed condition
uses this wording. This condition is
necessary to clarify the requirements for
determining whether flaw growth has
occurred and make the requirements
consistent with ASME B&PV Code
requirements endorsed by the NRC in 10
CFR 50.55a.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(6)) on welds that
are determined through a volumetric
examination to have cracking that
penetrates beyond the thickness of the
inlay or cladding. The condition would
require such welds to be reclassified as
Inspection Item A–1, A–2, or B, as
appropriate, until corrected by repair/
replacement activity in accordance with
IWA–4000 or by corrective measures
beyond the scope of Code Case N–770.
Code Case N–770 would permit welds
mitigated by inlay or cladding (i.e.,
onlay) in Inspection Items G, H, J, and
K, to remain in those Inspection Items
if cracking that penetrates through the
thickness of the inlay or cladding
occurs. The purpose of an inlay or
cladding is to provide a corrosion
resistant barrier between reactor coolant
and the underlying Alloy 82/182 weld
material that is susceptible to PWSCC.
If cracking penetrates through the
thickness of an inlay or cladding, the
inspection frequencies of Inspection
Items G, H, J, and K would no longer be
appropriate even after satisfying the
successive examination requirements of
paragraph –2420. This condition is
necessary because welds with cracking
that penetrates beyond the thickness of
the protective barrier of the inlay or
cladding would no longer be mitigated
and would need to be inspected under
one of the Inspection Items for
unmitigated welds.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(7)) on welds in
Inspection Items G, H, J, and K, (welds
mitigated by inlay or cladding) that the
ISI surface examination requirements of
Table 1 should apply whether the
inservice volumetric examinations are
performed from the weld outside
diameter or the weld inside diameter.
Code Case N–770 only requires a surface
examination for welds in Inspection
Items G, H, J, and K if a volumetric
examination is performed from the weld
inside diameter surface. A volumetric
examination performed from the weld
outside diameter surface would not be
capable of detecting flaws in an inlay or
cladding. This condition is necessary to
ensure that weld inlays or cladding are
still performing their intended function
PO 00000
Frm 00021
Fmt 4701
Sfmt 4702
24343
of providing a protective barrier
between the reactor coolant and the
underlying Alloy 82/182 weld that is
susceptible to PWSCC.
The NRC also proposes, as part of a
new condition as § 50.55a(g)(6)(ii)(F)(7),
to require that all hot-leg operating
temperature welds in Inspection Items
G, H, J, and K (welds mitigated by inlay
or cladding) be inspected each interval
and that a 25 percent sample of cold leg
operating temperature welds in
Inspection Items G, H, J, and K be
inspected whenever the core barrel is
removed (unless it has already been
inspected within the past 10 years) or 20
years, whichever is less. Code Case N–
770 permits welds in Inspection Items
G, H, J, and K to be placed in a 25
percent sample inspection program
under certain conditions after the
required initial inspection. The NRC has
performed analyses of crack growth in
welds mitigated by Alloy 52/152 inlay
or cladding using experimentally
derived crack growth data for this weld
material. The results of those analyses
show that welds in Inspection Items G,
H, J, and K at hot leg temperature have
to be examined once per interval and
welds at cold leg temperature have to be
inspected under a sample inspection
program to detect potentially significant
crack growth. This condition is being
proposed to ensure that ASME Codeallowable limits would not be exceeded
and PWSCC would not lead to leaks or
ruptures.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(8)) to prohibit the
first examination following weld inlay,
cladding, or stress improvement for
Inspection Items D, G, and H from being
deferred to the end of the interval. Code
Case N–770 provides requirements on
the timing of the first examination
following weld inlay, cladding, or stress
improvement. Inspection Items D, G,
and H pertain to mitigation of cracked
welds and the timing of the initial
examinations in the code case has been
specified in the code case so that the
welds are not in service for an extended
time period prior to the initial
examination. However, the code case
does not explicitly preclude deferral of
these examinations to the end of the
interval. Therefore, this NRC condition
is needed to ensure that the initial
examinations of welds in Inspection
Items D, G, and H take place on an
appropriate schedule to verify the
effectiveness of the mitigation process.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(9)) on Measurement
or Quantification Criterion I–1.1 of
Appendix I to require the assumption in
the weld residual stress (WRS) analysis
of a construction weld repair from the
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
24344
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
inside diameter to a depth of 50 percent
of the weld thickness extending 360°
around the weld. Measurement or
Quantification Criterion I–1.1 does not
specify the circumferential extent of the
repair that must be assumed. This
condition is necessary to clarify the size
of the repair to be assumed in the weld
residual stress analysis which would
ensure that appropriate criteria for the
WRS analysis are used for mitigation by
stress improvement.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(10)) on
Measurement or Quantification
Criterion I–2.1 of Appendix I to require
that the last sentence be replaced. This
criterion was inappropriately worded
since this criterion pertains to the
permanence of a mitigation process by
stress improvement and plastic
‘‘shakedown’’ rather than ‘‘ratcheting’’ is
the phenomenon that could lead to
stress relaxation. This condition is
necessary to clarify the type of analysis
necessary to ensure that the mitigation
process is permanent and that the
inspection frequencies associated with
the process continue to be correct.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(11)) to require that
in applying Measurement or
Quantification Criterion I–7.1 of
Appendix I, an analysis be performed
using IWB–3600 evaluation methods
and acceptance criteria to verify that the
mitigation process will not cause any
existing flaws to grow. Measurement or
Quantification Criterion I–7.1 permits
the growth of existing flaws in welds
mitigated by stress improvement. This is
an inappropriate provision since the
process of mitigating by stress
improvement is intended to prevent
growth of existing flaws which could
lead to leakage or rupture of the weld.
This condition is necessary to ensure
that stress improvement of welds with
existing flaws is an effective mitigation
technique consistent with the
inspection frequency in the code case.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(12)) to require that
the NRC be provided with a report if the
volumetric examination of any
mitigated weld detects new flaws or
growth of existing flaws that exceed the
acceptance standards of IWB–3514 and
are found to be acceptable for continued
service through an analytical evaluation
or a repair or the alternative
requirements of an ASME code case.
The report would summarize the
evaluation, along with inputs,
methodologies, assumptions, and cause
of the new flaw or flaw growth and
would be provided to the NRC prior to
the weld being placed in service. Welds
that are mitigated have been modified
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
by a technique, such as weld inlays,
cladding, or stress improvement.
Mitigation techniques are designed to
prevent new flaws from occurring and
prevent the growth of any existing
flaws. If volumetric examination detects
new flaws or growth of existing flaws in
the required examination volume, the
mitigation will not be performing as
designed and the NRC will need to
evaluate the licensee’s actions to
address the problem. Therefore, this
condition is needed to verify the
acceptability of the weld prior to being
placed back in service.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(13)) to require that
the last sentence of the Extent and
Frequency of Examination for
Inspection Items C and F be revised.
Inspection Items C and F apply to butt
welds mitigated by full structural weld
overlays of Alloy 52/152 material. Note
10 of the Code Case requires that welds
in Inspection Items C and F that are not
included in the 25 percent sample be
examined prior to the end of the
mitigation evaluation period if the plant
is to be operated beyond that time. This
condition would ensure that welds in
the 25 percent sample are also examined
prior to the end of the mitigation
evaluation period; that is, prior to the
end of life of the overlay predicted by
the mitigation evaluation. Inspection
prior to the end of the mitigation
evaluation period is necessary to ensure
that appropriate information has been
obtained to verify the condition of the
weld overlay and update the analysis for
the predicted life of the weld overlay.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(14)) on the 1⁄2-inch
(13 mm) dimension shown in Figures
2(b) and 5(b) of Code Case N–770. The
condition would require that a
dimension ‘‘b’’ be used instead of c inch,
where ‘‘b’’ is equivalent to the nominal
thickness of the nozzle or pipe being
overlaid, as appropriate. The code case
contains information on component
thicknesses to be used in application of
the acceptance standards of ASME
B&PV Code, Section XI, IWB–3514, to
evaluate flaws detected during
preservice inspection of weld overlays.
The 1⁄2-inch (13 mm) dimension shown
in Figures 2(b) and 5(b) is nonconservative. The appropriate
dimension is a function of the nominal
thickness of the nozzle or pipe being
overlaid and not a single specified value
for all pipes and nozzles. This condition
is necessary to ensure that acceptance
standards used for evaluation of any
flaws detected during preservice
inspection of weld overlays assure an
appropriate level of safety.
PO 00000
Frm 00022
Fmt 4701
Sfmt 4702
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(15)) on the use of
the acceptance standards of ASME
B&PV Code, Section XI, IWB–3514, for
evaluating indications in inlays or
onlays. The proposed condition
specifies that the thickness ‘‘t’’ in IWB–
3514 is the thickness of the inlay or
onlay. The code case requires that the
preservice examination for inlays or
onlays consist of a surface examination,
which does not allow planar flaws, and
a volumetric examination. The
volumetric examination allows the use
of the acceptance standards of IWB–
3514 provided the surface examination
acceptance standards are satisfied. That
is, it would allow the acceptance of
some subsurface indications, but IWB–
3514 acceptance standards would only
allow very small flaws. However, the
code case does not specify the value ‘‘t’’
to be used in the application of IWB–
3514. The appropriate value ‘‘t’’ when
applying IWB–3514 to inlays or onlays
is the thickness of the inlay or onlay,
since the acceptance standards in this
case only apply to accepting flaws
within the inlay or onlay. This
condition is necessary to preclude the
misapplication of the acceptance
standards of IWB–3514 and potential
acceptance of flaws that could
compromise the integrity and function
of the inlay or onlay as a protective
barrier.
The NRC proposes to add a condition
(§ 50.55a(g)(6)(ii)(F)(16)) on welds
mitigated by stress improvement by
welding in Inspection Items D and E to
not permit them to be placed into a
population to be examined on a sample
basis after the initial examination. Stress
improvement by welding is also called
an optimized weld overlay. Code Case
N–770 permits welds mitigated by this
technique to be placed in a 25 percent
inspection sample after the initial
examination. Sample inspections could
result in three-quarters of the welds
never being examined after the initial
examination. Although full structural
weld overlays have been used
extensively in the nuclear industry for
many years, the industry does not have
experience with optimized weld
overlays. Optimized weld overlays are
designed to rely on the outer 25 percent
of the original Alloy 82/182 material to
satisfy the design margins and would
not satisfy design margins if significant
cracking were to occur. If significant
cracking were to occur in the Alloy 82/
182 material, the optimized weld
overlay material would prevent the
weld from leaking and could potentially
rupture without prior evidence of
leakage under design basis conditions.
E:\FR\FM\04MYP3.SGM
04MYP3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
The proposed condition is necessary to
ensure that all optimized weld overlays
are periodically inspected for potential
degradation.
After ASME Code Case N–770 was
approved by ASME in early 2009, the
NRC brought concerns on the code case
to the attention of members of the
ASME B&PV Code, Section XI, task
group that developed it. These concerns
are the subject of these proposed
conditions. The ASME B&PV Code,
Section XI, has been working on a
revision to Code Case N–770 to address
many of these concerns. The NRC will
consider endorsing an ASME-approved
revision to Code Case N–770 in the final
rule to update 10 CFR 50.55a,
depending upon when such a revision
is issued and the contents of the
revision, and may remove some or all
conditions depending upon whether the
revised Code Case addresses the
concerns previously discussed.
Standards Approved for Incorporation
by Reference
10 CFR 50.55a(b)
The NRC proposes to add the title
‘‘Standards approved for incorporation
by reference’’ to paragraph (b).
The NRC proposes to modify the
language in paragraph (b) to clarify that
non-mandatory appendices are
excluded from the ASME B&PV Code,
Section III requirements that are
incorporated by reference into 10 CFR
50.55a, and to clarify that only Division
1 requirements of Section III and
Section XI are incorporated by reference
(not Division 2 and Division 3
requirements).
ASME B&PV Code, Section III
10 CFR 50.55a(b)(1)
The NRC proposes to substitute the
word ‘‘condition(s)’’ for the words
‘‘limitation(s)’’ ‘‘modification(s)’’ and
‘‘provision(s),’’ throughout 10 CFR
50.55a as shown in Table 1 of this
document for consistency. The NRC
does not believe it necessary to
distinguish among different types of
‘‘caveats’’ that it imposes on the use of
the ASME Codes, and therefore
proposes to use a single term for clarity
and consistency.
The NRC proposes to amend
paragraph (b)(1) to incorporate by
reference the 2005 Addenda (Division 1)
through 2008 Addenda (Division 1) of
Section III of the ASME B&PV Code into
10 CFR 50.55a, subject to the conditions
outlined in modified paragraphs (b)(1)(i)
through 50.55a(b)(1)(vi) and proposed
paragraph (b)(vii). The paragraph
modification would also include an
editorial change to the references to
Section III ASME B&PV Code for
clarification purposes. As a result,
applicants and licensees may use the
1974 Edition (Division 1) through the
2008 Addenda (Division 1) of Section III
of the ASME B&PV Code subject to the
conditions contained within modified
paragraphs (b)(1)(i) through (b)(1)(vi)
and new paragraph (b)(1)(vii).
IV. Paragraph-by-Paragraph Discussion
10 CFR 50.55a(b)(1)(ii)
Quality Standards, ASME Codes and
IEEE Standards, and Alternatives
The NRC proposes to apply the
existing condition in paragraph (b)(1)(ii)
regarding stress indices used for weld
stresses in piping design to the
comparable provisions in the ASME
Code editions and addenda
incorporated by reference in this
proposed rule. The paragraph
modification also includes the addition
of a condition on the use of paragraph
NB–3683.4(c)(2) for applicants and
licensees applying the 1989 Addenda
through the latest edition and addenda
of Section III of the ASME B&PV Code.
As a result, this modification prohibits
the use of Footnote 13 from the 2004
Edition through the 2008 Addenda of
Section III of the ASME B&PV Code to
Figures NC–3673.2(b)–1 and ND–
3673.2(b)–1 for welds with leg size less
than 1.09 times the nominal pipe wall
thickness (tn) for applicants and
licensees applying the 1989 Addenda
through the latest edition and addenda
of Section III of the ASME B&PV Code.
Substitution of the Term ‘‘Condition’’ in
10 CFR 50.55a
10 CFR 50.55a(a)
The NRC proposes to add the title
‘‘Quality standards, ASME Codes and
IEEE standards, and alternatives’’ to
paragraph (a).
Applicant/Licensee Proposed
Alternatives to the Requirements of 10
CFR 50.55a
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
10 CFR 50.55a(a)(3)
The NRC proposes to add a sentence
to paragraph (a)(3) to clarify that an
alternative is to be submitted to, and
approved by, the NRC prior to an
applicant or licensee implementing the
alternative. For applicants, approval of
an alternative must be obtained before
construction begins (rather than during
the design process).
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
PO 00000
Frm 00023
Fmt 4701
Sfmt 4702
24345
Also as a result, the use of paragraph
NB–3683.4(c)(2), is not allowed for
applicants and licensees applying the
1989 Addenda through the latest edition
and addenda of Section III of the ASME
B&PV Code.
10 CFR 50.55a(b)(1)(iii)
The NRC proposes to modify
paragraph (b)(1)(iii) to impose
conditions on the seismic design of
piping when licensees use the latest
editions and addenda of the ASME
B&PV Code, Section III, incorporated by
reference in modified paragraph (b). The
paragraph would also be modified with
an editorial change to replace
‘‘limitations and modifications’’ with
‘‘conditions’’ and ‘‘limitation’’ with
‘‘condition.’’ The modified paragraph
would allow the use of Subarticles NB–
3200, NB–3600, NC–3600, and ND–3600
for the seismic design of piping when
applying editions and addenda, up to
and including the 1993 Addenda of the
ASME B&PV Code, Section III, subject
to the condition in modified paragraph
(b)(1)(ii). The modified paragraph would
not allow the use of Subarticles NB–
3200, NB–3600, NC–3600, and ND–3600
for the seismic design of piping when
applying the 1994 Addenda through the
2006 Addenda of Section III of the
ASME B&PV Code except that
Subarticle NB–3200 in the 2004 Edition
through the 2008 Addenda of Section III
of the ASME B&PV Code may be used
by applicants and licensees subject to
the condition in new paragraph
(b)(1)(iii)(B). The modified paragraph
would allow the use of Subarticles NB–
3200, NB–3600, NC–3600, and ND–3600
for the seismic design of piping when
applying the 2006 Addenda through the
2008 Addenda of Section III of the
ASME B&PV Code, subject to the three
new conditions in new paragraphs
(b)(1)(iii)(A), (b)(1)(iii)(B), and
(b)(1)(iii)(C).
10 CFR 50.55a(b)(1)(iii)(A)
NRC proposes to add a new paragraph
(b)(1)(iii)(A) to impose a condition on
the minimum value of the B2 indices
when applicants and licensees use
Subarticle NB–3600 of the 2006
Addenda up to and including the 2008
Addenda of the ASME Code, Section III,
for the seismic design of piping. As a
result, licensees and applicants using
Subarticle NB–3600 of the 2006
Addenda up to and including the 2008
Addenda of the ASME B&PV Code,
Section III, for the seismic design of
piping must use a value for the B2
index, defined in Subparagraph NB–
3656(b)(3), equal to or greater than
0.75B2, from Table NB–3681(A)–1, for
Class 1 elbows and tees of ferritic steel
E:\FR\FM\04MYP3.SGM
04MYP3
24346
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
materials operating at temperatures
above 300°F.
10 CFR 50.55a(b)(1)(iii)(B)
The NRC proposes to add a new
paragraph (b)(1)(iii)(B) requiring
licensees and applicants using Note (1)
of Figure NB–3222–1 in Section III of
the 2004 Edition up to and including
the 2008 Addenda of the ASME B&PV
Code to include reversing dynamic
loads in calculating primary bending
stresses, if consideration of these loads
is warranted.
10 CFR 50.55a(b)(1)(iii)(C)
The NRC proposes to add a new
paragraph(b)(1)(iii)(C) to impose a
condition on the use of Subarticles NB–
3600, NC–3600, and ND–3600 of the
ASME B&PV Code, Section III when
applying the 2006 Addenda through the
2008 Addenda of Section III of the
ASME B&PV Code by requiring the
outer diameter-over-thickness ratio
(Do/t) to be less than or equal to 40. As
a result, licensees and applicants may
not apply Subparagraph NB–3683.2(C),
Note (1) to Table NB–3681(a)–1, and
Note (3) to Figures NC–3673.2(b)–1 and
ND–3673.2(b)–1.
10 CFR 50.55a(b)(1)(iv)
The NRC proposes to modify
paragraph (b)(1)(iv) to allow the use the
1994 Edition of NQA–1 when applying
the 2006 Addenda and later Editions
and Addenda of the ASME B&PV Code,
Section III.
10 CFR 50.55a(b)(1)(vii)
The NRC proposes to add a new
paragraph (b)(1)(vii) to prohibit the use
of paragraph NB–7742 when applying
the 2006 Addenda up to and including
the 2007 Edition and 2008 Addenda of
the ASME B&PV Code, Section III. As a
result, new Class 1 incompressiblefluid, pressure-relief valve designs must
be tested at the highest values of setpressure ranges as required by prior
editions and addenda of the ASME
B&PV Code, Section III.
ASME B&PV Code, Section XI
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
10 CFR 50.55a(b)(2)
The NRC proposes to revise the
introductory text to paragraph (b)(2) to
incorporate by reference only
Subsections IWA, IWB, IWC, IWD, IWE,
IWF, IWL, Mandatory and NonMandatory Appendices, of the 2005
Addenda through 2008 Addenda of
Section XI of the ASME B&PV Code,
with conditions, into 10 CFR 50.55a. It
would also be revised to make an
editorial change to the reference to
Section XI of the ASME B&PV Code.
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
10 CFR 50.55a(b)(2)(i)
The NRC proposes to delete the
requirements of current paragraph
(b)(2)(i) which address limitations on
specific editions and addenda.
Licensees are no longer using these
older editions (1974 and 1977 Editions)
and addenda of the ASME B&PV Code.
The requirements of current paragraph
(b)(2)(ii) which address pressureretaining welds in ASME Code Class 1
piping would be redesignated as
paragraph (b)(2)(i), with no change to
redesignated language.
10 CFR 50.55a(b)(2)(ii)
The NRC proposes to redesignate the
requirements of current paragraph
(b)(2)(vi), which address containment
inservice inspection requirements, as
paragraph (b)(2)(ii). This paragraph is
also modified to clarify the conditions
applicable to this paragraph.
10 CFR 50.55a(b)(2)(iii)
The NRC proposes to delete the
requirements of current paragraph
(b)(2)(iii) which address steam generator
tubing. The NRC proposes removal of
this condition because the condition is
redundant to the 1989 Edition through
the 2008 Addenda of Section XI. The
requirements of current paragraph
(b)(2)(vii) which address Section XI
references to OM Part 4, OM Part 6, and
OM Part 10 would be redesignated as
paragraph (b)(2)(iii), with no change to
redesignated language.
10 CFR 50.55a(b)(2)(iv)
The NRC proposes to redesignate the
requirements of current paragraph
(b)(2)(viii), which address the inservice
examination of concrete containments
in accordance with Subsection IWL of
the ASME B&PV Code, Section XI, as
paragraph (b)(2)(iv). This paragraph is
also modified so that the conditions in
redesignated paragraphs (b)(2)(iv)(F)
and (b)(2)(iv)(G) do not apply when
using the 2007 Edition with 2008
Addenda of the ASME B&PV Code,
Section XI.
10 CFR 50.55a(b)(2)(v)
The NRC proposes to redesignate the
requirements of current paragraph
(b)(2)(ix), which address the
examination of metal containments and
the liners of concrete containments in
accordance with Subsection IWE of the
ASME B&PV Code, Section XI, as
paragraph (b)(2)(v). This paragraph is
also modified so that the conditions in
redesignated paragraphs (b)(2)(v)(F),
(b)(2)(v)(G), (b)(2)(v)(H) and (b)(2)(v)(I)
do not apply when using the 2004
Edition with 2006 Addenda through the
2007 Edition with 2008 Addenda of
PO 00000
Frm 00024
Fmt 4701
Sfmt 4702
Subsection IWE of the ASME B&PV
Code, Section XI. Also, this paragraph is
modified so that the condition in
redesignated paragraph (b)(2)(v)(I)
would not apply when using the 2004
Edition, up to and including, the 2005
Addenda of Subsection IWE of the
ASME B&PV Code, Section XI.
10 CFR 50.55a(b)(2)(v)(J)
The NRC proposes to add a new
paragraph (b)(2)(v)(J) to address major
containment modifications as they
apply to Class MC and Class CC
containment structures and the use of
Article IWE–5000, of Subsection IWE
when applying the 2007 Edition up to
and including the 2008 Addenda of the
ASME B&PV Code, Section XI.
10 CFR 50.55a(b)(2)(vi)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(x), which address Quality
Assurance, as paragraph (b)(2)(vi), with
no change to the redesignated language.
10 CFR 50.55a(b)(2)(vii)
The NRC proposes to redesignate the
current paragraph (b)(2)(xi), which is
‘‘Reserved,’’ as paragraph (b)(2)(vii), and
that it remain reserved for possible
future use.
10 CFR 50.55a(b)(2)(viii)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xii), which address underwater
welding, as paragraph (b)(2)(viii), with
no change to the redesignated language.
10 CFR 50.55a(b)(2)(ix)
The NRC proposes to redesignate the
current paragraph (b)(2)(xiii), which is
‘‘Reserved,’’ as paragraph (b)(2)(ix), and
that it remain reserved for possible
future use.
10 CFR 50.55a(b)(2)(x)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xiv), which address Appendix VIII
personnel qualifications, as paragraph
(b)(2)(x), with no change to the
redesignated language.
10 CFR 50.55a(b)(2)(xi)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xv), which address Appendix VIII
specimen set and qualification
requirements, as paragraph (b)(2)(xi).
The paragraph would be modified by
limiting the use of the provisions
described in redesignated paragraphs
(b)(2)(xi)(A) through (b)(2)(xi)(M) to
licensees using editions and addenda of
the B&PV Code after the 2001 Edition
through the 2006 Addenda.
E:\FR\FM\04MYP3.SGM
04MYP3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
10 CFR 50.55a(b)(2)(xii)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xvi), which address Appendix VIII
single-sided ferritic-vessel and piping
and stainless steel piping examination,
as paragraph (b)(2)(xii), with no change
to the redesignated language.
10 CFR 50.55a(b)(2)(xiii)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xvii), which address
reconciliation of quality requirements,
as paragraph (b)(2)(xiii), with no change
to the redesignated language.
10 CFR 50.55a(b)(2)(xiv)(A)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xviii)(A), which address
certification of NDE personnel, as
paragraph (b)(2)(xiv)(A), with no change
to the redesignated language.
10 CFR 50.55a(b)(2)(xiv)(B)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xviii)(B), which address
Certification of NDE personnel, as
paragraph (b)(2)(xiv)(B). In addition, the
requirements would be revised such
that the condition would not apply to
the 2007 Edition through the 2008
Addenda of Section XI.
10 CFR 50.55a(b)(2)(xiv)(C)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xviii)(C), which address
certification of NDE personnel, as
paragraph (b)(2)(xiv)(C). In addition, the
requirements would be revised such
that the current conditions on the
qualification of VT–3 examination
personnel would not apply to the 2005
Addenda through the 2008 Addenda of
Section XI.
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
10 CFR 50.55a(b)(2)(xv)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xix), which address substitution
of alternative methods, as paragraph
(b)(2)(xv). In addition, the requirements
would be revised so the current
conditions for the substitution of
alternative examination methods in that
paragraph would not apply when using
the 2005 Addenda through the 2008
Addenda. The paragraph would also be
revised to impose the condition that
paragraphs IWA–4520(b)(2) and IWA–
4521 of the 2007 Edition of Section XI,
Division 1, with 2008 Addenda, are not
approved for use.
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
10 CFR 50.55a(b)(2)(xvi)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xx), which address system leakage
tests, as paragraph (b)(2)(xvi), with no
change to the redesignated language.
24347
5242 for the 2007 Edition and later
addenda of Section XI of the ASME
B&PV Code.
10 CFR 50.55a(b)(2)(xvii)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xxi), which address Table IWB–
2500–1 examination requirements, as
paragraph (b)(2)(xvii), with no change to
the redesignated language.
10 CFR 50.55a(b)(2)(xxiv)
The NRC proposes to add a new
paragraph (b)(2)(xxiv) which would
condition the use of the fatigue crack
growth rate calculation for subsurface
flaws defined in paragraph A–4300(b)(1)
of Section XI, Nonmandatory Appendix
A when the ratio of the minimum cyclic
stress to the maximum cyclic stress (R)
is less than zero.
10 CFR 50.55a(b)(2)(xviii)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xxii), which address surface
examination, as paragraph (b)(2)(xviii),
with no change to the redesignated
language.
10 CFR 50.55a(b)(2)(xxv)
The NRC proposes to add a new
paragraph (b)(2)(xxv) which would
condition the use of ASME B&PV Code,
Section XI, Non-Mandatory Appendix E,
by establishing that Section E–1200 is
not acceptable for use.
10 CFR 50.55a(b)(2)(xix)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xxiii), which address evaluation
of thermally cut surfaces, as paragraph
(b)(2)(xix), with no change to the
redesignated language.
10 CFR 50.55a(b)(2)(xx)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xxiv), which address
incorporation of the performance
demonstration initiative and addition of
ultrasonic examination criteria, as
paragraph (b)(2)(xx). In addition, the
requirements would be revised so that
the current condition would not apply
when using the 2007 Edition through
the 2008 Addenda of Section XI of the
ASME B&PV Code.
10 CFR 50.55a(b)(2)(xxi)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xxv), which address mitigation of
defects by modification, as paragraph
(b)(2)(xxi), with no change to the
redesignated language.
10 CFR 50.55a(b)(2)(xxvi)
The NRC proposes to add a new
paragraph (b)(2)(xxvi) which would
condition the use of ASME B&PV Code,
Section XI, Non-Mandatory Appendix R
to require licensees to submit an
alternative in accordance with
paragraph (a)(3) and obtain NRC
authorization of the proposed
alternative prior to implementing
Appendix R, RI–ISI programs.
ASME OM Code
10 CFR 50.55a(b)(3)
The NRC proposes to revise the
introductory text of paragraph (b)(3) to
require that the 2004 Edition with the
2005 and 2006 Addenda of the ASME
OM Code be used during the initial 120month IST interval under paragraph
(f)(4)(i) and during mandatory 120month IST program updates under
paragraph (f)(4)(ii). The proposed
revision would also allow users to
voluntarily update their IST programs to
the 2004 Edition with the 2005 and
2006 Addenda of the ASME OM Code
under paragraph (f)(4)(iv).
10 CFR 50.55a(b)(2)(xxii)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xxvi), which address pressure
testing of Class 1, 2, and 3 mechanical
joints, as paragraph (b)(2)(xxii), with no
change to the redesignated language.
10 CFR 50.55a(b)(3)(v)
The NRC proposes to revise paragraph
(b)(3)(v) to require that the provisions in
Subsection ISTD of the ASME OM Code
be used for the inservice examination
and testing of snubbers when using the
2006 Addenda and later editions and
addenda of Section XI.
10 CFR 50.55a(b)(2)(xxiii)
The NRC proposes to redesignate the
requirements in current paragraph
(b)(2)(xxvii), which address removal of
insulation, as paragraph (b)(2)(xxiii). In
addition, the requirements would be
revised to add a condition to refer to
paragraph IWA–5241 instead of IWA–
10 CFR 50.55a(b)(3)(vi)
The NRC proposes to revise paragraph
(b)(3)(vi) to require that the current
condition for exercising manual valves
continue to apply when using the 1999
through 2005 Addenda of the ASME
OM Code. This condition would not
apply to the 2006 Addenda and later
PO 00000
Frm 00025
Fmt 4701
Sfmt 4702
E:\FR\FM\04MYP3.SGM
04MYP3
24348
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
editions and addenda of the ASME OM
Code.
(g)(6)(ii)(E)(3) to update the requirement
to implement Code Case N–722–1.
Reactor Coolant Pressure Boundary,
Quality Group B Components and
Quality Group C Components
10 CFR 50.55a(g)(6)(ii)(F)
The NRC proposes to add a new
paragraph (g)(6)(ii)(F), ‘‘Inspection
Requirements for Class 1 Pressurized
Water Reactor Piping and Vessel Nozzle
Butt Welds,’’ to require licensees to
implement ASME Code Case N–770,
with conditions.
The NRC proposes to revise
paragraphs (c)(3), (d)(2), and (e)(2) to
replace ‘‘but—’’ with ‘‘subject to the
following conditions’’ at the end of the
introductory text to the paragraphs for
clarity.
Inservice Testing Requirements
10 CFR 50.55a(f)(5)(iv)
The NRC proposes to revise paragraph
(f)(5)(iv) to clarify that licensees are
required to submit requests for relief
based on impracticality within 12
months after the expiration of the IST
interval for which relief is being sought.
Inservice Inspection Requirements
10 CFR 50.55a(g)(2), (g)(3)(i), (g)(3)(ii),
the Introductory Text of (g)(4), (g)(4)(i),
and (g)(4)(ii)
The NRC proposes to revise
paragraphs (g)(2), (g)(3)(i), (g)(3)(ii),
(g)(4)(i) and (g)(4)(ii) to require that the
provisions in Subsection ISTD of the
ASME OM Code, and the optional
ASME code cases listed in Regulatory
Guide 1.192, be used for the ISI of
snubbers. The introductory text of
paragraph (g)(4) would be revised to
require that licensees use the provisions
for examination and testing snubbers in
Subsection ISTD of the ASME OM Code.
10 CFR 50.55a(g)(4)(iii)
The NRC proposes to revise paragraph
(g)(4)(iii) to provide the proper
references to Section XI, Table IWB–
2500–1, ‘‘Examination Category B–J,’’
Item Numbers B9.20, B9.21 and B9.22.
10 CFR 50.55a(g)(5)(iii)
The NRC proposes to revise paragraph
(g)(5)(iii) by adding a sentence to clarify
that a request for relief must be
submitted to the NRC no later than 12
months after the examination has been
attempted during a given ISI interval
and the ASME Code requirement
determined to be impractical.
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
10 CFR 55a(g)(5)(iv)
The NRC proposes to revise paragraph
(g)(5)(iv) to clarify that licensees are
required to submit requests for relief
based on impracticality within 12
months after the end of the ISI interval
for which relief is being sought.
10 CFR 50.55a(g)(6)(ii)(E)(1) through
(g)(6)(ii)(E)(3)
The NRC proposes to revise
paragraphs (g)(6)(ii)(E)(1) through
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
Footnote 1 to 10 CFR 50.55a(g)(6)(ii)(E)
The NRC proposes to revise footnote
1 to paragraph (g)(6)(ii)(E) to clarify that
for inspections conducted once per
interval, the portion of welds to be
inspected in the remaining portion of
the interval be based on rules already
established by the ASME B&PV Code.
Substitution of the Term ‘‘Condition’’ in
10 CFR 50.55a
The NRC proposes to substitute the
words ‘‘limitation(s),’’ ‘‘modification(s),’’
and ‘‘provision(s)’’ with the word
‘‘condition(s)’’ throughout 10 CFR
50.55a, as shown in Table 1 of this
document, for consistency.
V. Generic Aging Lessons Learned
Report
In September 2005, the NRC issued
‘‘Generic Aging Lessons Learned (GALL)
Report,’’ NUREG–1801, Volumes 1 and
2, Revision 1, for applicants to use in
preparing their license renewal
applications. The GALL Report
evaluates existing programs and
documents the bases for determining
when existing programs, without change
or augmentation, are adequate for aging
management compliance in the license
renewal rule, as given in 10 CFR
54.21(a)(3). In Revision 1 of the GALL
Report, editions of the ASME B&PV
Code, Section XI, Subsections IWB,
IWC, IWD, IWE, IWF, and IWL from the
1995 Edition through the 2001 Edition,
inclusive of the 2003 Addenda, were
evaluated and were found to be
acceptable editions and addenda for
complying with the requirements of 10
CFR 54.21(a)(3), unless specifically
noted in specific sections of the GALL
Report.
In the GALL Report, Section XI.M1,
‘‘ASME Section XI Inservice Inspection,
Subsections IWB, IWC, and IWD;’’
Section XI.S1, ‘‘ASME Section XI,
Subsection IWE;’’ Section XI.S2,’’ASME
Section XI, Subsection IWL;’’ and
Section XI.S3, ‘‘ASME Section XI,
Subsection IWF’’ describe the evaluation
and technical bases for determining the
adequacy of these ASME Code
subsections. In addition, many other
aging management programs (AMPs) in
the GALL report rely in part, but to a
PO 00000
Frm 00026
Fmt 4701
Sfmt 4702
lesser degree, on the requirements in the
ASME B&PV Code, Section XI.
The NRC has evaluated Subsections
IWB, IWC, IWD, IWE, IWF, and IWL of
Section XI of the ASME B&PV Code,
2004 Edition with the 2005 Addenda
through the 2007 Edition with the 2008
Addenda as part of the § 50.55a
amendment process to determine if the
conclusions of the GALL Report also
apply to AMPs that rely upon the ASME
B&PV Code editions and addenda that
are proposed to be incorporated by
reference into § 50.55a by this rule. The
NRC finds that the 2004 Edition,
inclusive of the 2005 and 2006
Addenda, and the 2007 Edition,
inclusive of the 2008 Addenda of
Sections XI of the ASME B&PV Code,
Subsections IWB, IWC, IWD, IWE, IWF,
and IWL, as subject to the conditions of
this rule, are acceptable to be adopted
as AMPs for license renewal and the
conclusions of the GALL Report remain
valid, except where specifically noted
and augmented in the GALL Report.
Accordingly, an applicant for license
renewal may use Subsections IWB, IWC,
IWD, IWE, IWF, and IWL of Section XI
of the 2004 Edition with the 2005 and
2006 Addenda through the 2007 Edition
with the 2008 Addenda of the ASME
B&PV Code, subject to conditions
proposed in this rule, as acceptable
alternatives to the requirements of the
1995 Edition through the 2001 Edition
up to and including the 2003 Addenda
of the ASME B&PV Code, Section XI,
referenced in Revision 1 of the GALL
Report in its plant-specific license
renewal application. Similarly, a
licensee approved for license renewal
that relied on the GALL AMPs may use
Subsections IWB, IWC, IWD, IWE, IWF,
and IWL of Section XI of the 2004
Edition with the 2005 Addenda and the
2006 Addenda through the 2007 Edition
with the 2008 Addenda of the ASME
B&PV Code as acceptable alternatives to
the AMPs described in the Revision 1 of
the GALL report. However, a licensee
must assess and follow applicable NRC
requirements with regard to changes to
its licensing basis.
The NRC, however, notes that the
GALL Report includes Subsection IWE
and IWL AMPs that are evaluated based
on the requirements in the 1992 Edition
and 2001 Edition through the 2003
Addenda of Section XI of the ASME
B&PV Code. Also, some of the
terminology used and some details in
these AMPs are based on the 1992
Edition. Since these AMPs in Revision
1 of the GALL report have a specific
ASME B&PV Code year in the
description of the AMP or in one or
more of the ten elements, the details in
the AMP based on a specific ASME
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
B&PV Code edition may not be accurate
for other editions.
Revision 1 of the GALL report
includes AMPs that are based on the
requirements in the 1995 Edition
through the 2003 Addenda of Section XI
of the ASME B&PV Code but in which
the AMPs may recommend additional
augmentation of the Code requirements
in order to achieve aging management
for license renewal. The technical or
regulatory aspects of the AMPs, for
which augmentation is recommended,
also apply if using the 2004 Edition
inclusive of the 2005 Addenda, or the
2007 Edition, inclusive of the 2008
Addenda, of Section XI of the ASME
B&PV Code to meet the requirements of
10 CFR 54.21(a)(3). A license renewal
applicant may either augment its AMPs
in these areas, as described in the GALL
report, or propose alternatives
(exceptions) for the NRC to review as
part of a plant-specific program element
justification for its AMP.
For PWRs, the NRC currently
provides license renewal guidance for
augmented inspections of PWR upper
reactor vessel heads and their
penetration nozzles in GALL AMP
XI.M11, ‘‘Nickel-Alloy Nozzles and
Penetrations’’ and Alloy 600 Line items.
As part of this AMP, PWR upper reactor
vessel heads and their penetrations are
discussed in GALL AMP XI.M11A,
‘‘Nickel-Alloy Penetration Nozzles
Welded to the Upper Reactor Vessel
Closure Heads of Pressurized Water
Reactors (PWR Only).’’ The current
program elements and aging
management recommendations in GALL
AMP XI.M11A are based on the
augmented inspection requirements in
the First Revised Order EA–03–009,
‘‘Issuance of First Revised Order (EA–
03–009) Establishing Interim Inspection
Requirements for Reactor Pressure
Vessel Heads at Pressurized Water
Reactors.’’ For licensees that have been
granted a renewed operating license and
have committed to an AMP that is based
on both conformance with GALL AMP
XI.M11A and compliance with First
Revised Order EA–03–009, the licensees
may update the program elements of
their AMP to reflect compliance with
the proposed requirements in 10 CFR
50.55a(g)(6)(ii)(D) and (g)(6)(ii)(E)
without having to identify an exception
to GALL AMP XI.M11A. For new or
current license renewal applicants, they
may reference conformance with GALL
AMP XI.M11 and compliance with the
proposed augmented inspection
requirements in paragraphs 10 CFR
50.55a(g)(6)(ii)(D), (g)(6)(ii)(E) and
(g)(6)(ii)(F) without the need for taking
an exception to the program elements in
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
GALL AMP XI.M11 or GALL AMP
XI.M11A.
VI. Specific Request for Comments
The NRC requests public comment on
the changes to Code editions and
addenda, and Code Cases N–722–1 and
N–770, as part of this proposed
rulemaking. The NRC also requests
comments on specific NRC questions
associated with its implementing 10
CFR 50.55a rulemaking process
improvements to make incorporating by
reference ASME B&PV Code editions
and addenda into 10 CFR 50.55a more
predictable and consistent. The primary
process improvement is to have a 2-year
rulemaking cycle consisting of 1-year to
develop an adequate Regulatory Basis
and send a proposed rule to NRC
management for approval, and an
additional 1-year from publishing the
proposed rulemaking in the Federal
Register to publishing the final rule
(this includes the public comment
period). This 2-year rulemaking cycle is
to remain consistent, regardless of the
number of code editions or addenda
incorporated into 10 CFR 50.55a in the
rulemaking. This should make
publishing these rulemakings more
consistent. However, this does not help
users of the ASME B&PV Code predict
when the NRC will incorporate new
editions and addenda of the ASME Code
into 10 CFR 50.55a as that would
depend on when the NRC begins each
2-year rulemaking cycle.
As previously mentioned, the ASME
issues new editions of the ASME B&PV
Code every 3 years, issues addenda to
the editions yearly except in years when
a new edition is issued, and periodically
publishes new editions and addenda of
the ASME OM Code. However, the NRC
understands that ASME is re-evaluating
this process. The NRC could begin its
rulemaking cycle any time (subject to
availability of resources and other
constraints) after the ASME publishes
its code editions and addenda.
However, the NRC is trying to determine
how often it should publish its ASME
B&PV Code rulemakings to suit the
largest number of users. Some users
have told the NRC that they prefer to
have code rulemakings published every
2 years, while others have indicated that
they prefer a 3-year interval.
Accordingly, the NRC is requesting
comments on the following questions:
1. What should the scope of the
ASME B&PV Code edition and addenda
rulemaking be (i.e., how many editions
and addenda should be compiled into a
single rulemaking)?
2. What should the frequency of
ASME B&PV Code edition and addenda
rulemaking be (i.e., how often should
PO 00000
Frm 00027
Fmt 4701
Sfmt 4702
24349
the NRC incorporate by reference Code
editions and addenda into 10 CFR
50.55a)?
3. In what ways should the NRC
communicate the scope, schedule for
publishing the rulemakings in the
Federal Register, and status of 10 CFR
50.55a rulemakings to external users?
The NRC will review the responses to
these questions to help determine
agency positions on the scope,
frequency, and methods to
communicate 10 CFR 50.55a
rulemakings.
VII. Voluntary Consensus Standards
The National Technology Transfer
and Advancement Act of 1995, Public
Law 104–113, requires agencies to use
technical standards that are developed
or adopted by voluntary consensus
standards bodies instead of governmentunique standards, unless the use of such
a standard is inconsistent with
applicable law or is otherwise
impractical. Public Law.104–113
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. The law does not prohibit
an agency from generally 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 which are not
acceptable to the agency.
The NRC is proposing to amend its
regulations to incorporate by reference
more recent editions and addenda of
Sections III and XI of the ASME B&PV
Code and ASME OM Code, for
construction, in-service inspection, and
in-service testing of nuclear power plant
components. ASME B&PV and OM
Codes are national 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. In an SRM dated September
10, 1999, the Commission indicated its
intent that a rulemaking identify all
parts of an adopted voluntary consensus
standard that are not adopted and to
justify not adopting such parts. The
parts of the ASME B&PV Code and OM
Code that the NRC proposes not to
adopt, or to partially adopt, are
E:\FR\FM\04MYP3.SGM
04MYP3
24350
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
previously identified in Section II and
in the draft regulatory and backfit
analysis. The parts of the ASME B&PV
Code, OM Code, and Code Cases N–
722–1 and N–770 that the NRC proposes
to be conditionally acceptable, along
with the conditions under which they
may be applied, are also identified in
Section II and in the draft regulatory
and backfit analysis. If the NRC did not
conditionally accept ASME editions,
addenda, and code cases, it would
disapprove these entirely. The effect
would be that licensees would need to
submit a larger number of relief
requests, which would be an
unnecessary additional burden for both
the licensee and the NRC. For these
reasons, the treatment of ASME Code
editions and addenda, and code cases
and any conditions proposed to be
placed on them in this proposed rule
does not conflict with any policy on
agency use of consensus standards
specified in OMB Circular A–119.
The justification for not adopting
parts of, or conditioning, the ASME
B&PV Code, OM Code, and Code Cases
N–722–1 and N–770 as set forth in these
statements of consideration and the
draft regulatory and backfit analysis for
this proposed rule, satisfy the
requirements of Section 12(d)(3) of
Public Law 104–113, Office of
Management and Budget (OMB)
Circular A–119, and the Commission’s
direction in the SRM dated September
10, 1999. In accordance with the
National Technology Transfer and
Advancement Act of 1995 and OMB
Circular A–119, the NRC is requesting
public comment regarding whether
other national or international
consensus standards could be endorsed
as an alternative to the ASME B&PV
Code and the ASME OM Code.
VIII. Finding of No Significant
Environmental Impact: Environmental
Assessment
This proposed action is in accordance
with the NRC’s policy to incorporate by
reference in 10 CFR 50.55a new editions
and addenda of the ASME B&PV 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. ASME Codes are
national voluntary consensus standards
and are required by the National
Technology Transfer and Advancement
Act of 1995, Public Law 104–113, 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 government agencies to
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
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, if adopted,
would not be a major Federal action
significantly affecting the quality of the
human environment and, therefore, an
environmental impact statement is not
required. The proposed rulemaking will
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
estimates the radiological dose to plant
personnel performing the inspections
required by Code Case N–770 would be
about 3 rems per plant over a 10-year
interval, and a one-time exposure for
mitigating welds of about 30 rems per
plant. As required by 10 CFR part 20,
and in accordance with current plant
procedures and radiation protection
programs, plant radiation protection
staff will continue monitoring dose rates
and would make adjustments in
shielding, access requirements,
decontamination methods, and
procedures as necessary to minimize the
dose to workers. The increased
occupational dose to individual workers
stemming from the Code Case N–770
inspections must be maintained within
the limits of 10 CFR part 20 and as low
as reasonably achievable. Therefore, the
NRC concludes that the increase in
occupational exposure would not be
significant. The proposed rulemaking
does not involve non-radiological plant
effluents and has no other
environmental impact. Therefore, no
significant non-radiological impacts are
associated with the proposed action.
The determination of this draft
environmental assessment is that there
will be no significant off-site impact to
the public from this action. However,
the NRC is seeking public comment of
the draft environmental assessment.
Comments on any aspect of the
environmental assessment may be
submitted to the NRC as indicated
under the ADDRESSES heading of this
document.
IX. Paperwork Reduction Act
Statement
The public burden for this
information collection is estimated to be
a reduction of 120 hours, which is
PO 00000
Frm 00028
Fmt 4701
Sfmt 4702
insignificant. Because the burden for
this information collection is
insignificant, Office of Management and
Budget (OMB) clearance is not required.
Existing requirements were approved by
the Office of Management and Budget,
control number 3150–0011.
This proposed rule would impose
ASME Code Cases N–722–1 and N–770
which results in licensees having to
revise their ISI programs and
procedures. The NRC estimates that the
burden of preparing new ISI program
content and procedures is 40 personhours per plant over the next 3 years.
This one-time burden affects 69 PWR
plants, so the total burden on an annual
basis would be 920 hours. However,
there are a number of changes in the
ASME Code edition and addenda
associated with this proposed
rulemaking related to qualification of
inspections in Section XI, Appendix
VIII. These changes would result in a
one-time reduction of about 5 relief
requests per plant (104 PWR and BWR
plants) per 10-year ISI interval that
would have otherwise been necessary.
Assuming 20 hours of licensee time to
prepare each relief request results in a
one-time paperwork reduction of about
1,040 hours on an annual basis. Overall,
the burden on licensees for information
collection for this proposed rulemaking
is reduced by 120 hours.
The NRC 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 burden 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
information collection be minimized,
including the use of automated
collection techniques?
A copy of the NRC Form 670,
‘‘Information Required for Making an
Insignificant Burden Determination To
Support a Decision That OMB Clearance
Is Not Required,’’ may be viewed free of
charge at the NRC Public Document
Room, One White Flint North, 11555
Rockville Pike, Room O–1 F21,
Rockville, MD 20852. The NRC Form
670 and rule are available at the NRC
worldwide Web site: https://
www.nrc.gov/public-involve/
doccomment/omb/ for 60
days after the signature date of this
notice.
E:\FR\FM\04MYP3.SGM
04MYP3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
Send comments on any aspect of
these proposed information collections,
including suggestions for reducing the
burden and on the above issues, by June
3, 2010 to the Records and FOIA/
Privacy Services Branch (T–5 F52), U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, or by
Internet electronic mail to
INFOCOLLECTS.RESOURCE@NRC.GOV
and to Christine J. Kymn, the Desk
Officer, Office of Information and
Regulatory Affairs, NEOB–10202 (3150–
0011), Office of Management and
Budget, Washington, DC 20503.
Comments received after this date will
be considered if it is practical to do so,
but assurance of consideration cannot
be given to comments received after this
date. You may also e-mail comments to
ckym@omb.eop.gov or comment by
telephone at 202–395–4638.
List of Subjects in 10 CFR Part 50
Antitrust, Classified information,
Criminal penalties, Fire protection,
Intergovernmental relations, Nuclear
power plants and reactors, Radiation
protection, Reactor siting criteria,
Reporting and recordkeeping
requirements.
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.
Public Protection Notification
Authority: Secs. 102, 103, 104, 105, 161,
182, 183, 186, 189, 68 Stat. 936, 937, 938,
948, 953, 954, 955, 956, as amended, sec.
234, 83 Stat. 444, as amended (42 U.S.C.
2132, 2133, 2134, 2135, 2201, 2232, 2233,
2236, 2239, 2282); secs. 201, as amended,
202, 206, 88 Stat. 1242, as amended, 1244,
1246 (42 U.S.C. 5841, 5842, 5846); sec. 1704,
112 Stat. 2750 (44 U.S.C. 3504 note); Energy
Policy Act of 2005, Pub. L. 109–58, 119 Stat.
194 (2005).
Section 50.7 also issued under Pub. L. 95–
601, sec. 10, 92 Stat. 2951 as amended by
Pub. L. 102–486, sec. 2902, 106 Stat. 3123 (42
U.S.C. 5841), Section 50.10 also issued under
secs. 101, 185, 68 Stat. 955, as amended (42
U.S.C. 2131, 2235); sec. 102, Pub. L. 91–190,
83 Stat. 853 (42 U.S.C. 4332). Sections 50.13,
50.54(dd), and 50.103 also issued under sec.
108, 68 Stat. 939, as amended (42 U.S.C.
2138).
Sections 50.23, 50.35, 50.55, and 50.56 also
issued under sec. 185, 68 Stat. 955 (42 U.S.C.
2235). Sections 50.33a, 50.55a and Appendix
Q also issued under sec. 102, Pub. L. 91–190,
83 Stat. 853 (42 U.S.C. 4332). Sections 50.34
and 50.54 also issued under sec. 204, 88 Stat.
1245 (42 U.S.C. 5844). Sections 50.58, 50.91,
and 50.92 also issued under Pub. L. 97–415,
96 Stat. 2073 (42 U.S.C. 2239). Section 50.78
also issued under sec. 122, 68 Stat. 939 (42
U.S.C. 2152). Sections 50.80–50.81 also
issued under sec. 184, 68 Stat. 954, as
amended (42 U.S.C. 2234). Appendix F also
issued under sec. 187, 68 Stat. 955 (42 U.S.C.
2237).
The NRC may not conduct or sponsor,
and a person is not required to respond
to, a request for information or an
information collection unless the
requesting document displays a
currently valid OMB control number.
X. Regulatory and Backfit Analysis
The NRC has prepared a Regulatory
and Backfit Analysis on this proposed
rule. The analysis is available for review
as indicated in Section I, ‘‘Submitting
Comments and Accessing Information,’’
of this document.
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
XI. Regulatory Flexibility Certification
Under the Regulatory Flexibility Act
of 1980 (5 U.S.C. 605(b)), the NRC
certifies that this proposed rule would
not impose a significant economical
impact on a substantial number of small
entities. This proposed rule would affect
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 (10
CFR 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.
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
PART 50—DOMESTIC LICENSING OF
PRODUCTION AND UTILIZATION
FACILITIES
1. The authority citation for part 50
continues to read as follows:
2. In § 50.55a:
a. Revise paragraph (a), the
introductory text of paragraphs (b) and
(b)(1), paragraphs (b)(1)(ii), (b)(1)(iii),
and (b)(1)(iv); and add paragraph
(b)(1)(vii);
b. Revise paragraph (b)(2);
c. Revise the introductory text of
paragraph (b)(3), paragraphs (b)(3)(v),
(b)(3)(vi), (c)(3), (d)(2), (e)(2), (f)(2),
(f)(3)(v), (f)(4), (f)(5)(iv), (g)(2), (g)(3),
(g)(4), (g)(5)(iii), (g)(5)(iv), (g)(6)(ii)(B),
(g)(6)(ii)(E)(1), (g)(6)(ii)(E)(2), and
(g)(6)(ii)(E)(3);
PO 00000
Frm 00029
Fmt 4701
Sfmt 4702
24351
d. Add paragraph (g)(6)(ii)(F); and
e. Revise footnote 1 to this section
that appears after paragraph (h)(3) to
read as follows:
§ 50.55a
Codes and standards.
*
*
*
*
*
(a) Quality standards, ASME Codes
and IEEE standards, and alternatives.
(1) Structures, systems, and
components must be designed,
fabricated, erected, constructed, tested,
and inspected to quality standards
commensurate with the importance of
the safety function to be performed.
(2) Systems and components of
boiling and pressurized water-cooled
nuclear power reactors must meet the
requirements of the ASME Boiler and
Pressure Vessel Code specified in
paragraphs (b), (c), (d), (e), (f), and (g) of
this section. Protection systems of
nuclear power reactors of all types must
meet the requirements specified in
paragraph (h) of this section.
(3) Proposed alternatives to the
requirements of paragraphs (c), (d), (e),
(f), (g), and (h) of this section, or
portions thereof, may be used when
authorized by the Director, Office of
Nuclear Reactor Regulation, or Director,
Office of New Reactors, as appropriate.
Any proposed alternatives must be
submitted and authorized prior to
implementation. The applicant or
licensee shall demonstrate that:
(i) The proposed alternatives would
provide an acceptable level of quality
and safety; or
(ii) Compliance with the specified
requirements of this section would
result in hardship or unusual difficulty
without a compensating increase in the
level of quality and safety.
(b) Standards approved for
incorporation by reference. The
following standards have been approved
for incorporation by reference by the
Director of the Federal Register pursuant
to 5 U.S.C. 552(a) and 1 CFR Part 51:
Section III, Division 1 (excluding Nonmandatory Appendices) and Section XI,
Division 1, of the ASME Boiler and
Pressure Vessel Code, and the ASME
Code for Operation and Maintenance of
Nuclear Power Plants, which are
referenced in paragraphs (b)(1), (b)(2),
and (b)(3) of this section; NRC
Regulatory Guide 1.84, Revision 34,
‘‘Design, Fabrication, and Materials
Code Case Acceptability, ASME Section
III’’ (October 2007), NRC Regulatory
Guide 1.147, Revision 15, ‘‘Inservice
Inspection Code Case Acceptability,
ASME Section XI, Division 1’’ (October
2007), and Regulatory Guide 1.192,
‘‘Operation and Maintenance Code Case
Acceptability, ASME OM Code’’ (June
2003), which list ASME Code cases that
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
24352
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
the NRC has approved in accordance
with the requirements in paragraphs
(b)(4), (b)(5), and (b)(6) of this section;
ASME Code Case N–722–1, ‘‘Additional
Examinations for PWR Pressure
Retaining Welds in Class 1 Components
Fabricated with Alloy 600/82/182
Materials, Section XI, Division 1’’
(ASME Approval Date: January 26,
2009), which has been approved by the
NRC with conditions in accordance
with the requirements in paragraph
(g)(6)(ii)(E) of this section; ASME Code
Case N–729–1, ‘‘Alternative
Examination Requirements for PWR
Reactor Vessel Upper Heads With
Nozzles Having Pressure-Retaining
Partial-Penetration Welds, Section XI,
Division 1’’ (ASME Approval Date:
March 28, 2006), which has been
approved by the NRC with conditions in
accordance with the requirements in
paragraph (g)(6)(ii)(D) of this section;
and ASME Code Case N–770,
‘‘Alternative Examination Requirements
and Acceptance Standards for Class 1
PWR Piping and Vessel Nozzle Butt
Welds Fabricated with UNS N06082 or
UNS W86182 Weld Filler Material With
or Without Application of Listed
Mitigation Activities, Section XI,
Division 1,’’ (ASME Approval Date:
January 26, 2009), which has been
approved by the NRC with conditions in
accordance with the requirements in
paragraph (g)(6)(ii)(F) of this section.
Copies of the ASME Boiler and Pressure
Vessel Code, the ASME Code for
Operation and Maintenance of Nuclear
Power Plants, ASME Code Case N–722–
1, ASME Code Case N–729–1, and
ASME Code Case N–770 may be
purchased from the American Society of
Mechanical Engineers, Three Park
Avenue, New York, NY 10016 or
through the Web https://www.asme.org/
Codes/. Single copies of NRC Regulatory
Guides 1.84, Revision 34; 1.147,
Revision 15; and 1.192 may be obtained
free of charge by writing the
Reproduction and Distribution Services
Section, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; or by fax to 301–415–2289; or by
e-mail to
DISTRIBUTION.RESOURCE@nrc.gov.
Copies of the ASME Codes and NRC
Regulatory Guides incorporated by
reference in this section may be
inspected at the NRC Technical Library,
Two White Flint North, 11545 Rockville
Pike, Rockville, MD 20852–2738 or call
301–415–5610, or at the National
Archives and Records Administration
(NARA). For information on the
availability of this material at NARA,
call 202–741–6030, or go to: https://
VerDate Mar<15>2010
22:19 May 03, 2010
Jkt 220001
www.archives.gov/federal-register/cfr/
ibr-locations.html.
(1) As used in this section, references
to Section III refer to Section III of the
ASME Boiler and Pressure Vessel Code,
and include the 1963 Edition through
1973 Winter Addenda, and the 1974
Edition (Division 1) through the 2008
Addenda (Division 1), subject to the
following conditions:
*
*
*
*
*
(ii) Weld leg dimensions. When
applying the 1989 Addenda through the
latest edition and addenda incorporated
by reference in paragraph (b)(1) of this
section, applicants or licensees may not
apply subparagraphs NB–3683.4(c)(1)
and NB–3683.4(c)(2) or Footnote 11
from the 1989 Addenda through the
2003 Addenda, or Footnote 13 from the
2004 Edition through the 2008 Addenda
to Figures NC–3673.2(b)–1 and ND–
3673.2(b)–1 for welds with leg size less
than 1.09 tn.
(iii) 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 2006 Addenda incorporated by
reference in paragraph (b)(1) of this
section except that Subarticle NB–3200
in the 2004 Edition through the 2008
Addenda may be used by applicants and
licensees subject to the condition in
paragraph (b)(1)(iii)(B) 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
2008 Addenda subject to the conditions
of this paragraph corresponding to these
subarticles.
(A) For Class 1 elbows and tees of
ferritic steel materials operating at
temperatures above 300 °F, the
allowable B2’ index defined in
Subparagraph NB–3656(b)(3) shall be no
less than 0.75B2 from Table NB–
3681(A)–1.
(B) 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.
(C) Do/t must not be greater than 40,
where Do is the outer diameter of pipe,
and t is the nominal pipe thickness.
Subparagraph NB–3683.2(C), Note (1) to
Table NB–3681(a)–1, Note (3) to Figures
NC–3673.2(b)–1 and ND–3673.2(b)–1
may not be applied.
PO 00000
Frm 00030
Fmt 4701
Sfmt 4702
(iv) Quality assurance. When
applying editions and addenda later
than the 1989 Edition of Section III, the
requirements of NQA–1, ‘‘Quality
Assurance Requirements for Nuclear
Facilities,’’ 1986 Edition through the
1994 Edition, are acceptable for use,
provided that the edition and addenda
of NQA–1 specified in NCA–4000 is
used in conjunction with the
administrative, quality, and technical
provisions contained in the edition and
addenda of Section III being used.
*
*
*
*
*
(vii) Capacity certification and
demonstration of function of
incompressible-fluid pressure-relief
valves. When applying the 2006
Addenda through the 2008 Addenda,
applicants or licensees may not apply
paragraph NB–7742 of the ASME B&PV
Code, Section III. New Class 1
incompressible-fluid, pressure-relief
valve designs must be tested at the
highest values of set-pressure ranges as
required by prior editions and addenda
of the ASME B&PV Code, Section III.
(2) As used in this section, references
to Section XI refer to Section XI,
Division 1, of the ASME Boiler and
Pressure Vessel Code, and include the
1970 Edition though the 1976 Winter
Addenda, and the 1977 Edition through
the 2007 Edition with the 2008
Addenda, subject to the following
conditions:
(i) Pressure-retaining welds in ASME
Code Class 1 piping (applies to Table
IWB–2500 and IWB–2500–1 and
Category B–J). If the facility’s
application for a construction permit
was docketed prior to July 1, 1978, the
extent of examination for Code Class 1
pipe welds may be determined by the
requirements of Table IWB–2500 and
Table IWB–2600 Category B–J of Section
XI of the ASME B&PV Code in the 1974
Edition and addenda through the
Summer 1975 Addenda or other
requirements the NRC may adopt.
(ii) Effective edition and addenda of
Subsection IWE and Subsection IWL,
Section XI. Applicants or licensees may
use either the 1992 Edition with the
1992 Addenda or the 1995 Edition with
the 1996 Addenda of Subsection IWE
and Subsection IWL as conditioned by
the requirements in paragraphs (b)(2)(iv)
and (b)(2)(v) of this section when
implementing the initial 120-month
inspection interval for the containment
inservice inspection requirements of
this section. Successive 120-month
interval updates must be implemented
in accordance with paragraph (g)(4)(ii)
of this section.
(iii) Section XI References to OM Part
4, OM Part 6 and OM Part 10 (Table
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
IWA–1600–1). When using Table IWA–
1600–1, ‘‘Referenced Standards and
Specifications,’’ in the Section XI,
Division 1, 1987 Addenda, 1988
Addenda, or 1989 Edition, the specified
‘‘Revision Date or Indicator’’ for ASME/
ANSI OM Part 4, ASME/ANSI Part 6,
and ASME/ANSI Part 10 must be the
OMa–1988 Addenda to the OM–1987
Edition. These requirements have been
incorporated into the OM Code which is
incorporated by reference in paragraph
(b)(3) of this section.
(iv) Examination of concrete
containments. Applicants or licensees
applying Subsection IWL, 1992 Edition
with the 1992 Addenda, shall apply
paragraphs (b)(2)(iv)(A) of this section.
Applicants or licensees applying
Subsection IWL, 1995 Edition with the
1996 Addenda, shall apply paragraphs
(b)(2)(iv)(A), (b)(2)(iv)(D)(3), and
(b)(2)(iv)(E) of this section. Applicants
or licensees applying Subsection IWL,
1998 Edition through the 2000 Addenda
shall apply paragraphs (b)(2)(iv)(E) and
(b)(2)(iv)(F) of this section. Applicants
or licensees applying Subsection IWL,
2001 Edition through the 2004 Edition,
up to and including the 2006 Addenda,
shall apply paragraphs (b)(2)(iv)(E)
through (b)(2)(iv)(G) of this section.
Applicants or licensees applying
Subsection IWL, 2007 Edition through
the latest edition and addenda
incorporated by reference in paragraph
(b)(2) of this section, shall apply
paragraph (b)(2)(iv)(E) of this section.
(A) Grease caps that are accessible
must be visually examined to detect
grease leakage or grease cap
deformations. Grease caps must be
removed for this examination when
there is evidence of grease cap
deformation that indicates deterioration
of anchorage hardware.
(B) When evaluation of consecutive
surveillances of prestressing forces for
the same tendon or tendons in a group
indicates a trend of prestress loss such
that the tendon force(s) would be less
than the minimum design prestress
requirements before the next inspection
interval, an evaluation must be
performed and reported in the
Engineering Evaluation Report as
prescribed in IWL–3300.
(C) When the elongation
corresponding to a specific load
(adjusted for effective wires or strands)
during retensioning of tendons differs
by more than 10 percent from that
recorded during the last measurement,
an evaluation must be performed to
determine whether the difference is
related to wire failures or slip of wires
in anchorage. A difference of more than
10 percent must be identified in the ISI
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
Summary Report required by IWA–
6000.
(D) The applicant or licensee shall
report the following conditions, if they
occur, in the ISI Summary Report
required by IWA–6000:
(1) The sampled sheathing filler
grease contains chemically combined
water exceeding 10 percent by weight or
the presence of free water;
(2) The absolute difference between
the amount removed and the amount
replaced exceeds 10 percent of the
tendon net duct volume;
(3) Grease leakage is detected during
general visual examination of the
containment surface.
(E) For Class CC applications, the
applicant or licensee shall evaluate the
acceptability of inaccessible areas when
conditions exist in accessible areas that
could indicate the presence of or result
in degradation to such inaccessible
areas. For each inaccessible area
identified, the applicant or licensee
shall provide the following in the ISI
Summary Report required by IWA–
6000:
(1) A description of the type and
estimated extent of degradation, and the
conditions that led to the degradation;
(2) An evaluation of each area, and
the result of the evaluation, and;
(3) A description of necessary
corrective actions.
(F) 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) 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.
(v) Examination of metal
containments and the liners of concrete
containments. Applicants or licensees
applying Subsection IWE, 1992 Edition
with the 1992 Addenda, or the 1995
Edition with the 1996 Addenda, shall
satisfy the requirements of paragraphs
(b)(2)(v)(A) through (b)(2)(v)(E) of this
section. Applicants or licensees
applying Subsection IWE, 1998 Edition
through the 2001 Edition with the 2003
Addenda, shall satisfy the requirements
of paragraphs (b)(2)(v)(A), (b)(2)(v)(B),
and (b)(2)(v)(F) through (b)(2)(v)(I) of
this section. Applicants or licensees
applying Subsection IWE, 2004 Edition,
up to and including, the 2005 Addenda,
shall satisfy the requirements of
paragraphs (b)(2)(v)(A), (b)(2)(v)(B), and
(b)(2)(v)(F) through (b)(2)(v)(H) of this
PO 00000
Frm 00031
Fmt 4701
Sfmt 4702
24353
section. Applicants or licensees
Licensees applying Subsection IWE,
2004 Edition with the 2006 Addenda,
shall satisfy the requirements of
paragraphs (b)(2)(v)(A) and (b)(2)(v)(B)
of this section. Applicants or licensees
applying Subsection IWE, 2007 Edition
through the latest addenda incorporated
by reference in paragraph (b)(2) of this
section, shall satisfy the requirements of
paragraphs (b)(2)(v)(A), (b)(2)(v)(B) and
(b)(2)(v)(J) of this section.
(A) For Class MC applications, the
applicant or licensee shall evaluate the
acceptability of inaccessible areas when
conditions exist in accessible areas that
could indicate the presence of or result
in degradation to such inaccessible
areas. For each inaccessible area
identified, the applicant or licensee
shall provide the following in the ISI
Summary Report as required by IWA–
6000:
(1) A description of the type and
estimated extent of degradation, and the
conditions that led to the degradation;
(2) An evaluation of each area, and
the result of the evaluation, and;
(3) A description of necessary
corrective actions.
(B) When performing remotely the
visual examinations required by
Subsection IWE, the maximum direct
examination distance specified in Table
IWA–2210–1 may be extended and the
minimum illumination requirements
specified in Table IWA–2210–1 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) The examinations specified in
Examination Category E–B, Pressure
Retaining Welds, and Examination
Category E–F, Pressure Retaining
Dissimilar Metal Welds, are optional.
(D) Paragraph (b)(2)(v)(D) of this
section may be used as an alternative to
the requirements of IWE–2430.
(1) If the examinations reveal flaws or
areas of degradation exceeding the
acceptance standards of Table IWE–
3410–1, an evaluation must be
performed to determine whether
additional component examinations are
required. For each flaw or area of
degradation identified which exceeds
acceptance standards, the applicant or
licensee shall provide the following in
the ISI Summary Report required by
IWA–6000:
(i) A description of each flaw or area,
including the extent of degradation, and
the conditions that led to the
degradation;
(ii) The acceptability of each flaw or
area, and the need for additional
examinations to verify that similar
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
24354
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
degradation does not exist in similar
components, and;
(iii) A description of necessary
corrective actions.
(2) The number and type of additional
examinations to ensure detection of
similar degradation in similar
components.
(E) A general visual examination as
required by Subsection IWE must be
performed once each period.
(F) 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
shall 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) 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) 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) 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 pressureretaining components.
(J) In general, the cutting of a large
hole in the containment pressure
boundary for replacement of steam
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
generators, reactor vessel heads,
pressurizers, or other similar
modification is considered a ‘‘major’’
modification or repair/replacement for
Class MC and Class CC containment
structures. When applying IWE–5000,
any repair/replacement that is a ‘‘major’’
containment modification, as defined in
this section, must be followed by a Type
A test to provide assurance of
containment structural and leaktight
integrity prior to returning to service, in
accordance with 10 CFR part 50,
appendix J, 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
acceptance standard for the test must be
in accordance with 10 CFR part 50,
appendix J. In lieu of performing the
Type A test, the applicant or licensee
may conduct a short-duration structural
test of the containment, which is a
combination of actions to ensure that:
(1) The modified containment meets
the pre-service non-destructive
examination (NDE) test requirements as
required by the construction code;
(2) The locally welded areas are
examined for essentially zero leakage
using a soap bubble test, or an
equivalent test;
(3) The entire containment is
subjected to the peak calculated
containment design basis accident
pressure, Pa, for a minimum of 10
minutes (Class MC steel containment)
and 1 hour (Class CC concrete
containment); and
(4) The outside surfaces of concrete
containments are visually examined as
required by Subsection IWL, during the
peak pressure, and that the outside and
inside surfaces of the steel containment
surfaces are examined as required by
Subsection IWE, during or immediately
after the test.
(vi) Quality assurance. When
applying Section XI editions and
addenda later than the 1989 Edition, the
requirements of NQA–1, ‘‘Quality
Assurance Requirements for Nuclear
Facilities,’’ 1979 Addenda through the
1989 Edition, are acceptable as
permitted by IWA–1400 of Section XI, if
the licensee uses its 10 CFR part 50,
appendix B, quality assurance program,
in conjunction with Section XI
requirements. Commitments contained
in the licensee’s quality assurance
program description that are more
stringent than those contained in NQA–
1 must govern Section XI activities.
Further, where NQA–1 and Section XI
do not address the commitments
contained in the licensee’s Appendix B
quality assurance program description,
PO 00000
Frm 00032
Fmt 4701
Sfmt 4702
the commitments must be applied to
Section XI activities.
(vii) [Reserved]
(viii) Underwater welding. The
provisions in IWA–4660, ‘‘Underwater
Welding,’’ of Section XI, 1997 Addenda
through the latest edition and addenda
incorporated by reference in paragraph
(b)(2) of this section, are not approved
for use on irradiated material.
(ix) [Reserved]
(x) Appendix VIII personnel
qualification. All personnel qualified for
performing ultrasonic examinations in
accordance with Appendix VIII shall
receive 8 hours of annual hands-on
training on specimens that contain
cracks. Licensees applying the 1999
Addenda through the latest edition and
addenda incorporated by reference in
paragraph (b)(2) 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.
(xi) Appendix VIII specimen set and
qualification requirements. Licensees
using Appendix VIII in the 1995 Edition
through the 2001 Edition of the ASME
Boiler and Pressure Vessel Code may
elect to comply with all of the
provisions in paragraphs (b)(2)(xi)(A)
through (b)(2)(xi)(M) of this section,
except for paragraph (b)(2)(xi)(F) of this
section, which may be used at the
licensee’s option. Licensees using
editions and addenda after 2001 Edition
through the 2006 Addenda shall use the
2001 Edition of Appendix VIII, and may
elect to comply with all of the
provisions in paragraphs (b)(2)(xi)(A)
through (b)(2)(xi)(M) of this section,
except for paragraph (b)(2)(xi)(F) of this
section, which may be used at the
licensee’s option.
(A) When applying Supplements 2, 3,
and 10 to Appendix VIII, the following
examination coverage criteria
requirements must be used:
(1) Piping must be examined in two
axial directions, and when examination
in the circumferential direction is
required, the circumferential
examination must be performed in two
directions, provided access is available.
Dissimilar metal welds must be
examined axially and circumferentially.
(2) Where examination from both
sides is not possible, full coverage credit
may be claimed from a single side for
ferritic welds. Where examination from
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
both sides is not possible on austenitic
welds or dissimilar metal welds, full
coverage credit from a single side may
be claimed only after completing a
successful single-sided Appendix VIII
demonstration using flaws on the
opposite side of the weld. Dissimilar
metal weld qualifications must be
demonstrated from the austenitic side of
the weld and may be used to perform
examinations from either side of the
weld.
(B) The following conditions must be
used in addition to the requirements of
Supplement 4 to Appendix VIII:
(1) Paragraph 3.1, Detection
acceptance criteria—Personnel are
qualified for detection if the results of
the performance demonstration satisfy
the detection requirements of ASME
Section XI, Appendix VIII, Table VIII–
S4–1 and no flaw greater than 0.25 inch
through wall dimension is missed.
(2) Paragraph 1.1(c), Detection test
matrix—Flaws smaller than the 50
percent of allowable flaw size, as
defined in IWB–3500, need not be
included as detection flaws. For
procedures applied from the inside
surface, use the minimum thickness
specified in the scope of the procedure
to calculate a/t. For procedures applied
from the outside surface, the actual
thickness of the test specimen is to be
used to calculate a/t.
(C) When applying Supplement 4 to
Appendix VIII, the following conditions
must be used:
(1) A depth sizing requirement of 0.15
inch RMS must be used in lieu of the
requirements in Subparagraphs 3.2(a)
and 3.2(c), and a length sizing
requirement of 0.75 inch RMS must be
used in lieu of the requirement in
Subparagraph 3.2(b).
(2) In lieu of the location acceptance
criteria requirements of Subparagraph
2.1(b), a flaw will be considered
detected when reported within 1.0 inch
or 10 percent of the metal path to the
flaw, whichever is greater, of its true
location in the X and Y directions.
(3) In lieu of the flaw type
requirements of Subparagraph 1.1(e)(1),
a minimum of 70 percent of the flaws
in the detection and sizing tests shall be
cracks. Notches, if used, must be limited
by the following:
(i) Notches must be limited to the case
where examinations are performed from
the clad surface.
(ii) Notches must be semielliptical
with a tip width of less than or equal to
0.010 inches.
(iii) Notches must be perpendicular to
the surface within ±2 degrees.
(4) In lieu of the detection test matrix
requirements in paragraphs 1.1(e)(2) and
1.1(e)(3), personnel demonstration test
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
sets must contain a representative
distribution of flaw orientations, sizes,
and locations.
(D) The following conditions must be
used in addition to the requirements of
Supplement 6 to Appendix VIII:
(1) Paragraph 3.1, Detection
Acceptance Criteria—Personnel are
qualified for detection if:
(i) No surface connected flaw greater
than 0.25 inch through wall has been
missed.
(ii) No embedded flaw greater than
0.50 inch through wall has been missed.
(2) Paragraph 3.1, Detection
Acceptance Criteria—For procedure
qualification, all flaws within the scope
of the procedure are detected.
(3) Paragraph 1.1(b) for detection and
sizing test flaws and locations—Flaws
smaller than the 50 percent of allowable
flaw size, as defined in IWB–3500, need
not be included as detection flaws.
Flaws which are less than the allowable
flaw size, as defined in IWB–3500, may
be used as detection and sizing flaws.
(4) Notches are not permitted.
(E) When applying Supplement 6 to
Appendix VIII, the following conditions
must be used:
(1) A depth sizing requirement of 0.25
inch RMS must be used in lieu of the
requirements of subparagraphs 3.2(a),
3.2(c)(2), and 3.2(c)(3).
(2) In lieu of the location acceptance
criteria requirements in Subparagraph
2.1(b), a flaw will be considered
detected when reported within 1.0 inch
or 10 percent of the metal path to the
flaw, whichever is greater, of its true
location in the X and Y directions.
(3) In lieu of the length sizing criteria
requirements of Subparagraph 3.2(b), a
length sizing acceptance criteria of 0.75
inch RMS must be used.
(4) In lieu of the detection specimen
requirements in Subparagraph 1.1(e)(1),
a minimum of 55 percent of the flaws
must be cracks. The remaining flaws
may be cracks or fabrication type flaws,
such as slag and lack of fusion. The use
of notches is not allowed.
(5) In lieu of paragraphs 1.1(e)(2) and
1.1(e)(3) detection test matrix, personnel
demonstration test sets must contain a
representative distribution of flaw
orientations, sizes, and locations.
(F) The following conditions may be
used for personnel qualification for
combined Supplement 4 to Appendix
VIII and Supplement 6 to Appendix VIII
qualification. Licensees choosing to
apply this combined qualification shall
apply all of the provisions of
Supplements 4 and 6 including the
following conditions:
(1) For detection and sizing, the total
number of flaws must be at least 10. A
minimum of 5 flaws shall be from
PO 00000
Frm 00033
Fmt 4701
Sfmt 4702
24355
Supplement 4, and a minimum of 50
percent of the flaws must be from
Supplement 6. At least 50 percent of the
flaws in any sizing must be cracks.
Notches are not acceptable for
Supplement 6.
(2) Examination personnel are
qualified for detection and length sizing
when the results of any combined
performance demonstration satisfy the
acceptance criteria of Supplement 4 to
Appendix VIII.
(3) Examination personnel are
qualified for depth sizing when
Supplement 4 to Appendix VIII and
Supplement 6 to Appendix VIII flaws
are sized within the respective
acceptance criteria of those
supplements.
(G) When applying Supplement 4 to
Appendix VIII, Supplement 6 to
Appendix VIII, or combined
Supplement 4 and Supplement 6
qualification, the following additional
conditions must be used, and
examination coverage must include:
(1) The clad to base metal interface,
including a minimum of 15 percent T
(measured from the clad to base metal
interface), must be examined from four
orthogonal directions using procedures
and personnel qualified in accordance
with Supplement 4 to Appendix VIII.
(2) If the clad-to-base-metal-interface
procedure demonstrates delectability of
flaws with a tilt angle relative to the
weld centerline of at least 45 degrees,
the remainder of the examination
volume is considered fully examined if
coverage is obtained in one parallel and
one perpendicular direction. This must
be accomplished using a procedure and
personnel qualified for single-side
examination in accordance with
Supplement 6. Subsequent
examinations of this volume may be
performed using examination
techniques qualified for a tilt angle of at
least 10 degrees.
(3) The examination volume not
addressed by paragraph (b)(2)(xi)(G)(1)
of this section is considered fully
examined if coverage is obtained in one
parallel and one perpendicular
direction, using a procedure and
personnel qualified for single sided
examination when the conditions in
paragraph (b)(2)(xi)(G)(2) are met.
(H) When applying Supplement 5 to
Appendix VIII, at least 50 percent of the
flaws in the demonstration test set must
be cracks and the maximum misorientation must be demonstrated with
cracks. Flaws in nozzles with bore
diameters equal to or less than 4 inches
may be notches.
(I) When applying Supplement 5,
Paragraph (a), to Appendix VIII, the
number of false calls allowed must be
E:\FR\FM\04MYP3.SGM
04MYP3
24356
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
D/10, with a maximum of 3, where D is
the diameter of the nozzle.
(J) [Reserved]
(K) When performing nozzle-to-vessel
weld examinations, the following
conditions must be used when the
requirements contained in Supplement
7 to Appendix VIII are applied for
nozzle-to-vessel welds in conjunction
with Supplement 4 to Appendix VIII,
Supplement 6 to Appendix VIII, or
combined Supplement 4 and
Supplement 6 qualification.
(1) For examination of nozzle-tovessel welds conducted from the bore,
the following conditions are required to
qualify the procedures, equipment, and
personnel:
(i) For detection, a minimum of four
flaws in one or more full-scale nozzle
mock-ups must be added to the test set.
The specimens must comply with
Supplement 6, paragraph 1.1, to
Appendix VIII, except for flaw locations
specified in Table VIII S6–1. Flaws may
be notches, fabrication flaws or cracks.
Seventy-five (75) percent of the flaws
must be cracks or fabrication flaws.
Flaw locations and orientations must be
selected from the choices shown in
paragraph (b)(2)(xi)(K)(4) of this section,
Table VIII–S7–1—Modified, with the
exception that flaws in the outer eightyfive (85) percent of the weld need not
be perpendicular to the weld. There
may be no more than two flaws from
each category, and at least one
subsurface flaw must be included.
(ii) For length sizing, a minimum of
four flaws as in paragraph
(b)(2)(xi)(K)(1)(i) of this section must be
included in the test set. The length
sizing results must be added to the
results of combined Supplement 4 to
Appendix VIII and Supplement 6 to
Appendix VIII. The combined results
must meet the acceptance standards
contained in paragraph (b)(2)(xi)(E)(3) of
this section.
(iii) For depth sizing, a minimum of
four flaws as in paragraph
(b)(2)(xi)(K)(1)(i) of this section must be
included in the test set. Their depths
must be distributed over the ranges of
Supplement 4, Paragraph 1.1, to
Appendix VIII, for the inner 15 percent
of the wall thickness and Supplement 6,
Paragraph 1.1, to Appendix VIII, for the
remainder of the wall thickness. The
depth sizing results must be combined
with the sizing results from Supplement
4 to Appendix VIII for the inner 15
percent and to Supplement 6 to
Appendix VIII for the remainder of the
wall thickness. The combined results
must meet the depth sizing acceptance
criteria contained in paragraphs
(b)(2)(xi)(C)(1), (b)(2)(xi)(E)(1), and
(b)(2)(xi)(F)(3) of this section.
(2) For examination of reactor
pressure vessel nozzle-to-vessel welds
conducted from the inside of the vessel,
(i) The clad to base metal interface
and the adjacent examination volume to
a minimum depth of 15 percent T
(measured from the clad to base metal
interface) must be examined from four
orthogonal directions using a procedure
and personnel qualified in accordance
with Supplement 4 to Appendix VIII as
conditioned by paragraphs (b)(2)(xi)(B)
and (b)(2)(xi)(C) of this section.
(ii) When the examination volume
defined in paragraph (b)(2)(xi)(K)(2)(i) of
this section cannot be effectively
examined in all four directions, the
examination must be augmented by
examination from the nozzle bore using
a procedure and personnel qualified in
accordance with paragraph
(b)(2)(xi)(K)(1) of this section.
(iii) The remainder of the examination
volume not covered by paragraph
(b)(2)(xi)(K)(2)(ii) of this section or a
combination of paragraphs
(b)(2)(xi)(K)(2)(i) and (b)(2)(xi)(K)(2)(ii)
of this section, must be examined from
the nozzle bore using a procedure and
personnel qualified in accordance with
paragraph (b)(2)(xi)(K)(1) of this section,
or from the vessel shell using a
procedure and personnel qualified for
single sided examination in accordance
with Supplement 6 to Appendix VIII, as
conditioned by paragraphs (b)(2)(xi)(D)
through (b)(2)(xi)(G) of this section.
(3) For examination of reactor
pressure vessel nozzle-to-shell welds
conducted from the outside of the
vessel,
(i) The clad to base metal interface
and the adjacent metal to a depth of 15
percent T, (measured from the clad to
base metal interface) must be examined
from one radial and two opposing
circumferential directions using a
procedure and personnel qualified in
accordance with Supplement 4 to
Appendix VIII, as conditioned by
paragraphs (b)(2)(xi)(B) and (b)(2)(xi)(C)
of this section, for examinations
performed in the radial direction, and
Supplement 5 to Appendix VIII, as
conditioned by paragraph (b)(2)(xi)(J) of
this section, for examinations performed
in the circumferential direction.
(ii) The examination volume not
addressed by paragraph
(b)(2)(xi)(K)(3)(i) of this section must be
examined in a minimum of one radial
direction using a procedure and
personnel qualified for single sided
examination in accordance with
Supplement 6 to Appendix VIII, as
conditioned by paragraphs (b)(2)(xi)(D)
through (b)(2)(xi)(G) of this section.
(4) Table VIII–S7–1, ‘‘Flaw Locations
and Orientations,’’ Supplement 7 to
Appendix VIII, is conditioned as
follows:
TABLE VIII–S7–1—MODIFIED
Flaw Locations and Orientations
Parallel to weld
Perpendicular to weld
X
X
X
X
........................................
........................................
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Inner 15 percent ......................................................................................................................
OD Surface ..............................................................................................................................
Subsurface ...............................................................................................................................
(L) As a condition to the requirements
of Supplement 8, Subparagraph 1.1(c),
to Appendix VIII, notches may be
located within one diameter of each end
of the bolt or stud.
(M) When implementing Supplement
12 to Appendix VIII, only the provisions
related to the coordinated
implementation of Supplement 3 to
VerDate Mar<15>2010
21:08 May 03, 2010
Jkt 220001
Supplement 2 performance
demonstrations are to be applied.
(xii) Appendix VIII single side ferritic
vessel and piping and stainless steel
piping examination.
(A) Examinations performed from one
side of a ferritic vessel weld must be
conducted with equipment, procedures,
and personnel that have demonstrated
proficiency with single side
PO 00000
Frm 00034
Fmt 4701
Sfmt 4702
examinations. To demonstrate
equivalency to two sided examinations,
the demonstration must be performed to
the requirements of Appendix VIII as
conditioned by this paragraph and
paragraphs (b)(2)(xi)(B) through
(b)(2)(xi)(G) of this section, on
specimens containing flaws with nonoptimum sound energy reflecting
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
characteristics or flaws similar to those
in the vessel being examined.
(B) Examinations performed from one
side of a ferritic or stainless steel pipe
weld must be conducted with
equipment, procedures, and personnel
that have demonstrated proficiency with
single side examinations. To
demonstrate equivalency to two sided
examinations, the demonstration must
be performed to the requirements of
Appendix VIII as conditioned by this
paragraph and paragraph (b)(2)(xi)(A) of
this section.
(xiii) Reconciliation of quality
requirements. When purchasing
replacement items, in addition to the
reconciliation provisions of IWA–4200,
1995 Addenda through 1998 Edition,
the replacement items must be
purchased, to the extent necessary, in
accordance with the licensee’s quality
assurance program description required
by 10 CFR 50.34(b)(6)(ii).
(xiv) Certification of NDE personnel.
(A) Level I and II nondestructive
examination personnel shall be
recertified on a 3-year interval in lieu of
the 5-year interval specified in the 1997
Addenda and 1998 Edition of IWA–
2314, and IWA–2314(a) and IWA–
2314(b) of the 1999 Addenda through
the latest edition and addenda
incorporated by reference in paragraph
(b)(2) of this section.
(B) 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) When applying editions and
addenda prior to the 2004 Edition
through 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.
(xv) 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 1998 Edition through
the 2004 Edition of Section XI of the
ASME B&PV Code. The provisions in
IWA–4520(c), 1997 Addenda 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
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
not approved for use. The provisions in
IWA–4520(b)(2) and IWA–4521 of the
2008 Addenda through the latest edition
and addenda approved in paragraph
(b)(2) of this section, allowing the
substitution of ultrasonic examination
for radiographic examination specified
in the Construction Code are not
approved for use.
(xvi) System leakage tests.
(A) When performing system leakage
tests in accordance with IWA–5213(a),
1997 through 2002 Addenda, the
licensee shall 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) The NDE provision in IWA–
4540(a)(2) of the 2002 Addenda of
Section XI must be applied when
performing system leakage tests 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 incorporated by reference
in paragraph (b)(2) of this section.
(xvii) Table IWB–2500–1 examination
requirements.
(A) The provisions of Table IWB–
2500–1, Examination Category B–D, Full
Penetration Welded Nozzles in Vessels,
Items B3.40 and B3.60 (Inspection
Program A) and Items B3.120-and
B3.140 (Inspection Program B) of the
1998 Edition must be applied when
using the 1999 Addenda through the
latest edition and addenda incorporated
by reference in paragraph (b)(2) of this
section. A visual examination with
magnification that has a resolution
sensitivity to detect a 1-mil width wire
or crack, utilizing the allowable flaw
length criteria in Table IWB–3512–1,
1997 Addenda through the latest edition
and addenda incorporated by reference
in paragraph (b)(2) of this section, with
a limiting assumption on the flaw aspect
ratio (i.e., a/l=0.5), may be performed
instead of an ultrasonic examination.
(B) The provisions of Table IWB–
2500–1, Examination Category B–G–2,
Item B7.80, that are in the 1995 Edition
are applicable only to reused bolting
when using the 1997 Addenda through
the latest edition and addenda
incorporated by reference in paragraph
(b)(2) of this section.
(xviii) Surface examination. The use
of the provision in IWA–2220, ‘‘Surface
Examination,’’ of Section XI, 2001
Edition through the latest edition and
PO 00000
Frm 00035
Fmt 4701
Sfmt 4702
24357
addenda incorporated by reference in
paragraph (b)(2) of this section, that
allow use of an ultrasonic examination
method is prohibited.
(xix) Evaluation of thermally cut
surfaces. The use of the provisions for
eliminating mechanical processing of
thermally cut surfaces in IWA–4461.4.2
of Section XI, 2001 Edition through the
latest edition and addenda incorporated
by reference in paragraph (b)(2) of this
section are prohibited.
(xx) Incorporation of the performance
demonstration initiative and addition of
ultrasonic examination criteria. The use
of Appendix VIII and the supplements
to Appendix VIII and Article I–3000 of
Section XI of the ASME B&PV Code,
2002 Addenda through the 2006
Addenda is prohibited.
(xxi) Mitigation of defects by
modification. The use of the provisions
in IWA–4340, ‘‘Mitigation of Defects by
Modification,’’ Section XI, 2001 Edition
through the latest edition and addenda
incorporated by reference in paragraph
(b)(2) of this section are prohibited.
(xxii) Pressure testing Class 1, 2, and
3 mechanical joints. The repair and
replacement activity provisions in IWA–
4540(c) of the 1998 Edition of Section XI
for pressure testing Class 1, 2, and 3
mechanical joints must be applied when
using the 2001 Edition through the
latest edition and addenda incorporated
by reference in paragraph (b)(2) of this
section.
(xxiii) Removal of insulation. When
performing visual examination in
accordance with IWA–5242 of Section
XI of the ASME B&PV Code, 2003
Addenda through the 2006 Addenda, or
IWA–5241 of the 2007 Edition through
the latest edition and addenda
incorporated in paragraph (b)(2) of the
section, insulation must be removed
from 17–4 PH or 410 stainless steel
studs or bolts aged at a temperature
below 1100°F or having a Rockwell
Method C hardness value above 30, and
from A–286 stainless steel studs or bolts
preloaded to 100,000 pounds per square
inch or higher.
(xxiv) Analysis of flaws. Licensees
using ASME B&PV Code, Section XI,
Appendix A shall use the following
conditions when implementing
Equation (2) in A–4300(b)(1):
For R < 0, DKI depends on the crack depth
(a), and the flow stress (sf). The flow stress
is defined by sf = 1⁄2(sys + sult), where sys is
the yield strength and sult is the ultimate
tensile strength in units ksi (MPa) and a is
in units in. (mm). For ¥2 ≤ R ≤ 0 and Kmax
¥ Kmin ≤ 0.8 × 1.12 sf √(πa), S = 1 and DKI
= Kmax. For R < ¥2 and Kmax ¥ Kmin ≤ 0.8
× 1.12 sf √(πa), S = 1 and DKI = (1–R) Kmax/
3. For R < 0 and Kmax ¥ Kmin > 0.8 × 1.12
sf √(πa), S = 1 and DKI = Kmax ¥ Kmin.
E:\FR\FM\04MYP3.SGM
04MYP3
24358
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
(xxv) Evaluation of unanticipated
operating events. The provisions of
ASME B&PV Code, Section XI,
Appendix E, Section E–1200 are not
approved for use. In addition, when
using the provisions of Section E–1300,
the analytical procedure must be based
on a postulated semi-elliptical surface
flaw of a one-quarter vessel thickness
(i.e., the ‘‘minimum initiation crack size’’
in Table E–2 shall be a 1/4T flaw) and
the linear elastic fracture mechanics
criteria be as follows:
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
1.4KIm + KIr = KIc for the LTOP condition,
and 1.4KIm + KIt + KIr = KIc, for the PTT
condition
(xxvi) Nonmandatory Appendix R.
Nonmandatory Appendix R, ‘‘RiskInformed Inspection Requirements for
Piping,’’ of Section XI, 2005 Addenda
through the latest edition and addenda
incorporated by reference in paragraph
(b)(2) of this section, may not be
implemented without prior NRC
authorization of the proposed
alternative in accordance with
paragraph (a)(3)(i) of this section.
(3) As used in this section, references
to the OM Code refer to the ASME Code
for Operation and Maintenance of
Nuclear Power Plants, Subsections
ISTA, ISTB, ISTC, and ISTD, Mandatory
Appendices I and II, and Nonmandatory
Appendices A through H and J, and
include the 1995 Edition through the
2006 Addenda subject to the following
conditions:
*
*
*
*
*
(v) Subsection ISTD. Article IWF–
5000, ‘‘Inservice Inspection
Requirements for Snubbers,’’ of the
ASME B&PV Code, Section XI, must be
used when performing inservice
inspection examinations and tests of
snubbers at nuclear power plants.
(A) Licensees may use Subsection
ISTD, ‘‘Preservice and Inservice
Examination and Testing of Dynamic
Restraints (Snubbers) in Light-Water
Reactor Power Plants,’’ ASME OM Code,
1995 Edition through the latest edition
and addenda incorporated by reference
in paragraph (b)(3) of this section, in
place of the requirements for snubbers
in the editions and addenda up to the
2005 Addenda of the ASME B&PV Code,
Section XI, IWF–5200(a) and (b) and
IWF–5300(a) and (b), by making
appropriate changes to their technical
specifications or licensee-controlled
documents. Preservice and inservice
examinations must be performed using
the VT–3 visual examination method
described in IWA–2213.
(B) Licensees shall comply with the
provisions for examining and testing
snubbers in Subsection ISTD of the
ASME OM Code and make appropriate
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
changes to their technical specifications
or licensee-controlled documents when
using the 2006 Addenda and later
editions and addenda of Section XI of
the ASME B&PV Code.
(vi) Exercise interval for manual
valves. Manual valves must be exercised
on a 2-year interval rather that the 5year interval specified in paragraph
ISTC–3540 of the 1999 through the 2005
Addenda of the ASME OM Code,
provided that adverse conditions do not
require more frequent testing.
*
*
*
*
*
(c) * * *
(3) The Code edition, addenda, and
optional ASME Code cases to be applied
to components of the reactor coolant
pressure boundary must be determined
by the provisions of paragraph NCA–
1140, Subsection NCA of Section III of
the ASME Boiler and Pressure Vessel
Code, subject to the following
conditions:
(i) The edition and addenda applied
to a component must be those which are
incorporated by reference in paragraph
(b)(1) of this section;
(ii) The ASME Code provisions
applied to the pressure vessel may be
dated no earlier than the Summer 1972
Addenda of the 1971 edition;
(iii) The ASME Code provisions
applied to piping, pumps, and valves
may be dated no earlier than the Winter
1972 Addenda of the 1971 edition; and
(iv) The optional Code cases applied
to a component must be those listed in
NRC Regulatory Guide 1.84 that is
incorporated by reference in paragraph
(b) of this section.
*
*
*
*
*
(d) * * *
(2) The Code edition, addenda, and
optional ASME Code cases to be applied
to the systems and components
identified in paragraph (d)(1) of this
section must be determined by the rules
of paragraph NCA–1140, Subsection
NCA of Section III of the ASME Boiler
and Pressure Vessel Code, subject to the
following conditions:
(i) The edition and addenda must be
those which are incorporated by
reference in paragraph (b)(1) of this
section;
(ii) The ASME Code provisions
applied to the systems and components
may be dated no earlier than the 1980
Edition; and
(iii) The optional Code cases must be
those listed in the NRC Regulatory
Guide 1.84 that is incorporated by
reference in paragraph (b) of this
section.
(e) * * *
(2) The Code edition, addenda, and
optional ASME Code cases to be applied
PO 00000
Frm 00036
Fmt 4701
Sfmt 4702
to the systems and components
identified in paragraph (e)(1) of this
section must be determined by the rules
of paragraph NCA–1140, subsection
NCA of Section III of the ASME Boiler
and Pressure Vessel Code, subject to the
following conditions:
(i) The edition and addenda must be
those which are incorporated by
reference in paragraph (b)(1) of this
section;
(ii) The ASME Code provisions
applied to the systems and components
may be dated no earlier than the 1980
Edition; and
(iii) The optional Code cases must be
those listed in NRC Regulatory Guide
1.84 that is incorporated by reference in
paragraph (b) of this section.
(f) * * *
(2) For a boiling or pressurized watercooled nuclear power facility whose
construction permit was issued on or
after January 1, 1971, but before July 1,
1974, pumps and valves which are
classified as ASME Code Class 1 and
Class 2 must be designed and provided
with access to enable the performance of
inservice tests for operational readiness
set forth in editions and addenda of
Section XI of the ASME Boiler and
Pressure Vessel Code incorporated by
reference in paragraph (b) of this section
(or the optional ASME Code cases listed
in NRC Regulatory Guide 1.147,
Revision 15, or 1.192 that are
incorporated by reference in paragraph
(b) of this section) in effect 6 months
before the date of issuance of the
construction permit. The pumps and
valves may meet the inservice test
requirements set forth in subsequent
editions of this Code and addenda
which are incorporated by reference in
paragraph (b) of this section (or the
optional ASME Code Cases listed in
NRC Regulatory Guide 1.147, Revision
15, or 1.192 that are incorporated by
reference in paragraph (b) of this
section), subject to the applicable
conditions listed therein.
(3) * * *
(v) All pumps and valves may meet
the test requirements set forth in
subsequent editions of codes and
addenda or portions thereof which are
incorporated by reference in paragraph
(b) of this section, subject to the
conditions listed in paragraph (b) of this
section.
(4) Throughout the service life of a
boiling or pressurized water-cooled
nuclear power facility, pumps and
valves which are classified as ASME
Code Class 1, Class 2, and Class 3 must
meet the inservice test requirements,
except design and access provisions, set
forth in the ASME OM Code and
addenda that become effective
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
subsequent to editions and addenda
specified in paragraphs (f)(2) and (f)(3)
of this section and that are incorporated
by reference in paragraph (b) of this
section, to the extent practical within
the limitations of design, geometry and
materials of construction of the
components.
(i) 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 Code incorporated by
reference in paragraph (b) of this section
on the date 12 months before the date
of issuance of the operating license
under this part, or 12 months before the
date scheduled for initial loading fuel
under a combined license under part 52
of this chapter (or the optional ASME
Code cases listed in NRC Regulatory
Guide 1.192, that is incorporated by
reference in paragraph (b) of this
section), subject to the conditions listed
in paragraph (b) of this section.
(ii) 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 Code incorporated
by reference in paragraph (b) of this
section 12 months before the start of the
120-month interval (or the optional
ASME Code cases listed in NRC
Regulatory Guide 1.147, Revision 15, or
Regulatory Guide 1.192 that are
incorporated by reference in paragraph
(b) of this section), subject to the
conditions listed in paragraph (b) of this
section.
(iii) [Reserved]
(iv) Inservice tests of pumps and
valves may meet the requirements set
forth in subsequent editions and
addenda that are incorporated by
reference in paragraph (b) 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.
(5) * * *
(iv) Where a pump or valve test
requirement by the code or addenda is
determined to be impractical by the
licensee and is not included in the
revised inservice test program as
permitted by paragraph (f)(4) of this
section, the basis for this determination
must be submitted for NRC review and
approval not later than 12 months after
the expiration of the initial 120-month
interval of operation from start of
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
facility commercial operation and each
subsequent 120-month interval of
operation during which the test is
determined to be impractical.
*
*
*
*
*
(g) * * *
(2) For a boiling or pressurized watercooled nuclear power facility whose
construction permit was issued on or
after January 1, 1971, but before July 1,
1974, components (including supports)
which are classified as ASME Code
Class 1 and Class 2 must be designed
and be provided with access to enable
the performance of inservice
examination of such components
(including supports) and must meet the
preservice examination requirements set
forth in editions and addenda of Section
III or Section XI of the ASME B&PV
Code (or ASME OM Code for snubber
examination and testing) incorporated
by reference in paragraph (b) of this
section (or the optional ASME code
cases listed in NRC Regulatory Guide
1.147, Revision 15, that are incorporated
by reference in paragraph (b) of this
section) in effect six months before the
date of issuance of the construction
permit. The components (including
supports) may meet the requirements set
forth in subsequent editions and
addenda of this Code which are
incorporated by reference in paragraph
(b) of this section (or the optional ASME
code cases listed in NRC Regulatory
Guide 1.147, Revision 15, when using
Section XI, or Regulatory Guide 1.192
when using the OM Code, that are
incorporated by reference in paragraph
(b) of this section), subject to the
applicable conditions.
(3) For a boiling or pressurized watercooled nuclear power facility whose
construction permit under this part, or
design certification, design approval,
combined license, or manufacturing
license under part 52 of this chapter,
was issued on or after July 1, 1974:
(i) Components (including supports)
which are classified as ASME Code
Class 1 must be designed and provided
with access to enable the performance of
inservice examination of these
components and must meet the
preservice examination requirements set
forth in the editions and addenda of
Section III or Section XI of the ASME
B&PV Code (or ASME OM Code for
snubber examination and testing)
incorporated by reference in paragraph
(b) of this section (or the optional ASME
code cases listed in NRC Regulatory
Guide 1.147, Revision 15, when using
Section XI; or Regulatory Guide 1.192
when using the OM Code, that are
incorporated by reference in paragraph
(b) of this section) applied to the
PO 00000
Frm 00037
Fmt 4701
Sfmt 4702
24359
construction of the particular
component.
(ii) Components which are classified
as ASME Code Class 2 and Class 3 and
supports for components which are
classified as ASME Code Class 1, Class
2, and Class 3 must be designed and be
provided with access to enable the
performance of inservice examination of
these components and must meet the
preservice examination requirements set
forth in the editions and addenda of
Section III or Section XI of the ASME
B&PV Code (or ASME OM Code for
snubber examination and testing)
incorporated by reference in paragraph
(b) of this section (or the optional ASME
code cases listed in NRC Regulatory
Guide 1.147, Revision 15, when using
Section XI; or Regulatory Guide 1.192
when using the OM Code, that are
incorporated by reference in paragraph
(b) of this section) applied to the
construction of the particular
component.
(iii)–(iv) [Reserved]
(v) All components (including
supports) may meet the requirements set
forth in subsequent editions of codes
and addenda or portions thereof which
are incorporated by reference in
paragraph (b) of this section, subject to
the conditions listed therein.
(4) Throughout the service life of a
boiling or pressurized water-cooled
nuclear power facility, components
(including supports) which 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
B&PV Code (or ASME OM Code for
snubber examination and testing) that
become effective subsequent to editions
specified in paragraphs (g)(2) and (g)(3)
of this section and that are incorporated
by reference in paragraph (b) of this
section, to the extent practical within
the limitations of design, geometry and
materials of construction of the
components. Components which are
classified as Class MC pressure retaining
components and their integral
attachments, and components which 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 B&PV Code and addenda that
are incorporated by reference in
paragraph (b) of this section, subject to
the condition listed in paragraph
(b)(2)(ii) of this section and the
conditions listed in paragraphs (b)(2)(iv)
and (b)(2)(v) of this section, to the extent
E:\FR\FM\04MYP3.SGM
04MYP3
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
24360
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
practical within the limitation of design,
geometry and materials of construction
of the components.
(i) Inservice examination of
components and system pressure tests
conducted during the initial 120-month
inspection interval must comply with
the requirements in the latest edition
and addenda of the Code incorporated
by reference in paragraph (b) of this
section on the date 12 months before the
date of issuance of the operating license
(or the optional ASME code cases listed
in NRC Regulatory Guide 1.147,
Revision 15, when using Section XI; or
Regulatory Guide 1.192 when using the
OM Code, that are incorporated by
reference in paragraph (b) of this
section), subject to the conditions listed
in paragraph (b) of this section.
(ii) Inservice examination of
components and system pressure tests
conducted during successive 120-month
inspection intervals must comply with
the requirements of the latest edition
and addenda of the Code incorporated
by reference in paragraph (b) of this
section 12 months before the start of the
120-month inspection interval (or the
optional ASME code cases listed in NRC
Regulatory Guide 1.147, Revision 15,
when using Section XI; or Regulatory
Guide 1.192 when using the OM Code,
that are incorporated by reference in
paragraph (b) of this section), subject to
the conditions listed in paragraph (b) of
this section.
(iii) When applying editions and
addenda prior to the 2003 Addenda of
Section XI of the ASME B&PV Code
licensees may, but are not required to,
perform the surface examinations of
high-pressure safety injection systems
specified in Table IWB–2500–1,
Examination Category B–J, Item
Numbers B9.20, B9.21 and B9.22.
(iv) Inservice examination of
components and system pressure tests
may meet the requirements set forth in
subsequent editions and addenda that
are incorporated by reference in
paragraph (b) of this section, subject to
the conditions listed in paragraph (b) of
this section, and subject to Commission
approval. Portions of editions or
addenda may be used provided that all
related requirements of the respective
editions or addenda are met.
(v) For a boiling or pressurized watercooled nuclear power facility whose
construction permit under this part or
combined license under part 52 of this
chapter was issued after January 1,
1956:
(A) Metal containment pressure
retaining components and their integral
attachments must meet the inservice
inspection, repair, and replacement
requirements applicable to components
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
which are classified as ASME Code
Class MC;
(B) Metallic shell and penetration
liners which are pressure retaining
components and their integral
attachments in concrete containments
must meet the inservice inspection,
repair, and replacement requirements
applicable to components which are
classified as ASME Code Class MC;
(C) Concrete containment pressure
retaining components and their integral
attachments, and the post-tensioning
systems of concrete containments must
meet the inservice inspections, repair,
and replacement requirements
applicable to components which are
classified as ASME Code Class CC.
(5) * * *
(iii) If the licensee has determined
that conformance with a code
requirement is impractical for its
facility, the licensee shall notify the
Commission and submit, as specified in
§ 50.4, information to support the
determinations. Determinations of
impracticality in accordance with this
section must be based on the
demonstrated limitations experienced
when attempting to comply with the
code requirements during the inservice
inspection interval for which the
request is being submitted. Requests for
relief made in accordance with this
section must be submitted to the NRC
no later than 12 months after the
examination has been attempted.
(iv) Where the licensee determines
that an examination required by Code
edition or addenda is impractical, and is
not included in the revised inservice
inspection program as permitted by
paragraph (g)(4) of this section, the basis
for this determination must be
submitted for NRC review and approval
not later than 12 months after the
expiration of the initial or subsequent
120-month inspection interval for which
relief is sought.
(6) * * *
(ii) * * *
(B) Licensees do not have to submit to
the NRC for approval of their
containment inservice inspection
programs which were developed to
satisfy the requirements of Subsection
IWE and Subsection IWL with
specified conditions. The program
elements and the required
documentation must be maintained on
site for audit.
*
*
*
*
*
(E) * * *
(1) All licensees of pressurized water
reactors shall augment their inservice
inspection program by implementing
ASME Code Case N–722–1 subject to
the conditions specified in paragraphs
PO 00000
Frm 00038
Fmt 4701
Sfmt 4702
(g)(6)(ii)(E)(2) through (g)(6)(ii)(E)(4) of
this section. The inspection
requirements of ASME Code Case N–
722–1 do not apply to components with
pressure retaining welds fabricated with
Alloy 600/82/182 materials that have
been mitigated by weld overlay or stress
improvement.
(2) If a visual examination determines
that leakage is occurring from a specific
item listed in Table 1 of ASME Code
Case N–722–1 that is not exempted by
the ASME Code, Section XI, IWB–
1220(b)(1), additional actions must be
performed to characterize the location,
orientation, and length of crack(s) in
Alloy 600 nozzle wrought material and
location, orientation, and length of
crack(s) in Alloy 82/182 butt welds.
Alternatively, licensees may replace the
Alloy 600/82/182 materials in all the
components under the item number of
the leaking component.
(3) If the actions in paragraph
(g)(6)(ii)(E)(2) of this section determine
that a flaw is circumferentially oriented
and potentially a result of primary water
stress corrosion cracking, licensees shall
perform non-visual NDE inspections of
components that fall under that ASME
Code Case N–722–1 item number. The
number of components inspected must
equal or exceed the number of
components found to be leaking under
that item number. If circumferential
cracking is identified in the sample,
non-visual NDE must be performed in
the remaining components under that
item number.
*
*
*
*
*
(F) Inspection requirements for class 1
pressurized-water reactor piping and
vessel nozzle butt welds.
(1) Licensees of existing operating
pressurized-water reactors as of
[publication date of the final rule] shall
implement the requirements of ASME
Code Case N–770, subject to the
conditions specified in paragraphs
(g)(6)(ii)(F)(2) through (g)(6)(ii)(F)(16) of
this section, by the first refueling outage
after [date that is 60 days after the date
of publication of the final rule].
(2) Full structural weld overlays
authorized by the NRC staff may be
categorized as Inspection Items C or F,
as appropriate; welds that have been
mitigated by stress improvement
without welding may be categorized as
Inspection Items D or E, as appropriate,
provided the criteria in Appendix I of
the code case have been met; for ISI
frequencies, all other butt welds that
rely on Alloy 82/182 for structural
integrity shall be categorized as
Inspection Items A–1, A–2 or B until the
NRC staff has reviewed the mitigation
and authorized an alternative code case
E:\FR\FM\04MYP3.SGM
04MYP3
24361
Federal Register / Vol. 75, No. 85 / Tuesday, May 4, 2010 / Proposed Rules
jlentini on DSKJ8SOYB1PROD with PROPOSALS3
Inspection Item for the mitigated weld,
or until an alternative code case
Inspection Item is used based on
conformance with an ASME mitigation
code case endorsed in Regulatory Guide
1.147 with conditions, if applicable, and
incorporated in this section.
(3) Welds in Table 1, Inspection Items
A–1, A–2, and B, that have not received
a baseline examination using Section XI,
Appendix VIII requirements, shall be
examined at the next refueling outage
after [the effective date of the final rule].
(4) The axial examination coverage
requirements of –2500(c) may not be
considered to be satisfied unless
essentially 100 percent coverage is
achieved.
(5) Replace paragraph—3132.3(b) with
‘‘Previously-evaluated flaws that were
mitigated by the techniques identified
in Table 1 need not be reevaluated nor
have additional successive or additional
examinations performed if new planar
flaws have not been identified or
previously evaluated flaws have
remained essentially unchanged.’’
(6) If a weld mitigated by inlay or
cladding is determined through a
volumetric examination to have
cracking that penetrates beyond the
thickness of the inlay or cladding, the
weld must be reclassified as and
inspected using the frequencies of
Inspection Item A–1, A–2, or B, as
appropriate, until corrected by repair/
replacement activity in accordance with
IWA–4000 or by corrective measures
beyond the scope of Code Case N–770.
(7) For Inspection Items G, H, J, and
K, the surface examination requirements
of Table 1 must apply whether the
inservice volumetric examinations are
performed from the weld outside
diameter or the weld inside diameter.
All hot leg operating temperature welds
in inspection items G, H, J, and K must
be inspected each interval. A 25 percent
sample of cold leg operating
temperature welds must be inspected
VerDate Mar<15>2010
19:37 May 03, 2010
Jkt 220001
whenever the core barrel is removed
(unless it has already been inspected
within the past 10 years) or 20 years,
whichever is less.
(8) The first examination following
weld inlay, cladding, weld overlay or
stress improvement for Inspection Items
D, G, and H may not be deferred to the
end of the interval.
(9) In applying Measurement or
Quantification Criterion I–1.1 of
Appendix I, a construction weld repair
from the inside diameter to a depth of
50 percent of the weld thickness
extending 360° around the weld shall be
assumed.
(10) The last sentence of Measurement
or Quantification Criterion I–2.1 of
Appendix I shall be replaced by, ‘‘The
analysis or demonstration test shall
account for (a) load combinations that
could relieve plastic stress due to
shakedown and (b) any material
properties related to stress relaxation
over time.’’
(11) Replace Measurement or
Quantification Criterion I–7.1 of
Appendix I, with ‘‘An analysis shall be
performed using IWB–3600 evaluation
methods and acceptance criteria to
verify that the mitigation process will
not cause any existing flaws to grow.
(12) For any mitigated weld whose
volumetric examination detects new
flaws or growth of existing flaws in the
required examination volume that
exceed the acceptance standards of
IWB–3514 and are found to be
acceptable for continued service
through an analytical evaluation
meeting the requirements of IWB–3600
or a repair meeting the requirements of
IWA–4000 or the alternative
requirements of an ASME code case, a
report summarizing the evaluation,
along with inputs, methodologies,
assumptions, and cause of the new flaw
or flaw growth is to be provided to the
NRC prior to the weld being placed in
service other than modes 5 or 6.
PO 00000
Frm 00039
Fmt 4701
Sfmt 9990
(13) Replace the last sentence of the
Extent and Frequency of Examination
for Inspection Items C and F with,
‘‘Twenty-five percent of this population
shall be added to the ISI Program in
accordance with –2410 and shall be
examined the shorter of once each
inspection interval or the life of the
overlay.’’
(14) In Figures 2(b) and 5(b), the
dimension ‘‘b’’ must be used in place of
1⁄2 inch (13 mm), where ‘‘b’’ is equivalent
to the nominal thickness of the nozzle
or pipe being overlaid, as appropriate.
(15) For Inspection Items G, H, J, and
K, when applying the acceptance
standards of ASME B&PV Code, Section
XI, IWB–3514, the thickness ‘‘t’’ in IWB–
3514 is the thickness of the inlay or
onlay.
(16) Welds mitigated by optimized
weld overlays in Inspection Items D and
E are not permitted to be placed into a
population to be examined on a sample
basis and must be examined once each
inspection interval.
*
*
*
*
*
1 For inspections to be conducted once per
interval, the inspections shall be performed
in accordance with the schedule in Section
XI, paragraph IWB–2400, except for plants
with inservice inspection programs based on
a Section XI edition or addenda prior to the
1994 Addenda. For plants with inservice
inspection programs based on a Section XI
edition or addenda prior to the 1994
Addenda, the inspection shall be performed
in accordance with the schedule in Section
XI, paragraph IWB–2400, of the 1994
Addenda.
*
*
*
*
*
Dated at Rockville, Maryland, this 19th day
of April 2010.
For the Nuclear Regulatory Commission.
Eric J. Leeds,
Director, Office of Nuclear Reactor
Regulation.
[FR Doc. 2010–9700 Filed 5–3–10; 8:45 am]
BILLING CODE 7590–01–P
E:\FR\FM\04MYP3.SGM
04MYP3
Agencies
[Federal Register Volume 75, Number 85 (Tuesday, May 4, 2010)]
[Proposed Rules]
[Pages 24324-24361]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-9700]
[[Page 24323]]
-----------------------------------------------------------------------
Part III
Nuclear Regulatory Commission
-----------------------------------------------------------------------
10 CFR Part 50
American Society of Mechanical Engineers (ASME) Codes and New and
Revised ASME Code Cases; Proposed Rule
Federal Register / Vol. 75 , No. 85 / Tuesday, May 4, 2010 / Proposed
Rules
[[Page 24324]]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
10 CFR Part 50
RIN 3150-AI35
[NRC 2008-0554]
American Society of Mechanical Engineers (ASME) Codes and New and
Revised ASME Code Cases
AGENCY: Nuclear Regulatory Commission (NRC).
ACTION: Proposed rule.
-----------------------------------------------------------------------
SUMMARY: The NRC proposes to amend its regulations to incorporate by
reference the 2005 Addenda through 2008 Addenda of Section III,
Division 1, and the 2005 Addenda through 2008 Addenda of Section XI,
Division 1, of the ASME Boiler and Pressure Vessel Code (ASME B&PV
Code); and the 2005 Addenda and 2006 Addenda of the ASME Code for
Operation and Maintenance of Nuclear Power Plants (ASME OM Code). The
NRC also proposes to incorporate by reference ASME Code Case N-722-1,
``Additional Examinations for PWR Pressure Retaining Welds in Class 1
Components Fabricated With Alloy 600/82/182 Materials Section XI,
Division 1,'' and Code Case N-770, ``Alternative Examination
Requirements and Acceptance Standards for Class 1 PWR [Pressurized-
Water Reactor] Piping and Vessel Nozzle Butt Welds Fabricated with UNS
N06082 or UNS W86182 Weld Filler Material with or without Application
of Listed Mitigation Activities.''
DATES: Submit comments by July 19, 2010. Comments received after this
date will be considered if it is practical to do so, but the NRC is
able to ensure consideration only of comments received on or before
this date.
ADDRESSES: Please include Docket ID NRC-2008-0554 in the subject line
of your comments For instructions on submitting comments and accessing
documents related to this action, see Section I, ``Submitting Comments
and Accessing Information'' in the SUPPLEMENTARY INFORMATION section of
this document. You may submit comments by any one of the following
methods.
Federal Rulemaking Web Site: Go to https://www.regulations.gov and
search for documents filed under Docket ID NRC-2008-0554. Address
questions about NRC dockets to Carol Gallagher, telephone 301-492-3668,
e-mail Carol.Gallager@nrc.gov.
Mail comments to: Secretary, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, ATTN: Rulemakings and Adjudications Staff.
E-mail comments to: Rulemaking.Comments@nrc.gov. If you do not
receive a reply e-mail confirming that we have received your comments,
contact us directly at 301-415-1677.
Hand-deliver comments to: 11555 Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m. Federal workdays. (Telephone
301-415-1677)
Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at
301-415-1101.
You may submit comments on the information collections by the
methods indicated in the Paperwork Reduction Act Statement.
FOR FURTHER INFORMATION CONTACT: L. Mark Padovan, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone 301-415-1423, e-mail Mark.Padovan@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Submitting Comments and Accessing Information
II. Background
III. Discussion of NRC Approval of New Edition and Addenda to the
Code, ASME Code Cases N-722-1 and N-770, and Other Proposed Changes
to 10 CFR 50.55a
a. Quality Standards, ASME Codes and Institute of Electrical and
Electronics Engineers (IEEE) Standards, and Alternatives
b. Applicant/Licensee-Proposed Alternatives to the Requirements
of 10 CFR 50.55a
c. Standards Approved for Incorporation by Reference
d. ASME B&PV Code, Section III
e. ASME B&PV Code, Section XI
f. ASME OM Code
g. Reactor Coolant Pressure Boundary, Quality Group B
Components, and Quality Group C Components
h. Inservice Testing Requirements
i. Inservice Inspection Requirements
j. Substitution of the Term ``Condition'' in 10 CFR 50.55a
IV. Paragraph-by-Paragraph Discussion
V. Generic Aging Lessons Learned (GALL) Report
VI. Specific Request for Comments
VII. Voluntary Consensus Standards
VIII. Finding of No Significant Environmental Impact: Environmental
Assessment
IX. Paperwork Reduction Act Statement
X. Regulatory and Backfit Analysis
XI. Regulatory Flexibility Certification
I. Submitting Comments and Accessing Information
Comments submitted in writing or in electronic form will be posted
on the NRC Web site and on the Federal rulemaking Web site
Regulations.gov. Because your comments will not be edited to remove any
identifying or contact information, the NRC cautions you against
including any information in your submission that you do not want to be
publicly disclosed. The NRC requests that any party soliciting or
aggregating comments received from other persons for submission to the
NRC inform those persons that the NRC will not edit their comments to
remove any identifying or contact information, and therefore, they
should not include any information in their comments that they do not
want publicly disclosed.
You can access publicly available documents related to this
document, including the following documents, using the following
methods:
NRC's Public Document Room (PDR): The public may examine, and have
copied for a fee, publicly-available documents at the NRC's PDR, Room
O1-F21, One White Flint North, 11555 Rockville Pike, Rockville,
Maryland.
NRC's Agencywide Documents Access and Management System (ADAMS):
Publicly available documents created or received at the NRC are
available electronically at the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain
entry into ADAMS, which provides text and image files of NRC's public
documents. If you do not have access to ADAMS or if there are problems
in accessing the documents located in ADAMS, contact the NRC's PDR
reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to
pdr.resource@nrc.gov.
Federal Rulemaking Web Site: Public comments and supporting
materials related to this proposed rule can be found at https://www.regulations.gov by searching on Docket ID NRC-2008-0554.
----------------------------------------------------------------------------------------------------------------
Rulemaking Web
Document PDR site Reading room
----------------------------------------------------------------------------------------------------------------
ASME B&PV Code*............................................... X ............... ..............
ASME Code Case N-770*......................................... X ............... ..............
ASME Code Case N-772-1*....................................... X ............... ..............
[[Page 24325]]
ASME OM Code*................................................. X ............... ..............
EPRI Report NP-5151**, ``Evaluation of Reactor Vessel Beltline ............... ............... ..............
Integrity Following Unanticipated Operating Events,'' April
1987.........................................................
Final Safety Evaluation by the Office of Nuclear Reactor X ............... ML081140105
Regulation on Topical Report NEI 94-01, Revision 2,
``Industry Guideline for Implementing Performance-Based
Option of 10 CFR Part 50, Appendix J,'' June 25, 2008........
GALL Report, NUREG-1801, Rev.1, September 2005:
Volume 1,................................................. X ............... ML052770419
Volume 2.................................................. X ............... ML052780376
NQA-1*, ``Quality Assurance Requirements for Nuclear ............... ............... ..............
Facilities,'' 1994 Edition...................................
NUREG-1800, Rev. 1, ``Standard Review Plan for Review of X ............... ML052770566
License Renewal Applications for Nuclear Power Plants,
September 2005...............................................
Regulatory and Backfit Analysis for proposed rule............. X X ML092510270
Regulatory Guide 1.178, ``An Approach for Plant-Specific Risk- X ............... ..............
Informed Decisionmaking for Inservice Inspection of Piping''.
Regulatory Guide 1.193, Revision 2, ``ASME Code Cases not X ............... ML072470294
Approved for Use.''..........................................
Regulatory Guide 1.200, ``An Approach for Determining the X ............... ..............
Technical Adequacy of Probabilistic Risk Assessment Results
for Risk-Informed Activities''...............................
Standard Review Plan 3.9.8, ``Risk-Informed Inservice X ............... ..............
Inspection of Piping''.......................................
----------------------------------------------------------------------------------------------------------------
* Available on the ASME Web site.
** Available on the EPRI Web site.
II. Background
The ASME develops and publishes the ASME B&PV Code, which contains
requirements for the design, construction, and inservice inspection
(ISI) of nuclear power plant components; and the ASME OM Code, which
contains requirements for inservice testing (IST) of nuclear power
plant components. The ASME issues new editions of the ASME B&PV Code
every 3 years and issues addenda to the editions yearly except in years
when a new edition is issued. Periodically, the ASME publishes new
editions and addenda of the ASME OM Code. The new editions and addenda
typically revise provisions of the 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 Codes
do not significantly change Code philosophy or approach.
The ASME B&PV and OM Codes are national voluntary consensus
standards, and are required by the National Technology Transfer and
Advancement Act of 1995, Public Law 104-113, to be used by government
agencies instead of government-unique standards, unless the use of such
a standard is inconsistent with applicable law or is otherwise
impractical. It has been the NRC's practice to review new editions and
addenda of the ASME B&PV and OM Codes and periodically update 10 CFR
50.55a to incorporate newer editions and addenda by reference. The NRC
approves and/or mandates the use of editions and addenda of the Codes
in 10 CFR 50.55a through the rulemaking process of ``incorporation by
reference.'' As such, each provision of the Codes incorporated by
reference into, and mandated by, 10 CFR 50.55a constitutes a legally-
binding NRC requirement imposed by rule. As the Codes are consensus
documents, there may be disagreement among the technical experts
regarding what constitutes an acceptable level of safety. The NRC
proposed conditions enhance the provisions in the Code in instances
where the NRC has determined that the provisions do not provide an
acceptable level of safety. In other instances, research data or
experience has shown that certain Code provisions are unnecessarily
conservative, and the NRC has determined that the Code revisions are
acceptable. This rulemaking is the latest in a series of rulemakings
which incorporate by reference new editions and/or addenda of the Codes
which are approved for use, either unconditionally or with conditions.
The editions and addenda of the ASME B&PV and OM Codes were last
incorporated by reference into the regulations in a final rule dated
September 10, 2008 (73 FR 52730), as corrected on October 2, 2008 (73
FR 57235), incorporating Section III of the 2004 Edition of the ASME
B&PV Code, Section XI of the 2004 Edition of the ASME B&PV Code, and
the 2004 Edition of the ASME OM Code, subject to NRC conditions.
III. Discussion of NRC Approval of New Edition and Addenda to the
Codes, ASME Code Cases N-722-1 and N-770, and Other Proposed Changes to
10 CFR 50.55a
The NRC proposes to amend its regulations to incorporate by
reference the 2005 Addenda through 2008 Addenda of Section III,
Division 1, and Section XI, Division 1 of the ASME B&PV Code; and the
2005 Addenda and 2006 Addenda of the ASME OM Code into 10 CFR 50.55a.
The NRC also proposes to incorporate by reference Code Case N-770, and
revision 1 to Code Case N-722, which was incorporated by reference into
the NRC's regulations on September 10, 2008 (73 FR 52729).
The NRC follows a three-step process to determine acceptability of
new provisions in new editions and addenda 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, 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 in support of each new or revised Code. Second, the NRC
committee representatives discuss the Codes and technical
justifications with other cognizant NRC staff to ensure an adequate
technical review. Finally, the proposed NRC position on each Code is
reviewed and approved by NRC management as part of the rulemaking
amending 10 CFR 50.55a to incorporate by reference new editions and
addenda of the ASME Codes, and conditions on
[[Page 24326]]
their use. This regulatory process, when considered together with the
ASME's own process for developing and approving ASME Codes provides
reasonable assurances 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 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 and addenda
of the Codes identified in this rulemaking. The NRC concluded, in
accordance with the process for review of changes to the Codes, that
each of the editions and addenda of the Codes, and the 1994 Edition of
NQA-1, are technically adequate, consistent with current NRC
regulations, and approved for use with the specified conditions. Table
1 identifies where the NRC proposes to change (clarify the regulation;
or impose new, revise existing, or remove conditions in) 10 CFR 50.55a.
Due to the extent of the proposed revisions to 10 CFR 50.55a(b)(2), the
NRC is proposing to revise this portion of the regulations in its
entirety, including the redesignation of paragraphs within the section.
These proposed redesignations are also outlined in Table 1 of this
document.
Table 1--Redesignation of Paragraphs and Description of Proposed Changes
to 10 CFR 50.55a
------------------------------------------------------------------------
Current Description of
Proposed regulation regulation proposed changes
------------------------------------------------------------------------
Applicant/Licensee-Proposed Alternatives to the Requirements of 10 CFR
50.55a
------------------------------------------------------------------------
Paragraph (a)................. Paragraph (a).... Revise to title the
paragraph Quality
standards, ASME
Codes and IEEE
standards, and
alternatives.
Paragraph (a)(3).............. Paragraph (a)(3). Revise to clarify
that an alternative
is to be submitted
to, and approved by,
the NRC prior to
implementing the
alternative.
------------------------------------------------------------------------
Standards Approved for Incorporation by Reference
------------------------------------------------------------------------
Introductory text to paragraph Introductory text Revise to title the
(b). to paragraph (b). paragraph Standards
approved for
incorporation by
reference. Revise to
incorporate by
reference the ASME
B&PV Code, Section
III, Division 1
(excluding Non-
mandatory
Appendices), and
Section XI, Division
1, and ASME OM Code,
which are referenced
in paragraphs
(b)(1), (b)(2), and
(b)(3) of this
section. In
addition, ASME Code
Cases N-722-1 and
N[dash]770 would be
incorporated by
reference.
------------------------------------------------------------------------
ASME B&PV Code, Section III
------------------------------------------------------------------------
Introductory text to paragraph Introductory text Revise to clarify the
(b)(1). to paragraph wording and include
(b)(1). the 1974 Edition
(Division 1) through
the 2008 Addenda
(Division 1),
subject to
conditions. Change
``limitations and
modifications'' to
``conditions.''
Paragraph (b)(1)(ii).......... Paragraph Revise the current
(b)(1)(ii), conditions on the
``Weld leg use of stress
dimensions''. indices used for
welds in piping
design under
Subarticles NB-3600,
NC-3600, and ND-
3600. Make editorial
corrections and
additions.
Introductory text to paragraph Introductory text Revise to include the
(b)(1)(iii). to paragraph latest addenda to
(b)(1)(iii), Section III of the
``Seismic design ASME B&PV Code (2006
of piping''. Addenda through the
2008 Addenda) and
Subarticle NB-3200
of the 2004 Edition
through the 2008
Addenda of the ASME
B&PV Code subject to
the condition
outlined in
paragraph
(b)(1)(iii)(B).
Change
``limitation'' to
``condition.''
Paragraphs (b)(1)(iii)(A), ................. Add new conditions on
(b)(1)(iii)(B), and the use of
(b)(1)(iii)(C). Subarticles NB-3200,
NB-3600, NC-3600 and
ND-3600 identified
in the introductory
text to paragraph
(b)(1)(iii).
Paragraph (b)(1)(iv).......... Paragraph Revise to incorporate
(b)(1)(iv) by reference the
``Quality 1994 Edition of NQA-
assurance''. 1, ``Quality
Assurance
Requirements for
Nuclear
Facilities.''
Paragraph (b)(1)(vii)......... ................. Add a new condition
to prohibit the use
of paragraph NB-7742
of the 2006 Addenda
up to and including
the 2007 Edition and
2008 Addenda of the
ASME B&PV Code,
Section III.
------------------------------------------------------------------------
ASME B&PV Code, Section XI
------------------------------------------------------------------------
Introductory text to paragraph Introductory text Revise to clarify the
(b)(2). to paragraph wording and
(b)(2). incorporate by
reference the 2005
Addenda through 2008
Addenda of the ASME
B&PV Code into Sec.
50.55a; only
Subsections IWA,
IWB, IWC, IWD, IWE,
IWF, IWL; Mandatory
and Non-Mandatory
Appendices of
Division 1 are
incorporated by
reference into 10
CFR 50.55a, with
conditions. Change
``limitations and
modifications'' to
``conditions.''
NA............................ Paragraph Remove because
(b)(2)(i), licensees are no
``Limitations on longer using the
specific 1974 and 1977
editions and Editions and addenda
addenda''. of the ASME B&PV
Code.
Paragraph (b)(2)(i)........... Paragraph Redesignate paragraph
(b)(2)(ii), (b)(2)(ii) as
``Pressure- paragraph (b)(2)(i).
retaining welds
in ASME Code
Class 1 piping
(applies to
Table IWB-2500
and IWB-2500-1
and Category B-
J''.
NA............................ Paragraph Remove because the
(b)(2)(iii), condition in the
``Steam paragraph is
generator tubing redundant to the
(modifies 1989 Edition through
Article IWB- the 2008 Addenda of
2000)''. Section XI.
[[Page 24327]]
NA............................ Paragraph Remove because
(b)(2)(iv), licensees are no
``Pressure longer using these
retaining welds older editions and
in ASME Code addenda of the code.
Class 2 piping''.
NA............................ Paragraph Remove because
(b)(2)(v), re: licensees are no
Evaluation longer using the
procedures and Winter 1983 Addenda
acceptance and the Winter 1984
criteria for Addenda of Section
austenitic XI.
piping.
Paragraph (b)(2)(ii).......... Paragraph Redesignate paragraph
(b)(2)(vi), (b)(2)(vi) as
``Effective paragraph
edition and (b)(2)(ii). Change
addenda of ``modified and
Subsection IWE supplemented'' to
and Subsection ``conditioned.''
IWL, Section
XI''.
Paragraph (b)(2)(iii)......... Paragraph Redesignate paragraph
(b)(2)(vii), (b)(2)(vii) as
``Section XI paragraph
references to OM (b)(2)(iii).
Part 4, OM Part
6 and OM Part 10
(Table IWA-1600-
1)''.
Paragraph (b)(2)(iv).......... Paragraph Redesignate paragraph
(b)(2)(viii), (b)(2)(viii) as
``Examination of paragraph
concrete (b)(2)(iv), and
containments''. revise the
introductory text to
remove the
conditions in
redesignated
paragraphs
(b)(2)(iv)(F) and
(b)(2)(iv)(G) when
using the 2007
Edition with 2008
Addenda of the ASME
Code, Section XI.
Paragraph (b)(2)(v)........... Paragraph Redesignate paragraph
(b)(2)(ix), (b)(2)(ix) as
``Examination of paragraph (b)(2)(v),
metal and revise the
containments and introductory text to
the liners of remove the
concrete conditions in
containments''. redesignated
paragraphs
(b)(2)(v)(F),
(b)(2)(v)(G),
(b)(2)(v)(H) and
(b)(2)(v)(I) when
applying the 2004
Edition with 2006
Addenda through the
2007 Edition with
2008 Addenda of the
ASME Code, Section
XI and remove the
condition in
redesignated
paragraph
(b)(2)(v)(I) when
applying the 2004
Edition, up to and
including, the 2005
Addenda. Add a new
condition as
paragraph
(b)(2)(v)(J) on the
use of Article IWE-
5000 of Subsection
IWE when applying
the 2007 Edition up
to and including the
2008 Addenda of the
ASME Code, Section
XI.
Paragraph (b)(2)(vi).......... Paragraph Redesignate paragraph
(b)(2)(x), (b)(2)(x) as
``Quality paragraph
assurance''. (b)(2)(vi).
Paragraph (b)(2)(vii)......... Paragraph Redesignate paragraph
(b)(2)(xi) (b)(2)(xi) as
[Reserved]. paragraph
(b)(2)(vii).
Paragraph (b)(2)(viii)........ Paragraph Redesignate paragraph
(b)(2)(xii), (b)(2)(xii) as
``Underwater paragraph
welding''. (b)(2)(viii).
Paragraph (b)(2)(ix).......... Paragraph Redesignate paragraph
(b)(2)(xiii) (b)(2)(xiii) as
[Reserved]. paragraph
(b)(2)(ix).
Paragraph (b)(2)(x)........... Paragraph Redesignate paragraph
(b)(2)(xiv), (b)(2)(xiv) as
``Appendix VIII paragraph (b)(2)(x).
personnel
qualification''.
Paragraph (b)(2)(xi).......... Paragraph Redesignate paragraph
(b)(2)(xv), (b)(2)(xv) as
``Appendix VIII paragraph (b)(2)(xi)
specimen set and and revise it so
qualification that existing
requirements''. conditions would not
apply to the 2007
Edition through the
2008 Addenda of
Section XI. Change
``provisions'' to
``conditions'' in
the introductory
text to redesignated
paragraphs
(b)(2)(xi),
(b)(2)(xi)(B),
(b)(2)(xi)(C),
(b)(2)(xi)(D),
(b)(2)(xi)(E),
(b)(2)(xi)(F),
(b)(2)(xi)(G),
(b)(2)(xi)(K), and
(b)(2)(xi)(K)(1).
Change ``provisions
of'' to ``conditions
in'' in paragraph
(b)(2)(xi)(G)(3).
Change ``modified''
and ``modification''
to ``conditioned''
and ``condition'' in
(b)(2)(xi)(K)(2)(i),
(b)(2)(xi)(K)(2)(iii
),
(b)(2)(xi)(K)(3)(i),
(b)(2)(xi)(K)(3)(ii)
, (b)(2)(xi)(K)(4),
and (b)(2)(xi)(L),
where applicable.
Paragraph (b)(2)(xii)......... Paragraph Redesignate paragraph
(b)(2)(xvi), (b)(2)(xvi) as
``Appendix VIII paragraph
single side (b)(2)(xii). Change
ferritic vessel ``modified'' to
and piping and ``conditioned'' in
stainless steel redesignated
piping paragraphs
examination''. (b)(2)(xii)(A) and
(b)(2)(xii)(B).
Paragraph (b)(2)(xiii)........ Paragraph Redesignate paragraph
(b)(2)(xvii), (b)(2)(xvii) as
``Reconciliation paragraph
of Quality (b)(2)(xiii).
Requirements''.
Paragraph (b)(2)(xiv)(A)...... Paragraph Redesignate paragraph
(b)(2)(xviii)(A) (b)(2)(xviii)(A) as
, paragraph
``Certification (b)(2)(xiv)(A).
of NDE
personnel''.
Paragraph (b)(2)(xiv)(B)...... Paragraph Redesignate paragraph
(b)(2)(xviii)(B) (b)(2)(xviii)(B) as
, paragraph
``Certification (b)(2)(xiv)(B), and
of NDE revise it so that
personnel''. existing condition
would not apply to
the 2007 Edition
through the 2008
Addenda of Section
XI.
Paragraph (b)(2)(xiv)(C)...... Paragraph Redesignate paragraph
(b)(2)(xviii)(C) (b)(2)(xviii)(C) as
, paragraph
``Certification (b)(2)(xiv)(C), and
of NDE revise it such that
personnel''. the existing
conditions on the
qualification of VT-
3 examination
personnel would not
apply to the 2005
Addenda through the
2008 Addenda of
Section XI.
Paragraph (b)(2)(xv).......... Paragraph Redesignate paragraph
(b)(2)(xix), (b)(2)(xix) as
``Substitution paragraph
of alternative (b)(2)(xv), and
methods''. revise it so that
existing conditions
for the substitution
of alternative
examination methods
would not apply when
using the 2005
Addenda through the
2008 Addenda.
Paragraph (b)(2)(xvi)......... Paragraph Redesignate paragraph
(b)(2)(xx), (b)(2)(xx) as
``System leakage paragraph
tests''. (b)(2)(xvi).
Paragraph (b)(2)(xvii)........ Paragraph Redesignate paragraph
(b)(2)(xxi), (b)(2)(xxi) as
``Table IWB-2500- paragraph
1 examination (b)(2)(xvii).
requirements''.
[[Page 24328]]
Paragraph (b)(2)(xviii)....... Paragraph Redesignate paragraph
(b)(2)(xxii), (b)(2)(xxii) as
``Surface paragraph
examination''. (b)(2)(xviii).
Paragraph (b)(2)(xix)......... Paragraph Redesignate paragraph
(b)(2)(xxiii), (b)(2)(xxiii) as
``Evaluation of paragraph
thermally cut (b)(2)(xix).
surfaces''.
Paragraph (b)(2)(xx).......... Paragraph Redesignate paragraph
(b)(2)(xxiv), (b)(2)(xxiv) as
``Incorporation paragraph
of the (b)(2)(xx), and
performance revise it so that
demonstration existing condition
initiative and would not apply when
addition of using the 2007
ultrasonic Edition through the
examination 2008 Addenda.
criteria''.
Paragraph (b)(2)(xxi)......... Paragraph Redesignate paragraph
(b)(2)(xxv), (b)(2)(xxv) as
``Mitigation of paragraph
defects by (b)(2)(xxi).
modification''.
Paragraph (b)(2)(xxii)........ Paragraph Redesignate paragraph
(b)(2)(xxvi), (b)(2)(xxvi) as
``Pressure paragraph
testing class 1, (b)(2)(xxii).
2, and 3
mechanical
joints''.
Paragraph (b)(2)(xxiii)....... Paragraph Redesignate paragraph
(b)(2)(xxvii), (b)(2)(xxvii) as
``Removal of paragraph
insulation''. (b)(2)(xxiii), and
revise it to refer
to IWA-5242 of the
2003 Addenda through
the 2006 Addenda or
IWA-5241 of the 2007
Edition through the
2008 Addenda of
Section XI of the
ASME B&PV Code for
performing VT-2
visual examination
of insulated
components in
systems borated for
the purpose of
controlling
reactivity.
New paragraph (b)(2)(xxiv), NA............... Add to place
``Analysis of flaws''. conditions on the
use of Section XI,
Nonmandatory
Appendix A,
``Analysis of
Flaws.''
New paragraph (b)(2)(xxv), NA............... Add to place
``Evaluation of unanticipated condition specifying
operating events''. that Section E-1200
of the ASME B&PV
Code, Section XI,
Nonmandatory
Appendix E,
``Evaluation of
Unanticipated
Operating Events,''
is not acceptable
for use.
New paragraph (b)(2)(xxvi), NA............... Add condition that
``Nonmandatory Appendix R''. would require
licensees to submit
an alternative in
accordance with Sec.
50.55a(a)(3), and
obtain NRC
authorization of the
proposed alternative
prior to
implementing Section
XI,
Non[dash]Mandatory
Appendix R, RI-ISI
programs.
------------------------------------------------------------------------
ASME OM Code
------------------------------------------------------------------------
Introductory text to paragraph Introductory text Revise to incorporate
(b)(3). to paragraph by reference the
(b)(3). 2005 and 2006
Addenda of the ASME
OM Code; Subsections
ISTA, ISTB, ISTC,
ISTD; Mandatory
Appendices I and II;
and Nonmandatory
Appendices A through
H and J of the ASME
OM Code into Sec.
50.55a. Change
``limitations and
modifications'' to
``conditions.''
Paragraph (b)(3)(v)........... Paragraph Revise to recognize
(b)(3)(v), that snubbers are
``Subsection tested in accordance
ISTD''. with Section ISTD of
the ASME OM Code
when using the 2006
Addenda and later
editions and addenda
of Section XI of the
ASME B&PV Code.
Paragraph (b)(3)(vi).......... Paragraph Revise to state that
(b)(3)(vi), this paragraph
``Exercise applies only when
interval for using the 1999
manual valves''. through 2005 Addenda
of the ASME OM Code,
as the 2006 Addenda
of the ASME OM Code
was revised to be
consistent with the
conditions in
paragraph
(b)(3)(vi).
------------------------------------------------------------------------
Reactor Coolant Pressure Boundary, Quality Group B Components, and
Quality Group C Components
------------------------------------------------------------------------
Paragraphs (c)(3), (d)(2) and Paragraphs Revise to replace
(e)(2). (c)(3), (d)(2) ``but--'' with
and (e)(2). ``subject to the
following
conditions'' at the
end of the
introductory text to
the paragraphs for
clarity.
------------------------------------------------------------------------
Inservice Testing
------------------------------------------------------------------------
Paragraphs (f)(2), (f)(3)(v), Paragraphs Change ``limitations
and (f)(4). (f)(2), and modifications''
(f)(3)(v), and to ``conditions.''
(f)(4).
Paragraph (f)(5)(iv).......... Paragraph Revise to clarify
(f)(5)(iv). that licensees are
required to submit
requests for relief
based on
impracticality
within 12 months
after the expiration
of the IST interval
for which relief is
being sought.
------------------------------------------------------------------------
Inservice Inspection
------------------------------------------------------------------------
Paragraph (g)(2).............. Paragraph (g)(2). Revise to include
provisions for
examination and
testing snubbers in
Subsection ISTD of
the ASME OM Code,
and the optional
ASME code cases
listed in Regulatory
Guide 1.192. Change
``limitations and
modifications'' to
``conditions.''
Paragraph (g)(3)(i)........... Paragraph Revise to include
(g)(3)(i). provisions for
examination and
testing snubbers in
Subsection ISTD of
the ASME OM Code,
and the optional
ASME code cases
listed in Regulatory
Guide 1.192.
Paragraph (g)(3)(ii).......... Paragraph Revise to include the
(g)(3)(ii). provisions for
examination and
testing snubbers in
Subsection ISTD of
the ASME OM Code,
and the optional
ASME code cases
listed in Regulatory
Guide 1.192.
Paragraph (g)(3)(v)........... Paragraph Change ``limitations
(g)(3)(v). and modifications''
to ``conditions.''
[[Page 24329]]
Introductory text to paragraph Introductory text Revise to include the
(g)(4). to paragraph provisions for
(g)(4). examination and
testing snubbers in
Subsection ISTD of
the ASME OM Code.
Change
``limitation'' to
``condition'' and
``modifications'' to
``conditions.''
Paragraph (g)(4)(i)........... Paragraph Revise to include the
(g)(4)(i). provisions for
examination and
testing snubbers in
Subsection ISTD of
the ASME OM Code,
and the optional
ASME code cases
listed in Regulatory
Guide 1.192. Change
``limitations and
modifications'' to
``conditions.''
Paragraph (g)(4)(ii).......... Paragraph Revise to include the
(g)(4)(ii). provisions for
examination and
testing snubbers in
Subsection ISTD of
the ASME OM Code,
and the optional
ASME code cases
listed in Regulatory
Guide 1.192. Change
``limitations and
modifications'' to
``conditions.''
Paragraph (g)(4)(iii)......... Paragraph Revise to provide the
(g)(4)(iii). proper references to
Section XI, Table
IWB-2500-1,
``Examination
Category B-J,'' Item
Numbers B9.20, B9.21
and B9.22.
Paragraph (g)(4)(iv).......... Paragraph Change ``limitations
(g)(4)(iv). and modifications''
to ``conditions.''
Paragraph (g)(5)(iii)......... Paragraph Revise to clarify
(g)(5)(iii). that a request for
relief must be
submitted to the NRC
no later than 12
months after the
examination has been
attempted during a
given ISI interval
and the ASME B&PV
Code requirement
determined to be
impractical.
Paragraph (g)(5)(iv).......... Paragraph Revise to clarify
(g)(5)(iv). that licensees are
required to submit
requests for relief
based on
impracticality
within 12 months
after the expiration
of the ISI interval
for which relief is
being sought.
Paragraph (g)(6)(ii)(B)....... Paragraph Change
(g)(6)(ii)(B). ``modifications and
limitations'' to
``conditions.''
Paragraphs (g)(6)(ii)(E)(1), Paragraphs Revise to update the
(g)(6)(ii)(E)(2), and (g)(6)(ii)(E)(1) requirements to Code
(g)(6)(ii)(E)(3). , Case N-722-1.
(g)(6)(ii)(E)(2)
, and
(g)(6)(ii)(E)(3)
, ``Reactor
coolant pressure
boundary visual
inspections''.
New paragraph (g)(6)(ii)(F), NA............... Add to incorporate
``Inspection requirements for ASME Code Case N-
class 1 pressurized water 770, ``Alternative
reactor piping and vessel Examination
nozzle butt welds''. Requirements and
Acceptance Standards
for Class 1 PWR
Piping and Vessel
Nozzle Butt Welds
Fabricated with UNS
N06082 or UNS W86182
Weld Filler Material
With or Without
Application of
Listed Mitigation
Activities, Section
XI, Division 1,''
with conditions,
into 10 CFR 50.55a.
Footnote 1.................... Footnote 1....... Revise footnote 1 to
clarify what portion
of welds has to be
inspected during the
plant interval that
remains after
January 1, 2009.
------------------------------------------------------------------------
For redesignated paragraphs in 10 CFR 50.55a, Table 2 cross-
references the proposed regulations with the current regulations, and
Table 3 cross-references the current regulations with the proposed
regulations.
Table 2--Cross Reference of Proposed Regulations With Current
Regulations
------------------------------------------------------------------------
Description of
Proposed regulation Current proposed
regulation redesignations
------------------------------------------------------------------------
ASME B&PV Code, Section XI
------------------------------------------------------------------------
Paragraph (b)(2)(i)........... Paragraph Redesignate paragraph
(b)(2)(ii). (b)(2)(ii) as
paragraph (b)(2)(i).
Paragraph (b)(2)(ii).......... Paragraph Redesignate paragraph
(b)(2)(vi). (b)(2)(vi) as
paragraph
(b)(2)(ii).
Paragraph (b)(2)(iii)......... Paragraph Redesignate paragraph
(b)(2)(vii). (b)(2)(vii) as
paragraph
(b)(2)(iii).
Paragraph (b)(2)(iv).......... Paragraph Redesignate paragraph
(b)(2)(viii). (b)(2)(viii) as
paragraph
(b)(2)(iv).
Paragraph (b)(2)(v)........... Paragraph Redesignate paragraph
(b)(2)(ix). (b)(2)(ix) as
paragraph (b)(2)(v).
Paragraph (b)(2)(vi).......... Paragraph Redesignate paragraph
(b)(2)(x). (b)(2)(x) as
paragraph
(b)(2)(vi).
Paragraph (b)(2)(vii)......... Paragraph Redesignate paragr