Changes to Aging Management Guidance for Various Steam Generator Components, 36612-36613 [2016-13388]
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36612
Federal Register / Vol. 81, No. 109 / Tuesday, June 7, 2016 / Notices
NUCLEAR REGULATORY
COMMISSION
[NRC–2016–0108]
Changes to Aging Management
Guidance for Various Steam Generator
Components
Nuclear Regulatory
Commission.
ACTION: Draft license renewal interim
staff guidance; request for comment.
AGENCY:
asabaliauskas on DSK3SPTVN1PROD with NOTICES
VerDate Sep<11>2014
19:13 Jun 06, 2016
Jkt 238001
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
The U.S. Nuclear Regulatory
Commission (NRC) is seeking public
comment on the draft License Renewal
Interim Staff Guidance (LR–ISG), LR–
ISG–2016–01, ‘‘Changes to Aging
Management Guidance for Various
Steam Generator Components.’’ The
draft LR–ISG describes changes to the
aging management guidance for steam
generator components in NUREG–1801,
‘‘Generic Aging Lessons Learned (GALL)
Report,’’ Revision 2, and NUREG–1800,
‘‘Standard Review Plan for Review of
License Renewal Applications for
Nuclear Power Plants’’ (SRP–LR),
Revision 2. This draft LR–ISG includes
changes to GALL Report aging
management program (AMP) XI.M19,
‘‘Steam Generators,’’ and the aging
management review (AMR) items in the
GALL Report and SRP–LR for the steam
generator components.
DATES: Submit comments by July 7,
2016. Comments received after this date
will be considered, if it is practical to do
so, but the Commission is able to ensure
consideration only for comments
received on or before this date.
ADDRESSES: You may submit comments
by any of the following methods (unless
this document describes a different
method for submitting comments on a
specific subject):
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0108. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: Cindy Bladey,
Office of Administration, Mail Stop:
OWFN–12–H08, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
For additional direction on obtaining
information and submitting comments,
see ‘‘Obtaining Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
FOR FURTHER INFORMATION CONTACT: Dr.
Seung Min, Office of Nuclear Reactor
SUMMARY:
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–2045; email:
Seung.Min@nrc.gov.
SUPPLEMENTARY INFORMATION:
Please refer to Docket ID NRC–2016–
0108 when contacting the NRC about
the availability of information regarding
this action. You may obtain publiclyavailable information related to this
action by any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0108.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. Draft
LR–ISG–2016–01 is available in
ADAMS under Accession No.
ML16102A268. The GALL Report,
NUREG–1801, Revision 2 (December
2010), and the SRP–LR, NUREG–1800,
Revision 2 (December 2010), are
available in ADAMS under Accession
Nos. ML103490041 and ML103490036,
respectively. The draft GALL Report for
Subsequent License Renewal (GALL–
SLR), NUREG–2191 (December 2015),
Volumes 1 and 2, and draft Standard
Review Plan for Subsequent License
Renewal (SRP–SLR), NUREG–2192
(December 2015), are available in
ADAMS under Accession Nos.
ML15348A111, ML15348A153, and
ML15348A265, respectively.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
• NRC’s License Renewal Guidance
Web site: Guidance for license renewal
documents are also available online at
https://www.nrc.gov/reactors/operating/
licensing/renewal/guidance.html.
B. Submitting Comments
Please include Docket ID NRC–2016–
0108 in your comment submission.
The NRC cautions you not to include
identifying or contact information that
you do not want to be publicly
disclosed in your comment submission.
PO 00000
Frm 00097
Fmt 4703
Sfmt 4703
The NRC posts all comment
submissions at https://
www.regulations.gov as well as entering
the comment submissions into ADAMS.
The NRC does not routinely edit
comment submissions to remove
identifying or contact information.
If you are requesting or aggregating
comments from other persons for
submission to the NRC, then you should
inform those persons not to include
identifying or contact information that
they do not want to be publicly
disclosed in their comment submission.
Your request should state that the NRC
does not routinely edit comment
submissions to remove such information
before making the comment
submissions available to the public or
entering the comment submissions into
ADAMS.
II. Background
This draft LR–ISG describes changes
to the aging management guidance for
steam generator components in
NUREG–1801 (GALL Report), Revision
2, and NUREG–1800 (SRP–LR), Revision
2. The draft LR–ISG revises GALL
Report AMP XI.M19, ‘‘Steam
Generators,’’ and SRP–LR Sections
3.1.2.2.11 and 3.1.3.2.11, ‘‘Cracking Due
to Primary Water Stress Corrosion
Cracking.’’ Specifically, this LR–ISG
addresses the changes to aging
management guidance for managing: (a)
cracking due to primary water stress
corrosion cracking in divider plate
assemblies and tube-to-tubesheet welds,
and (b) loss of material due to boric acid
corrosion in steam generator heads and
tubesheets. In addition, changes are
made to the associated AMR items in
the GALL Report and SRP–LR. This
draft LR–ISG also revises the Final
Safety Analysis Report supplement for
the AMP that is documented in Table
3.0–1, ‘‘FSAR Supplement for Aging
Management of Applicable Systems’’ of
the SRP–LR.
These changes provide one acceptable
approach for managing the associated
aging effects for steam generator
components within the scope of the
license renewal rule (part 54 of title 10
of the Code of Federal Regulations (10
CFR), ‘‘Requirements for Renewal of
Operating Licenses for Nuclear Power
Plants’’). A licensee may cite LR–ISG–
2016–01 in its license renewal
application until the guidance in this
LR–ISG is incorporated into the license
renewal guidance documents (i.e.,
GALL Report and SRP–LR).
The NRC issues LR–ISGs to
communicate insights and lessons
learned and to address emergent issues
not covered in license renewal guidance
documents, such as the GALL Report
E:\FR\FM\07JNN1.SGM
07JNN1
Federal Register / Vol. 81, No. 109 / Tuesday, June 7, 2016 / Notices
and SRP–LR. In this way, the NRC staff
and stakeholders may use the guidance
in an LR–ISG document before it is
incorporated into a formal license
renewal guidance document revision.
The NRC staff issues LR–ISGs in
accordance with the LR–ISG Process,
Revision 2 (ADAMS Accession No.
ML100920158), for which a notice of
availability was published in the
Federal Register on June 22, 2010 (75
FR 35510).
The NRC also plans to consider the
information in this LR–ISG and make
corresponding changes when finalizing
the draft aging management guidance
for the subsequent license renewal
period (i.e., up to 80 years of operation),
which is documented in draft NUREG–
2191, ‘‘Generic Aging Lessons Learned
for Subsequent License Renewal
(GALL–SLR) Report,’’ and draft
NUREG–2192, ‘‘Standard Review Plan
for Review of Subsequent License
Renewal Applications for Nuclear
Power Plants,’’ if it is practicable to do
so in terms of the guidance development
schedule.
III. Proposed Action
By this action, the NRC is requesting
public comments on draft LR–ISG–
2016–01. This LR–ISG proposes certain
revisions to NRC guidance on
implementation of the requirements in
10 CFR part 54. The NRC staff will make
a final determination regarding issuance
of the LR–ISG after it considers any
public comments received in response
to this request.
IV. Backfitting
asabaliauskas on DSK3SPTVN1PROD with NOTICES
Issuance of this LR–ISG in final form
would not constitute backfitting as
defined in 10 CFR 50.109 (the Backfit
Rule). As discussed in the ‘‘Backfitting’’
section of draft LR–ISG–2016–01, the
LR–ISG is directed to holders of
operating licenses who are currently in
the license renewal process. The LR–
ISG is not directed to holders of
operating licenses or combined licenses
until they apply for license renewal.
The LR–ISG also is not directed to
licensees who already hold renewed
operating licenses. However, the NRC
could also use the LR–ISG in evaluating
voluntary, licensee-initiated changes to
previously-approved AMPs.
Dated at Rockville, Maryland, this 31st day
of May, 2016.
For the Nuclear Regulatory Commission.
Dennis C. Morey,
Acting Deputy Director, Division of License
Renewal, Office of Nuclear Reactor
Regulation.
[FR Doc. 2016–13388 Filed 6–6–16; 8:45 am]
BILLING CODE 7590–01–P
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19:13 Jun 06, 2016
Jkt 238001
NUCLEAR REGULATORY
COMMISSION
[NRC–2016–0107]
Biweekly Notice, Applications and
Amendments to Facility Operating
Licenses and Combined Licenses
Involving No Significant Hazards
Considerations
Nuclear Regulatory
Commission.
ACTION: Biweekly notice.
AGENCY:
PO 00000
Frm 00098
Fmt 4703
Sfmt 4703
Regulation, telephone: 301–415–1506,
email: Kay.Goldstein@nrc.gov and Lynn
Ronewicz, Office of Nuclear Reactor
Regulation, telephone: 301–415–1927,
email: Lynn.Ronewicz@nrc.gov. Both are
staff of the U.S. Nuclear Regulatory
Commission, Washington DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
Pursuant to Section 189a. (2)
of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear
Regulatory Commission (NRC) is
publishing this regular biweekly notice.
The Act requires the Commission to
publish notice of any amendments
issued, or proposed to be issued, and
grants the Commission the authority to
issue and make immediately effective
any amendment to an operating license
or combined license, as applicable,
upon a determination by the
Commission that such amendment
involves no significant hazards
consideration, notwithstanding the
pendency before the Commission of a
request for a hearing from any person.
This biweekly notice includes all
notices of amendments issued, or
proposed to be issued from May 10,
2016, to May 23, 2016. The last
biweekly notice was published on May
24, 2016 (81 FR 32800).
DATES: Comments must be filed by July
7, 2016. A request for a hearing must be
filed by August 8, 2016.
ADDRESSES: You may submit comments
by any of the following methods (unless
this document describes a different
method for submitting comments on a
specific subject):
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0107. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individuals listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: Cindy Bladey,
Office of Administration, Mail Stop:
OWFN–12–H08, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
For additional direction on obtaining
information and submitting comments,
see ‘‘Obtaining Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
FOR FURTHER INFORMATION CONTACT: Kay
Goldstein, Office of Nuclear Reactor
SUMMARY:
36613
A. Obtaining Information
Please refer to Docket ID NRC–2016–
0107 when contacting the NRC about
the availability of information for this
action. You may obtain publiclyavailable information related to this
action by any of the following methods:
• Federal rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0107.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. The
ADAMS accession number for each
document referenced (if it is available in
ADAMS) is provided the first time that
it is mentioned in the SUPPLEMENTARY
INFORMATION section of this document.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC–2016–
0107, facility name, unit number(s),
application date, and subject in your
comment submission.
The NRC cautions you not to include
identifying or contact information that
you do not want to be publicly
disclosed in your comment submission.
The NRC will post all comment
submissions at https://
www.regulations.gov as well as enter the
comment submissions into ADAMS.
The NRC does not routinely edit
comment submissions to remove
identifying or contact information.
If you are requesting or aggregating
comments from other persons for
submission to the NRC, then you should
inform those persons not to include
identifying or contact information that
E:\FR\FM\07JNN1.SGM
07JNN1
Agencies
[Federal Register Volume 81, Number 109 (Tuesday, June 7, 2016)]
[Notices]
[Pages 36612-36613]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-13388]
[[Page 36612]]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2016-0108]
Changes to Aging Management Guidance for Various Steam Generator
Components
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft license renewal interim staff guidance; request for
comment.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is seeking public
comment on the draft License Renewal Interim Staff Guidance (LR-ISG),
LR-ISG-2016-01, ``Changes to Aging Management Guidance for Various
Steam Generator Components.'' The draft LR-ISG describes changes to the
aging management guidance for steam generator components in NUREG-1801,
``Generic Aging Lessons Learned (GALL) Report,'' Revision 2, and NUREG-
1800, ``Standard Review Plan for Review of License Renewal Applications
for Nuclear Power Plants'' (SRP-LR), Revision 2. This draft LR-ISG
includes changes to GALL Report aging management program (AMP) XI.M19,
``Steam Generators,'' and the aging management review (AMR) items in
the GALL Report and SRP-LR for the steam generator components.
DATES: Submit comments by July 7, 2016. Comments received after this
date will be considered, if it is practical to do so, but the
Commission is able to ensure consideration only for comments received
on or before this date.
ADDRESSES: You may submit comments by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2016-0108. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Mail comments to: Cindy Bladey, Office of Administration,
Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Dr. Seung Min, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-2045; email: Seung.Min@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2016-0108 when contacting the NRC
about the availability of information regarding this action. You may
obtain publicly-available information related to this action by any of
the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2016-0108.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov.
Draft LR-ISG-2016-01 is available in ADAMS under Accession No.
ML16102A268. The GALL Report, NUREG-1801, Revision 2 (December 2010),
and the SRP-LR, NUREG-1800, Revision 2 (December 2010), are available
in ADAMS under Accession Nos. ML103490041 and ML103490036,
respectively. The draft GALL Report for Subsequent License Renewal
(GALL-SLR), NUREG-2191 (December 2015), Volumes 1 and 2, and draft
Standard Review Plan for Subsequent License Renewal (SRP-SLR), NUREG-
2192 (December 2015), are available in ADAMS under Accession Nos.
ML15348A111, ML15348A153, and ML15348A265, respectively.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
NRC's License Renewal Guidance Web site: Guidance for
license renewal documents are also available online at https://www.nrc.gov/reactors/operating/licensing/renewal/guidance.html.
B. Submitting Comments
Please include Docket ID NRC-2016-0108 in your comment submission.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC posts all comment submissions at https://www.regulations.gov as well as entering the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment submissions into ADAMS.
II. Background
This draft LR-ISG describes changes to the aging management
guidance for steam generator components in NUREG-1801 (GALL Report),
Revision 2, and NUREG-1800 (SRP-LR), Revision 2. The draft LR-ISG
revises GALL Report AMP XI.M19, ``Steam Generators,'' and SRP-LR
Sections 3.1.2.2.11 and 3.1.3.2.11, ``Cracking Due to Primary Water
Stress Corrosion Cracking.'' Specifically, this LR-ISG addresses the
changes to aging management guidance for managing: (a) cracking due to
primary water stress corrosion cracking in divider plate assemblies and
tube-to-tubesheet welds, and (b) loss of material due to boric acid
corrosion in steam generator heads and tubesheets. In addition, changes
are made to the associated AMR items in the GALL Report and SRP-LR.
This draft LR-ISG also revises the Final Safety Analysis Report
supplement for the AMP that is documented in Table 3.0-1, ``FSAR
Supplement for Aging Management of Applicable Systems'' of the SRP-LR.
These changes provide one acceptable approach for managing the
associated aging effects for steam generator components within the
scope of the license renewal rule (part 54 of title 10 of the Code of
Federal Regulations (10 CFR), ``Requirements for Renewal of Operating
Licenses for Nuclear Power Plants''). A licensee may cite LR-ISG-2016-
01 in its license renewal application until the guidance in this LR-ISG
is incorporated into the license renewal guidance documents (i.e., GALL
Report and SRP-LR).
The NRC issues LR-ISGs to communicate insights and lessons learned
and to address emergent issues not covered in license renewal guidance
documents, such as the GALL Report
[[Page 36613]]
and SRP-LR. In this way, the NRC staff and stakeholders may use the
guidance in an LR-ISG document before it is incorporated into a formal
license renewal guidance document revision. The NRC staff issues LR-
ISGs in accordance with the LR-ISG Process, Revision 2 (ADAMS Accession
No. ML100920158), for which a notice of availability was published in
the Federal Register on June 22, 2010 (75 FR 35510).
The NRC also plans to consider the information in this LR-ISG and
make corresponding changes when finalizing the draft aging management
guidance for the subsequent license renewal period (i.e., up to 80
years of operation), which is documented in draft NUREG-2191, ``Generic
Aging Lessons Learned for Subsequent License Renewal (GALL-SLR)
Report,'' and draft NUREG-2192, ``Standard Review Plan for Review of
Subsequent License Renewal Applications for Nuclear Power Plants,'' if
it is practicable to do so in terms of the guidance development
schedule.
III. Proposed Action
By this action, the NRC is requesting public comments on draft LR-
ISG-2016-01. This LR-ISG proposes certain revisions to NRC guidance on
implementation of the requirements in 10 CFR part 54. The NRC staff
will make a final determination regarding issuance of the LR-ISG after
it considers any public comments received in response to this request.
IV. Backfitting
Issuance of this LR-ISG in final form would not constitute
backfitting as defined in 10 CFR 50.109 (the Backfit Rule). As
discussed in the ``Backfitting'' section of draft LR-ISG-2016-01, the
LR-ISG is directed to holders of operating licenses who are currently
in the license renewal process. The LR-ISG is not directed to holders
of operating licenses or combined licenses until they apply for license
renewal. The LR-ISG also is not directed to licensees who already hold
renewed operating licenses. However, the NRC could also use the LR-ISG
in evaluating voluntary, licensee-initiated changes to previously-
approved AMPs.
Dated at Rockville, Maryland, this 31st day of May, 2016.
For the Nuclear Regulatory Commission.
Dennis C. Morey,
Acting Deputy Director, Division of License Renewal, Office of Nuclear
Reactor Regulation.
[FR Doc. 2016-13388 Filed 6-6-16; 8:45 am]
BILLING CODE 7590-01-P