Changes to Aging Management Guidance for Various Steam Generator Components, 88276-88277 [2016-29363]
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88276
Federal Register / Vol. 81, No. 235 / Wednesday, December 7, 2016 / Notices
ADAMS accession
No.
Document
Response to Request for Additional Information Regarding the Application for Renewal of License R–84 (September 6,
2011) ..........................................................................................................................................................................................
Armed Forces Radiobiology Research Institute—Response to NRC Request for Additional Information Questions 14–41 and
Resubmittal of Technical Specifications (October 20, 2011) (redacted version) ......................................................................
Response to Request for Additional Information Regarding the Application for License Renewal (TAC No. ME1587) (November 28, 2011) ..............................................................................................................................................................................
Armed Forces Radiobiology Research Institute, Technical Responses to NRC Request for Additional Information Re: License Renewal (TAC No. ME1587) (November 28, 2011) (redacted version) ........................................................................
Request For Additional Information Regarding The Application For License Renewal (TAC No. ME1587) (April 20, 2012) .....
Response to Request for Additional Information Regarding the Application for License Renewal (TAC No. ME1587) (January 17, 2012) ..............................................................................................................................................................................
Request for Additional Information Regarding the Application for License Renewal (September 21, 2012) ..............................
Armed Forces Radiobiology Research Institute—Response to Request for Additional Information Regarding the Application
for License Renewal (TAC ME1587) (June 28, 2013) ..............................................................................................................
U.S. Dept of Defense, Uniformed Services University of the Health Sciences—Submittal of revised Technical Specifications,
Docket 50–170 (August 27, 2014) .............................................................................................................................................
Request for Additional Information Regarding the Renewal of Facility Operating License No. R–84 for the AFRRI TRIGA Reactor Facility (December 4, 2014) .............................................................................................................................................
Letter from Stephen L. Miller Enclosing Revision of the Technical Specifications for the Armed Forces Radiobiology Research Institute Reactor (license R–84, docket 50–170) (March 30, 2015) .............................................................................
Request for Additional Information Regarding the Application for License Renewal (February 9, 2016) ....................................
Submittal of Technical Specifications for the Armed Forces Radiobiology Research Institute Facility (February 26, 2016) ......
U.S. Fish and Wildlife Service, Armed Forces Radiobiology Research Institute TRIGA Research Reactor Proposed License
Renewal, IPaC Trust Resources Report, (August 5, 2016) ......................................................................................................
U.S. Fish and Wildlife Service, Endangered Species Consultations Frequently Asked Questions, (July 15, 2013) ...................
Response to NRR Request for Additional Information Regarding the Application for License Renewal for AFRRI Facility (August 5, 2016) ..............................................................................................................................................................................
U.S. Department of Defense, Armed Forces Radiobiology Research Institute (AFRRI), Submittal of Request for Additional
Information Regarding the Application for License Renewal (TAC No. ME1587) (September 12, 2016) ................................
Reactor Operator Requalification Program for the AFRRI TRIGA Reactor Facility (September 12, 2016) .................................
Request for Additional Information Regarding the Application for License Renewal (TAC No. ME1587) (September 21, 2016)
AFRRI Email Regarding License Renewal Application (September 26, 2016) ............................................................................
AFRRI Email Response to Request for Additional Information for License Renewal (September 27, 2016) .............................
Letter from Stephen L. Miller Enclosing Revision of the Technical Specifications for the Armed Forces Radiobiology Research Institute Reactor (September 30, 2016) ........................................................................................................................
U.S. Armed Forces Radiobiology Research Institute Letter Regarding Review of Draft License R–84 (November 16, 2016) ..
Armed Forces Radiobiology Research Institute—Issuance of Renewed Facility Operating License No. R–84 for the Armed
Forces Radiobiology Research Institute Research Reactor (November 30, 2016) ..................................................................
Dated at Rockville, Maryland, this 1st day
of December, 2016.
For the Nuclear Regulatory Commission
Alexander Adams, Jr.,
Chief, Research and Test Reactors Licensing
Branch, Division of Policy and Rulemaking,
Office of Nuclear Reactor Regulation.
[FR Doc. 2016–29359 Filed 12–6–16; 8:45 am]
BILLING CODE 7590–01–P
This LR–ISG describes changes to aging
management program (AMP) XI.M19,
‘‘Steam Generators,’’ and aging
management review (AMR) items 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.
NUCLEAR REGULATORY
COMMISSION
DATES:
[NRC–2016–0108]
ADDRESSES:
This guidance is effective on
January 6, 2017.
Changes to Aging Management
Guidance for Various Steam Generator
Components
Nuclear Regulatory
Commission.
ACTION: Interim staff guidance; issuance.
asabaliauskas on DSK3SPTVN1PROD with NOTICES
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing the final
License Renewal Interim Staff Guidance
(LR–ISG), LR–ISG–2016–01, ‘‘Changes
to Aging Management Guidance for
Various Steam Generator Components.’’
SUMMARY:
VerDate Sep<11>2014
17:54 Dec 06, 2016
Jkt 241001
Please refer to Docket ID
NRC–2016–0108 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly-available
information related to this document
using any of the following methods:
• 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
PO 00000
Frm 00080
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ML11269A030
ML113410120
ML11341A133
ML113460085
ML12122A146
ML12032A054
ML12272A303
ML13182A084
ML13254A064
ML14349A319
ML15093A099
ML16040A310
ML16060A210
ML16218A224
ML16120A505
ML16232A164
ML16258A463
ML16258A464
ML16267A447
ML16270A541
ML16271A536
ML16278A111
ML16321A461
ML16077A303
section of this
document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘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 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.
FOR FURTHER INFORMATION CONTACT:
Seung Min, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
INFORMATION CONTACT
E:\FR\FM\07DEN1.SGM
07DEN1
Federal Register / Vol. 81, No. 235 / Wednesday, December 7, 2016 / Notices
asabaliauskas on DSK3SPTVN1PROD with NOTICES
0001; telephone: 301–415–2045; email:
Seung.Min@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
The NRC issues LR–ISGs to
communicate insights and lessons
learned and to address emergent issues
not covered in existing license renewal
guidance documents such as the GALL
Report, NUREG–1801, Revision 2
(December 2010); and the SRP–LR,
NUREG–1800, Revision 2 (December
2010), which are available in ADAMS
under Accession Nos. ML103490041
and ML103490036, respectively. The
NRC staff and stakeholders may use the
guidance in an LR–ISG document before
it is incorporated into a 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 staff has developed LR–ISG–
2016–01 (ADAMS Accession No.
ML16237A383) to describe changes to
the aging management guidance for
various steam generator components
within the scope of part 54 of title 10
of the Code of Federal Regulations (10
CFR), ‘‘Requirements for Renewal of
Operating Licenses for Nuclear Power
Plants.’’ 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
(interior surfaces) and tubesheets
(primary side). In addition, changes are
made to the associated AMR items in
the GALL Report and SRP–LR. This LR–
ISG also revises the Final Safety
Analysis Report supplement for GALL
Report AMP XI.M19, ‘‘Steam
Generators’’ that is documented in Table
3.0–1, ‘‘FSAR Supplement for Aging
Management of Applicable Systems’’ of
the SRP–LR.
On June 7, 2016, (81 FR 36612) the
NRC requested public comments on
draft LR–ISG–2016–01 (ADAMS
Accession No. ML16102A268). The NRC
received comments from the Nuclear
Energy Institute by letter dated July 7,
2016 (ADAMS Accession No.
ML16194A026). No other comments
were submitted. The NRC considered
those comments in developing the final
LR–ISG. Detailed responses to the
comments can be found in Appendix C
of the final LR–ISG.
The final LR–ISG–2016–01 is
approved for NRC staff and stakeholder
VerDate Sep<11>2014
17:54 Dec 06, 2016
Jkt 241001
use and will be incorporated into the
next revision of the NRC’s license
renewal guidance document. These
changes provide one acceptable
approach for managing the associated
aging effects for steam generator
components within the scope of the
license renewal rule (10 CFR part 54). 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 staff also plans to consider the
information in this LR–ISG and make
corresponding changes when finalizing
the aging management guidance for the
subsequent license renewal period (i.e.,
up to 80 years of operation), which is
documented in draft NUREG–2191,
draft ‘‘Generic Aging Lessons Learned
for Subsequent License Renewal
Report’’ (GALL–SLR) (ADAMS
Accession Nos. ML15348A111 and
ML15348A153), and draft NUREG–
2192, draft ‘‘Standard Review Plan for
Review of Subsequent License Renewal
for Nuclear Power Plants’’ (SRP–SLR)
(ADAMS Accession No. ML15348A265).
II. Congressional Review Act
This LR–ISG is a rule as defined in
the Congressional Review Act (5 U.S.C.
801–808). However, the Office of
Management and Budget has not found
it to be a major rule as defined in the
Congressional Review Act.
III. Backfitting
The NRC intends to use the guidance
in this LR–ISG when reviewing current
and future license renewal applications.
Issuance of this final LR–ISG does not
constitute backfitting as defined in 10
CFR 50.109 (the Backfit Rule). As
discussed in the ‘‘Backfitting’’ section of
the final LR–ISG–2016–01, the
backfitting provisions in 10 CFR 50.109
are not applicable to an applicant for a
renewed license. Therefore, issuance of
this LR ISG would not constitute
backfitting for licensees currently in the
license renewal process as defined in 10
CFR 50.109(a)(1). This guidance is
nonbinding and the LR–ISG does not
require current holders of renewed
licenses to take any action (i.e.,
programmatic or plant hardware
changes for managing the associated
aging effects for components within the
scope of this LR–ISG). The current
holders of renewed licenses could treat
the information presented in this LR–
ISG as ‘‘operating experience’’
information and consider this
information to ensure that relevant
AMPs are, and will remain, effective.
However, the NRC could also use the
PO 00000
Frm 00081
Fmt 4703
Sfmt 4703
88277
LR–ISG in evaluating voluntary,
licensee-initiated changes to previously
approved AMPs.
Dated at Rockville, Maryland, this 30th day
of November, 2016.
For the Nuclear Regulatory Commission.
Benjamin G. Beasley,
Acting Deputy Director, Division of License
Renewal, Office of Nuclear Reactor
Regulation.
[FR Doc. 2016–29363 Filed 12–6–16; 8:45 am]
BILLING CODE 7590–01–P
SECURITIES AND EXCHANGE
COMMISSION
[Release No. 34–79437; File No. SR–
BatsBZX–2016–78]
Self-Regulatory Organizations; Bats
BZX Exchange, Inc.; Notice of Filing
and Immediate Effectiveness of a
Proposed Rule Change To Make NonSubstantive Changes to the Fee
Schedule
December 1, 2016.
Pursuant to Section 19(b)(1) of the
Securities Exchange Act of 1934 (the
‘‘Act’’),1 and Rule 19b–4 thereunder,2
notice is hereby given that on November
29, 2016, Bats BZX Exchange, Inc. (the
‘‘Exchange’’ or ‘‘BZX’’) filed with the
Securities and Exchange Commission
(the ‘‘Commission’’) the proposed rule
change as described in Items I, II, and
III below, which Items have been
prepared by the Exchange. The
Exchange has designated the proposed
rule change as one establishing or
changing a member due, fee, or other
charge imposed by the Exchange under
Section 19(b)(3)(A)(ii) of the Act 3 and
Rule 19b–4(f)(2) thereunder,4 which
renders the proposed rule change
effective upon filing with the
Commission. The Commission is
publishing this notice to solicit
comments on the proposed rule change
from interested persons.
I. Self-Regulatory Organization’s
Statement of the Terms of the Substance
of the Proposed Rule Change
The Exchange filed a proposal to
make several non-substantive changes to
the fee schedule applicable to
Members 5 and non-members of the
Exchange pursuant to Exchange Rules
15.1(a) and (c).
1 15
U.S.C. 78s(b)(1).
CFR 240.19b–4.
3 15 U.S.C. 78s(b)(3)(A)(ii).
4 17 CFR 240.19b–4(f)(2).
5 A Member is defined as ‘‘any registered broker
or dealer that has been admitted to membership in
the Exchange.’’ See Exchange Rule 1.5(n).
2 17
E:\FR\FM\07DEN1.SGM
07DEN1
]]>Agencies
[Federal Register Volume 81, Number 235 (Wednesday, December 7, 2016)]
[Notices]
[Pages 88276-88277]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-29363]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2016-0108]
Changes to Aging Management Guidance for Various Steam Generator
Components
AGENCY: Nuclear Regulatory Commission.
ACTION: Interim staff guidance; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing the
final License Renewal Interim Staff Guidance (LR-ISG), LR-ISG-2016-01,
``Changes to Aging Management Guidance for Various Steam Generator
Components.'' This LR-ISG describes changes to aging management program
(AMP) XI.M19, ``Steam Generators,'' and aging management review (AMR)
items 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.
DATES: This guidance is effective on January 6, 2017.
ADDRESSES: Please refer to Docket ID NRC-2016-0108 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly-available information related to this document
using any of the following methods:
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.
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. The
ADAMS accession number for each document referenced (if it is available
in ADAMS) is provided the first time that it is mentioned in 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.
FOR FURTHER INFORMATION CONTACT: Seung Min, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
[[Page 88277]]
0001; telephone: 301-415-2045; email: Seung.Min@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
The NRC issues LR-ISGs to communicate insights and lessons learned
and to address emergent issues not covered in existing license renewal
guidance documents such as the GALL Report, NUREG-1801, Revision 2
(December 2010); and the SRP-LR, NUREG-1800, Revision 2 (December
2010), which are available in ADAMS under Accession Nos. ML103490041
and ML103490036, respectively. The NRC staff and stakeholders may use
the guidance in an LR-ISG document before it is incorporated into a
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 staff has developed LR-ISG-2016-01 (ADAMS Accession No.
ML16237A383) to describe changes to the aging management guidance for
various steam generator components within the scope of part 54 of title
10 of the Code of Federal Regulations (10 CFR), ``Requirements for
Renewal of Operating Licenses for Nuclear Power Plants.'' 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
(interior surfaces) and tubesheets (primary side). In addition, changes
are made to the associated AMR items in the GALL Report and SRP-LR.
This LR-ISG also revises the Final Safety Analysis Report supplement
for GALL Report AMP XI.M19, ``Steam Generators'' that is documented in
Table 3.0-1, ``FSAR Supplement for Aging Management of Applicable
Systems'' of the SRP-LR.
On June 7, 2016, (81 FR 36612) the NRC requested public comments on
draft LR-ISG-2016-01 (ADAMS Accession No. ML16102A268). The NRC
received comments from the Nuclear Energy Institute by letter dated
July 7, 2016 (ADAMS Accession No. ML16194A026). No other comments were
submitted. The NRC considered those comments in developing the final
LR-ISG. Detailed responses to the comments can be found in Appendix C
of the final LR-ISG.
The final LR-ISG-2016-01 is approved for NRC staff and stakeholder
use and will be incorporated into the next revision of the NRC's
license renewal guidance document. These changes provide one acceptable
approach for managing the associated aging effects for steam generator
components within the scope of the license renewal rule (10 CFR part
54). 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 staff also plans to consider the information in this LR-ISG and
make corresponding changes when finalizing the aging management
guidance for the subsequent license renewal period (i.e., up to 80
years of operation), which is documented in draft NUREG-2191, draft
``Generic Aging Lessons Learned for Subsequent License Renewal Report''
(GALL-SLR) (ADAMS Accession Nos. ML15348A111 and ML15348A153), and
draft NUREG-2192, draft ``Standard Review Plan for Review of Subsequent
License Renewal for Nuclear Power Plants'' (SRP-SLR) (ADAMS Accession
No. ML15348A265).
II. Congressional Review Act
This LR-ISG is a rule as defined in the Congressional Review Act (5
U.S.C. 801-808). However, the Office of Management and Budget has not
found it to be a major rule as defined in the Congressional Review Act.
III. Backfitting
The NRC intends to use the guidance in this LR-ISG when reviewing
current and future license renewal applications. Issuance of this final
LR-ISG does not constitute backfitting as defined in 10 CFR 50.109 (the
Backfit Rule). As discussed in the ``Backfitting'' section of the final
LR-ISG-2016-01, the backfitting provisions in 10 CFR 50.109 are not
applicable to an applicant for a renewed license. Therefore, issuance
of this LR ISG would not constitute backfitting for licensees currently
in the license renewal process as defined in 10 CFR 50.109(a)(1). This
guidance is nonbinding and the LR-ISG does not require current holders
of renewed licenses to take any action (i.e., programmatic or plant
hardware changes for managing the associated aging effects for
components within the scope of this LR-ISG). The current holders of
renewed licenses could treat the information presented in this LR-ISG
as ``operating experience'' information and consider this information
to ensure that relevant AMPs are, and will remain, effective. However,
the NRC could also use the LR-ISG in evaluating voluntary, licensee-
initiated changes to previously approved AMPs.
Dated at Rockville, Maryland, this 30th day of November, 2016.
For the Nuclear Regulatory Commission.
Benjamin G. Beasley,
Acting Deputy Director, Division of License Renewal, Office of Nuclear
Reactor Regulation.
[FR Doc. 2016-29363 Filed 12-6-16; 8:45 am]
BILLING CODE 7590-01-P
