Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Units 3 and 4; Automatic Depressurization System Stage 2, 3 & 4 Valve Flow Area Changes and Clarifications, 8440-8441 [2017-01695]
Download as PDF
8440
Federal Register / Vol. 82, No. 15 / Wednesday, January 25, 2017 / Notices
outreach; and may be required to
provide supporting documentation. The
completed Profile is returned to NCUA
15 days after receipt by the contractor.
Type of Review: New collection.
Affected Public: Private Sector:
Businesses or other for-profits.
Estimated Total Annual Burden
Hours: 38.
By Gerard Poliquin, Secretary of the Board,
the National Credit Union Administration, on
January 19, 2017.
Dated: January 19, 2017.
Dawn D. Wolfgang,
NCUA PRA Clearance Officer.
[FR Doc. 2017–01654 Filed 1–24–17; 8:45 am]
NATIONAL TRANSPORTATION
SAFETY BOARD
Sunshine Act Meeting
9:30 a.m., Tuesday,
February 7, 2017.
PLACE: NTSB Conference Center, 429
L’Enfant Plaza SW., Washington, DC
20594.
STATUS: The one item is open to the
public.
MATTERS TO BE CONSIDERED:
8620A Railroad Accident Report—
BNSF Railway Train Derailment and
Subsequent Train Collision, Release
of Hazardous Materials, and Fire,
Casselton, North Dakota
(DCA14MR004)
NEWS MEDIA CONTACT: Telephone: (202)
314–6100.
The press and public may enter the
NTSB Conference Center one hour prior
to the meeting for set up and seating.
Individuals requesting specific
accommodations should contact
Rochelle Hall at (202) 314–6305 or by
email at Rochelle.Hall@ntsb.gov by
Wednesday, February 1, 2017.
The public may view the meeting via
a live or archived webcast by accessing
a link under ‘‘News & Events’’ on the
NTSB home page at www.ntsb.gov.
Schedule updates, including weatherrelated cancellations, are also available
at www.ntsb.gov.
FOR MORE INFORMATION CONTACT: Candi
Bing at (202) 314–6403 or by email at
bingc@ntsb.gov.
FOR MEDIA INFORMATION CONTACT: Eric
Weiss at (202) 314–6100 or by email at
eric.weiss@ntsb.gov.
mstockstill on DSK3G9T082PROD with NOTICES
TIME AND DATE:
Dated: January 23, 2017.
Candi R. Bing,
Federal Register Liaison Officer.
[FR Doc. 2017–01758 Filed 1–23–17; 11:15 am]
BILLING CODE 7533–01–P
20:29 Jan 24, 2017
[Docket Nos. 52–025 and 52–026; NRC–
2008–0252]
Southern Nuclear Operating Company,
Inc., Vogtle Electric Generating Plant,
Units 3 and 4; Automatic
Depressurization System Stage 2, 3 &
4 Valve Flow Area Changes and
Clarifications
Nuclear Regulatory
Commission.
ACTION: Exemption and combined
license amendment; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is granting an
exemption to allow a departure from the
certification information of Tier 1 of the
generic design control document (DCD)
and is issuing License Amendment No.
62 to Combined Licenses (COLs), NPF–
91 and NPF–92. The COLs were issued
to Southern Nuclear Operating
Company, Inc., and Georgia Power
Company, Oglethorpe Power
Corporation, MEAG Power SPVM, LLC,
MEAG Power SPVJ, LLC, MEAG Power
SPVP, LLC, Authority of Georgia, and
the City of Dalton, Georgia (the
licensee); for construction and operation
of the Vogtle Electric Generating Plant
(VEGP) Units 3 and 4, located in Burke
County, Georgia.
The granting of the exemption allows
the changes to Tier 1 information asked
for in the amendment. Because the
acceptability of the exemption was
determined in part by the acceptability
of the amendment, the exemption and
amendment are being issued
concurrently.
SUMMARY:
BILLING CODE 7535–01–P
VerDate Sep<11>2014
NUCLEAR REGULATORY
COMMISSION
Jkt 241001
The exemption and amendment
were issued on December 29, 2016.
ADDRESSES: Please refer to Docket ID
NRC–2008–0252 when contacting the
NRC about the availability of
information regarding this document.
You may access information related to
this document, which the NRC
possesses and is publicly available,
using any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2008–0252. 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 publiclyavailable documents online in the
DATES:
PO 00000
Frm 00045
Fmt 4703
Sfmt 4703
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. The
request for the amendment and
exemption was submitted by letter
dated July 25, 2016 (ADAMS Accession
No. ML16207A340).
• 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:
Chandu Patel, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–3025; email: Chandu.Patel@
nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is granting an exemption
from paragraph B of section III, ‘‘Scope
and Contents,’’ of appendix D, ‘‘Design
Certification Rule for the AP1000,’’ to
part 52 of title 10 of the Code of Federal
Regulations (10 CFR), and issuing
License Amendment No. 62 to COLs,
NPF–91 and NPF–92, to the licensee.
The exemption is required by paragraph
A.4 of Section VIII, ‘‘Processes for
Changes and Departures,’’ of appendix
D, to 10 CFR part 52 to allow the
licensee to depart from Tier 1
information. With the requested
amendment, the licensee sought
proposed changes that would allow
changes in appendix C of the COLs to
clarify the flow area for the Automatic
Depressurization System (ADS) fourth
stage squib valves and to reduce the
minimum effective flow area for the
second and third stage ADS control
valves.
Part of the justification for granting
the exemption was provided by the
review of the amendment. Because the
exemption is necessary in order to issue
the requested license amendment, the
NRC granted the exemption and issued
the amendment concurrently, rather
than in sequence. This included issuing
a combined safety evaluation containing
the NRC staff’s review of both the
exemption request and the license
amendment. The exemption met all
applicable regulatory criteria set forth in
E:\FR\FM\25JAN1.SGM
25JAN1
Federal Register / Vol. 82, No. 15 / Wednesday, January 25, 2017 / Notices
mstockstill on DSK3G9T082PROD with NOTICES
10 CFR 50.12, and 52.7, and Section
VIII.A.4 of appendix D to 10 CFR part
52. The license amendment was found
to be acceptable as well. The combined
safety evaluation is available in ADAMS
under Accession No. ML16357A681.
Identical exemption documents
(except for referenced unit numbers and
license numbers) were issued to the
licensee for VEGP Units 3 and 4 (COLs
NPF–91 and NPF–92). The exemption
documents for VEGP Units 3 and 4 can
be found in ADAMS under Accession
Nos. ML16357A659 and ML16357A665,
respectively. The exemption is
reproduced (with the exception of
abbreviated titles and additional
citations) in Section II of this document.
The amendment documents for COLs
NPF–91 and NPF–92 are available in
ADAMS under Accession Nos.
ML16357A651 and ML16357A654,
respectively. A summary of the
amendment documents is provided in
Section III of this document.
II. Exemption
Reproduced below is the exemption
document issued to VEGP Units 3 and
Unit 4. It makes reference to the
combined safety evaluation that
provides the reasoning for the findings
made by the NRC (and listed under Item
1) in order to grant the exemption:
1. In a letter dated July 25, 2016, the
licensee requested from the Commission
an exemption to allow departures from
Tier 1 information in the certified DCD
incorporated by reference in 10 CFR
part 52, appendix D, as part of license
amendment request 16–012, ‘‘Automatic
Depressurization System (ADS) Stage 2,
3, and 4 Valve Flow Area Changes and
Clarifications.’’
For the reasons set forth in Section 3.1
of the NRC staff’s Safety Evaluation,
which can be found in ADAMS under
Accession No. ML16357A681, the
Commission finds that:
A. The exemption is authorized by
law;
B. the exemption presents no undue
risk to public health and safety;
C. the exemption is consistent with
the common defense and security;
D. special circumstances are present
in that the application of the rule in this
circumstance is not necessary to serve
the underlying purpose of the rule;
E. the special circumstances outweigh
any decrease in safety that may result
from the reduction in standardization
caused by the exemption; and
F. the exemption will not result in a
significant decrease in the level of safety
otherwise provided by the design.
2. Accordingly, the licensee is granted
an exemption from the certified DCD
Tier 1 information, with corresponding
VerDate Sep<11>2014
20:29 Jan 24, 2017
Jkt 241001
changes to Appendix C of the Facility
Combined Licenses as described in the
licensee’s request dated July 25, 2016.
This exemption is related to, and
necessary for, the granting of License
Amendment No. 62, which is being
issued concurrently with this
exemption.
3. As explained in Section 5.0 of the
NRC staff’s Safety Evaluation (ADAMS
Accession No. ML16357A681), this
exemption meets the eligibility criteria
for categorical exclusion set forth in 10
CFR 51.22(c)(9). Therefore, pursuant to
10 CFR 51.22(b), no environmental
impact statement or environmental
assessment needs to be prepared in
connection with the issuance of the
exemption.
4. This exemption is effective as of the
date of its issuance.
III. License Amendment Request
By letter dated July 25, 2016 (ADAMS
Accession No. ML16207A340), the
licensee requested that the NRC amend
the COLs for VEGP, Units 3 and 4, COLs
NPF–91 and NPF–92. The proposed
amendment is described in Section I of
this Federal Register notice.
The Commission has determined for
these amendments that the application
complies with the standards and
requirements of the Atomic Energy Act
of 1954, as amended (the Act), and the
Commission’s rules and regulations.
The Commission has made appropriate
findings as required by the Act and the
Commission’s rules and regulations in
10 CFR chapter I, which are set forth in
the license amendment.
A notice of consideration of issuance
of amendment to facility operating
license or COL, as applicable, proposed
no significant hazards consideration
determination, and opportunity for a
hearing in connection with these
actions, was published in the Federal
Register on August 30, 2016 (81 FR
59659). No comments were received
during the 30-day comment period.
The Commission has determined that
these amendments satisfy the criteria for
categorical exclusion in accordance
with 10 CFR 51.22. Therefore, pursuant
to 10 CFR 51.22(b), no environmental
impact statement or environmental
assessment need be prepared for these
amendments.
IV. Conclusion
Using the reasons set forth in the
combined safety evaluation, the staff
granted the exemption and issued the
amendment that the licensee requested
on dated July 25, 2016. The exemption
and amendment were issued on
December 29, 2016, as part of a
PO 00000
Frm 00046
Fmt 4703
Sfmt 4703
8441
combined package to the licensee
(ADAMS Accession No. ML16357A640).
Dated at Rockville, Maryland, this 17th day
of January 2017.
For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
Chief, Licensing Branch 4, Division of New
Reactor Licensing, Office of New Reactors.
[FR Doc. 2017–01695 Filed 1–24–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS); Meeting of the
ACRS Subcommittee on APR 1400;
Notice of Meeting
The ACRS Subcommittee on APR
1400 will hold a meeting on February 8,
2017, Room T–2B1, 11545 Rockville
Pike, Rockville, Maryland.
The meeting will be open to public
attendance with the exception of
portions that may be closed to protect
information that is proprietary pursuant
to 5 U.S.C. 552b(c)(4). The agenda for
the subject meeting shall be as follows:
Wednesday, February 8, 2017—8:30
a.m. Until 5:00 p.m.
The Subcommittee will review topical
reports related to the APR 1400 Design
Control Document, Chapter 4,
‘‘Reactor.’’ The Subcommittee will hear
presentations by and hold discussions
with the NRC staff and other interested
persons regarding this matter. The
Subcommittee will gather information,
analyze relevant issues and facts, and
formulate proposed positions and
actions, as appropriate, for deliberation
by the Full Committee.
Members of the public desiring to
provide oral statements and/or written
comments should notify the Designated
Federal Official (DFO), Christopher
Brown (Telephone 301–415–7111 or
Email: Christopher.Brown@nrc.gov) five
days prior to the meeting, if possible, so
that appropriate arrangements can be
made. Thirty-five hard copies of each
presentation or handout should be
provided to the DFO thirty minutes
before the meeting. In addition, one
electronic copy of each presentation
should be emailed to the DFO one day
before the meeting. If an electronic copy
cannot be provided within this
timeframe, presenters should provide
the DFO with a CD containing each
presentation at least thirty minutes
before the meeting. Electronic
recordings will be permitted only
during those portions of the meeting
that are open to the public. Detailed
procedures for the conduct of and
E:\FR\FM\25JAN1.SGM
25JAN1
Agencies
[Federal Register Volume 82, Number 15 (Wednesday, January 25, 2017)]
[Notices]
[Pages 8440-8441]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-01695]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 52-025 and 52-026; NRC-2008-0252]
Southern Nuclear Operating Company, Inc., Vogtle Electric
Generating Plant, Units 3 and 4; Automatic Depressurization System
Stage 2, 3 & 4 Valve Flow Area Changes and Clarifications
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption and combined license amendment; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is granting an
exemption to allow a departure from the certification information of
Tier 1 of the generic design control document (DCD) and is issuing
License Amendment No. 62 to Combined Licenses (COLs), NPF-91 and NPF-
92. The COLs were issued to Southern Nuclear Operating Company, Inc.,
and Georgia Power Company, Oglethorpe Power Corporation, MEAG Power
SPVM, LLC, MEAG Power SPVJ, LLC, MEAG Power SPVP, LLC, Authority of
Georgia, and the City of Dalton, Georgia (the licensee); for
construction and operation of the Vogtle Electric Generating Plant
(VEGP) Units 3 and 4, located in Burke County, Georgia.
The granting of the exemption allows the changes to Tier 1
information asked for in the amendment. Because the acceptability of
the exemption was determined in part by the acceptability of the
amendment, the exemption and amendment are being issued concurrently.
DATES: The exemption and amendment were issued on December 29, 2016.
ADDRESSES: Please refer to Docket ID NRC-2008-0252 when contacting the
NRC about the availability of information regarding this document. You
may access information related to this document, which the NRC
possesses and is publicly available, using any of the following
methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2008-0252. 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. The request for the amendment and exemption was submitted by
letter dated July 25, 2016 (ADAMS Accession No. ML16207A340).
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: Chandu Patel, Office of New Reactors,
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001;
telephone: 301-415-3025; email: Chandu.Patel@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is granting an exemption from paragraph B of section III,
``Scope and Contents,'' of appendix D, ``Design Certification Rule for
the AP1000,'' to part 52 of title 10 of the Code of Federal Regulations
(10 CFR), and issuing License Amendment No. 62 to COLs, NPF-91 and NPF-
92, to the licensee. The exemption is required by paragraph A.4 of
Section VIII, ``Processes for Changes and Departures,'' of appendix D,
to 10 CFR part 52 to allow the licensee to depart from Tier 1
information. With the requested amendment, the licensee sought proposed
changes that would allow changes in appendix C of the COLs to clarify
the flow area for the Automatic Depressurization System (ADS) fourth
stage squib valves and to reduce the minimum effective flow area for
the second and third stage ADS control valves.
Part of the justification for granting the exemption was provided
by the review of the amendment. Because the exemption is necessary in
order to issue the requested license amendment, the NRC granted the
exemption and issued the amendment concurrently, rather than in
sequence. This included issuing a combined safety evaluation containing
the NRC staff's review of both the exemption request and the license
amendment. The exemption met all applicable regulatory criteria set
forth in
[[Page 8441]]
10 CFR 50.12, and 52.7, and Section VIII.A.4 of appendix D to 10 CFR
part 52. The license amendment was found to be acceptable as well. The
combined safety evaluation is available in ADAMS under Accession No.
ML16357A681.
Identical exemption documents (except for referenced unit numbers
and license numbers) were issued to the licensee for VEGP Units 3 and 4
(COLs NPF-91 and NPF-92). The exemption documents for VEGP Units 3 and
4 can be found in ADAMS under Accession Nos. ML16357A659 and
ML16357A665, respectively. The exemption is reproduced (with the
exception of abbreviated titles and additional citations) in Section II
of this document. The amendment documents for COLs NPF-91 and NPF-92
are available in ADAMS under Accession Nos. ML16357A651 and
ML16357A654, respectively. A summary of the amendment documents is
provided in Section III of this document.
II. Exemption
Reproduced below is the exemption document issued to VEGP Units 3
and Unit 4. It makes reference to the combined safety evaluation that
provides the reasoning for the findings made by the NRC (and listed
under Item 1) in order to grant the exemption:
1. In a letter dated July 25, 2016, the licensee requested from the
Commission an exemption to allow departures from Tier 1 information in
the certified DCD incorporated by reference in 10 CFR part 52, appendix
D, as part of license amendment request 16-012, ``Automatic
Depressurization System (ADS) Stage 2, 3, and 4 Valve Flow Area Changes
and Clarifications.''
For the reasons set forth in Section 3.1 of the NRC staff's Safety
Evaluation, which can be found in ADAMS under Accession No.
ML16357A681, the Commission finds that:
A. The exemption is authorized by law;
B. the exemption presents no undue risk to public health and
safety;
C. the exemption is consistent with the common defense and
security;
D. special circumstances are present in that the application of the
rule in this circumstance is not necessary to serve the underlying
purpose of the rule;
E. the special circumstances outweigh any decrease in safety that
may result from the reduction in standardization caused by the
exemption; and
F. the exemption will not result in a significant decrease in the
level of safety otherwise provided by the design.
2. Accordingly, the licensee is granted an exemption from the
certified DCD Tier 1 information, with corresponding changes to
Appendix C of the Facility Combined Licenses as described in the
licensee's request dated July 25, 2016. This exemption is related to,
and necessary for, the granting of License Amendment No. 62, which is
being issued concurrently with this exemption.
3. As explained in Section 5.0 of the NRC staff's Safety Evaluation
(ADAMS Accession No. ML16357A681), this exemption meets the eligibility
criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact
statement or environmental assessment needs to be prepared in
connection with the issuance of the exemption.
4. This exemption is effective as of the date of its issuance.
III. License Amendment Request
By letter dated July 25, 2016 (ADAMS Accession No. ML16207A340),
the licensee requested that the NRC amend the COLs for VEGP, Units 3
and 4, COLs NPF-91 and NPF-92. The proposed amendment is described in
Section I of this Federal Register notice.
The Commission has determined for these amendments that the
application complies with the standards and requirements of the Atomic
Energy Act of 1954, as amended (the Act), and the Commission's rules
and regulations. The Commission has made appropriate findings as
required by the Act and the Commission's rules and regulations in 10
CFR chapter I, which are set forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or COL, as applicable, proposed no significant
hazards consideration determination, and opportunity for a hearing in
connection with these actions, was published in the Federal Register on
August 30, 2016 (81 FR 59659). No comments were received during the 30-
day comment period.
The Commission has determined that these amendments satisfy the
criteria for categorical exclusion in accordance with 10 CFR 51.22.
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact
statement or environmental assessment need be prepared for these
amendments.
IV. Conclusion
Using the reasons set forth in the combined safety evaluation, the
staff granted the exemption and issued the amendment that the licensee
requested on dated July 25, 2016. The exemption and amendment were
issued on December 29, 2016, as part of a combined package to the
licensee (ADAMS Accession No. ML16357A640).
Dated at Rockville, Maryland, this 17th day of January 2017.
For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of
New Reactors.
[FR Doc. 2017-01695 Filed 1-24-17; 8:45 am]
BILLING CODE 7590-01-P