South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Units 2 and 3; Passive Core Cooling System (PXS) Design Changes To Address Potential Gas Intrusion, 9080-9081 [2017-02211]
Download as PDF
9080
Federal Register / Vol. 82, No. 21 / Thursday, February 2, 2017 / Notices
mstockstill on DSK3G9T082PROD with NOTICES
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 22, 2017—8:30
a.m. Until 5:00 p.m.
The Subcommittee will receive a
briefing on Advanced Reactor Design
Criteria. 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), Michael
Snodderly (Telephone 301–415–2241 or
Email: Michael.Snodderly@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
participation in ACRS meetings were
published in the Federal Register on
October 17, 2016, (81 FR 71543).
Detailed meeting agendas and meeting
transcripts are available on the NRC
Web site at https://www.nrc.gov/readingrm/doc-collections/acrs. Information
regarding topics to be discussed,
changes to the agenda, whether the
meeting has been canceled or
rescheduled, and the time allotted to
present oral statements can be obtained
from the Web site cited above or by
contacting the identified DFO.
Moreover, in view of the possibility that
the schedule for ACRS meetings may be
adjusted by the Chairman as necessary
to facilitate the conduct of the meeting,
persons planning to attend should check
with these references if such
rescheduling would result in a major
inconvenience.
If attending this meeting, please enter
through the One White Flint North
building, 11555 Rockville Pike,
Rockville, Maryland. After registering
with Security, please contact Mr.
VerDate Sep<11>2014
16:31 Feb 01, 2017
Jkt 241001
Theron Brown (Telephone 240–888–
9835) to be escorted to the meeting
room.
Dated: January 26, 2017.
Mark L. Banks,
Chief, Technical Support Branch, Advisory
Committee on Reactor Safeguards.
[FR Doc. 2017–02213 Filed 2–1–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 52–027 and 52–028; NRC–
2008–0441]
South Carolina Electric & Gas
Company Virgil C. Summer Nuclear
Station, Units 2 and 3; Passive Core
Cooling System (PXS) Design Changes
To Address Potential Gas Intrusion
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.
56 to Combined Licenses (COL), NPF–
93 and NPF–94. The COLs were issued
to South Carolina Electric & Gas
Company (the licensee); for construction
and operation of the Virgil C. Summer
Nuclear Station (VCSNS) Units 2 and 3,
located in Fairfield County, South
Carolina.
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 November 25, 2016.
ADDRESSES: Please refer to Docket ID
NRC–2008–0441 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–2008–0441. 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.
SUMMARY:
PO 00000
Frm 00026
Fmt 4703
Sfmt 4703
• 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. The
request for the amendment and
exemption was submitted by letter
dated June 2, 2016 (ADAMS Accession
No. ML16154A226).
• 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: Paul
Kallan, Office of New Reactors, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–2809; email: Paul.Kallan@
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. 56 to COLs,
NPF–93 and NPF–94, to the licensee.
The exemption is required by Paragraph
A.4 of Section VIII, ‘‘Processes for
Changes and Departures,’’ 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
revise the Updated Final Safety
Analysis Report in the form of
departures from the incorporated plantspecific DCD Tier 2 information. The
proposed amendment also involves
related changes to plant-specific Tier 1
information, with corresponding
changes to the associated COL
Appendix C information.
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
E:\FR\FM\02FEN1.SGM
02FEN1
Federal Register / Vol. 82, No. 21 / Thursday, February 2, 2017 / Notices
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
10 CFR 50.12, 10 CFR 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. ML16301A270.
Identical exemption documents
(except for referenced unit numbers and
license numbers) were issued to the
licensee for VCSNS Units 2 and 3 (COLs
NPF–93 and NPF–94). The exemption
documents for VCSNS Units 2 and 3 can
be found in ADAMS under Accession
Nos. ML16301A217 and ML16301A229,
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–93 and NPF–94 are available in
ADAMS under Accession Nos.
ML16301A198 and ML16301A203,
respectively. A summary of the
amendment documents is provided in
Section III of this document.
mstockstill on DSK3G9T082PROD with NOTICES
II. Exemption
Reproduced below is the exemption
document issued to VCSNS Units 2 and
Unit 3. 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 June 2, 2016, the
licensee requested from the Commission
an exemption from the provisions of 10
CFR part 52, appendix D, Section III.B,
as part of license amendment request
16–02, ‘‘Passive Core Cooling System
(PXS) Design Changes to Address
Potential Gas Intrusion (LAR–16–02).’’
For the reasons set forth in Section
3.1, ‘‘Evaluation of Exemption,’’ of the
NRC staff’s Safety Evaluation, which
can be found in ADAMS under
Accession No. ML16301A270, 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
VerDate Sep<11>2014
16:31 Feb 01, 2017
Jkt 241001
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 June 2, 2016.
This exemption is related to, and
necessary for, the granting of License
Amendment No. 56, which is being
issued concurrently with this
exemption.
3. As explained in Section 5.0,
‘‘Environmental Consideration,’’ of the
NRC staff’s Safety Evaluation (ADAMS
Accession No. ML16301A270), 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 June 2, 2016, the
licensee requested that the NRC amend
the COLs for VCSNS, Units 2 and 3,
COLs NPF–93 and NPF–94. 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 combined license, 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
September 13, 2016 (81 FR 62926). No
comments were received during the 30day 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.
PO 00000
Frm 00027
Fmt 4703
Sfmt 4703
9081
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 June 2, 2016. The exemption and
amendment were issued on November
25, 2016 as part of a combined package
to the licensee (ADAMS Accession No.
ML16301A175).
Dated at Rockville, Maryland, this 25th 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. 2017–02211 Filed 2–1–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS) Meeting of the
ACRS Subcommittee on Future Plant
Designs; Notice of Meeting
The ACRS Subcommittee on Future
Plant Designs will hold a meeting on
February 23, 2017, Room T–2B1, 11545
Rockville Pike, Rockville, Maryland.
The meeting will be open to public
attendance.
The agenda for the subject meeting
shall be as follows:
Thursday, February 23, 2017—8:30
a.m. Until 12:00 p.m.
The Subcommittee will review the
design acceptance criteria inspection
progress and results for piping and
human factors. 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), Christina
Antonescu (Telephone 301–415–6792 or
Email: Christina.Antonescu@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
E:\FR\FM\02FEN1.SGM
02FEN1
Agencies
[Federal Register Volume 82, Number 21 (Thursday, February 2, 2017)]
[Notices]
[Pages 9080-9081]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-02211]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 52-027 and 52-028; NRC-2008-0441]
South Carolina Electric & Gas Company Virgil C. Summer Nuclear
Station, Units 2 and 3; Passive Core Cooling System (PXS) Design
Changes To Address Potential Gas Intrusion
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. 56 to Combined Licenses (COL), NPF-93 and NPF-94.
The COLs were issued to South Carolina Electric & Gas Company (the
licensee); for construction and operation of the Virgil C. Summer
Nuclear Station (VCSNS) Units 2 and 3, located in Fairfield County,
South Carolina.
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 November 25, 2016.
ADDRESSES: Please refer to Docket ID NRC-2008-0441 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-2008-0441. 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 June 2, 2016 (ADAMS Accession No. ML16154A226).
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: Paul Kallan, Office of New Reactors,
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001;
telephone: 301-415-2809; email: Paul.Kallan@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. 56 to COLs, NPF-93 and NPF-
94, to the licensee. The exemption is required by Paragraph A.4 of
Section VIII, ``Processes for Changes and Departures,'' 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 revise the Updated Final Safety Analysis Report in the form of
departures from the incorporated plant-specific DCD Tier 2 information.
The proposed amendment also involves related changes to plant-specific
Tier 1 information, with corresponding changes to the associated COL
Appendix C information.
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
[[Page 9081]]
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 10 CFR 50.12, 10 CFR 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. ML16301A270.
Identical exemption documents (except for referenced unit numbers
and license numbers) were issued to the licensee for VCSNS Units 2 and
3 (COLs NPF-93 and NPF-94). The exemption documents for VCSNS Units 2
and 3 can be found in ADAMS under Accession Nos. ML16301A217 and
ML16301A229, 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-93 and NPF-94
are available in ADAMS under Accession Nos. ML16301A198 and
ML16301A203, 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 VCSNS Units 2
and Unit 3. 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 June 2, 2016, the licensee requested from the
Commission an exemption from the provisions of 10 CFR part 52, appendix
D, Section III.B, as part of license amendment request 16-02, ``Passive
Core Cooling System (PXS) Design Changes to Address Potential Gas
Intrusion (LAR-16-02).''
For the reasons set forth in Section 3.1, ``Evaluation of
Exemption,'' of the NRC staff's Safety Evaluation, which can be found
in ADAMS under Accession No. ML16301A270, 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 June 2, 2016. This exemption is related to,
and necessary for, the granting of License Amendment No. 56, which is
being issued concurrently with this exemption.
3. As explained in Section 5.0, ``Environmental Consideration,'' of
the NRC staff's Safety Evaluation (ADAMS Accession No. ML16301A270),
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 June 2, 2016, the licensee requested that the NRC
amend the COLs for VCSNS, Units 2 and 3, COLs NPF-93 and NPF-94. 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 combined license, 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 September 13, 2016 (81 FR 62926). 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 June 2, 2016. The exemption and amendment were issued on
November 25, 2016 as part of a combined package to the licensee (ADAMS
Accession No. ML16301A175).
Dated at Rockville, Maryland, this 25th 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. 2017-02211 Filed 2-1-17; 8:45 am]
BILLING CODE 7590-01-P