Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric & Gas Company; South Carolina Public Service Authority Debris Screen Related Dimensions, 19755-19756 [2017-08615]
Download as PDF
Federal Register / Vol. 82, No. 81 / Friday, April 28, 2017 / Notices
asabaliauskas on DSK3SPTVN1PROD with NOTICES
D, as part of license amendment request
16–14, ‘‘Design Reliability Assurance
Program (D–RAP) Changes.’’
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. ML17048A143, 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 related to the incontainment refueling water storage
tank vents and overflow weirs, the rod
drive motor-generator sets field control
relays, and the rod drive power supply
control cabinets, as described in the
licensee’s request dated September 22,
2016. This exemption is related to, and
necessary for the granting of License
Amendment No. 70, 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. ML17048A143), 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 September 22, 2016
(ADAMS Accession No. ML16270A582),
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
VerDate Sep<11>2014
17:38 Apr 27, 2017
Jkt 241001
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
November 8, 2016 (81 FR 78652). 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.
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 September 22, 2016.
The exemption and amendment were
issued on April 11, 2017, as part of a
combined package to the licensee
(ADAMS Accession No. ML17048A142).
Dated at Rockville, Maryland, this 14th day
of April 2017.
For the Nuclear Regulatory Commission.
Brian Hughes,
Acting Branch Chief, Licensing Branch 4,
Division of New Reactor Licensing, Office of
New Reactors.
[FR Doc. 2017–08633 Filed 4–27–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 52–027 and 52–028; NRC–
2008–0441]
Virgil C. Summer Nuclear Station,
Units 2 and 3; South Carolina Electric
& Gas Company; South Carolina
Public Service Authority Debris Screen
Related Dimensions
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.
66 to Combined Licenses (COL), NPF–
93 and NPF–94. The COLs were issued
to South Carolina Electric & Gas
SUMMARY:
PO 00000
Frm 00104
Fmt 4703
Sfmt 4703
19755
Company and the South Carolina Public
Service Authority, (both collectively
referred to as 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 March 27, 2017.
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–2008–0252. 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
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 August 12, 2016 (ADAMS
Accession No. ML16225A437).
• 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:
Ruth Reyes, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–3249; email: Ruth.Reyes@
nrc.gov.
SUPPLEMENTARY INFORMATION:
E:\FR\FM\28APN1.SGM
28APN1
asabaliauskas on DSK3SPTVN1PROD with NOTICES
19756
Federal Register / Vol. 82, No. 81 / Friday, April 28, 2017 / Notices
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. 66 to COLs,
NP–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. The proposed
changes are to information identifying
the frontal face area and screen surface
area for the In-Containment Refueling
Water Storage Tank (IRWST) screens,
the location and dimensions of the
protective plate located above the
containment recirculation (CR) screens,
and increasing the maximum Normal
Residual Heat Removal System flowrate
through the IRWST and CR screens.
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
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. ML17040A590.
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. ML17040A547 and ML17040A553,
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
VerDate Sep<11>2014
17:38 Apr 27, 2017
Jkt 241001
ADAMS under Accession Nos.
ML17040A543 and ML17040A545,
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 V. C. Summer Units
2 and 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 an application dated August 12,
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 14–11, ‘‘Debris Screen Related
Dimensions.’’
For the reasons set forth in Section 3.1
of the NRC staff’s Safety Evaluation,
which can be found at ADAMS
Accession No. ML17040A590, 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
COLs as described in the licensee’s
request dated August 12, 2016. This
exemption is related to, and necessary
for, the granting of License Amendment
No. 66, which is being issued
concurrently with this exemption.
3. As explained in Section 5.0 of the
NRC staff’s Safety Evaluation 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.
PO 00000
Frm 00105
Fmt 4703
Sfmt 9990
III. License Amendment Request
By letter dated August 12, 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
October 11, 2016 (81 FR 70182). 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.
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 August 12, 2016.
The exemption and amendment were
issued on March 27, 2017, as part of a
combined package to the licensee
(ADAMS Accession No. ML17040A530).
Dated at Rockville, Maryland, this 17th day
of April 2017.
For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
Chief, Licensing Branch 4, Division of New
Reactor Licensing, Office of New Reactors.
[FR Doc. 2017–08615 Filed 4–27–17; 8:45 am]
BILLING CODE 7590–01–P
E:\FR\FM\28APN1.SGM
28APN1
Agencies
[Federal Register Volume 82, Number 81 (Friday, April 28, 2017)]
[Notices]
[Pages 19755-19756]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-08615]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 52-027 and 52-028; NRC-2008-0441]
Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina
Electric & Gas Company; South Carolina Public Service Authority Debris
Screen Related Dimensions
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. 66 to Combined Licenses (COL), NPF-93 and NPF-94.
The COLs were issued to South Carolina Electric & Gas Company and the
South Carolina Public Service Authority, (both collectively referred to
as 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 March 27, 2017.
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-2008-0252. 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 August 12, 2016 (ADAMS Accession No. ML16225A437).
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: Ruth Reyes, Office of New Reactors,
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001;
telephone: 301-415-3249; email: Ruth.Reyes@nrc.gov.
SUPPLEMENTARY INFORMATION:
[[Page 19756]]
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. 66 to COLs, NP-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. The proposed changes are to information
identifying the frontal face area and screen surface area for the In-
Containment Refueling Water Storage Tank (IRWST) screens, the location
and dimensions of the protective plate located above the containment
recirculation (CR) screens, and increasing the maximum Normal Residual
Heat Removal System flowrate through the IRWST and CR screens.
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 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. ML17040A590.
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. ML17040A547 and
ML17040A553, 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. ML17040A543 and
ML17040A545, 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 V. C. Summer
Units 2 and 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 an application dated August 12, 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 14-11,
``Debris Screen Related Dimensions.''
For the reasons set forth in Section 3.1 of the NRC staff's Safety
Evaluation, which can be found at ADAMS Accession No. ML17040A590, 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 COLs as described in the licensee's request
dated August 12, 2016. This exemption is related to, and necessary for,
the granting of License Amendment No. 66, which is being issued
concurrently with this exemption.
3. As explained in Section 5.0 of the NRC staff's Safety Evaluation
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 August 12, 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 October 11, 2016 (81 FR 70182). 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 August 12, 2016.
The exemption and amendment were issued on March 27, 2017, as part
of a combined package to the licensee (ADAMS Accession No.
ML17040A530).
Dated at Rockville, Maryland, this 17th day of April 2017.
For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
Chief, Licensing Branch 4, Division of New Reactor Licensing, Office
of New Reactors.
[FR Doc. 2017-08615 Filed 4-27-17; 8:45 am]
BILLING CODE 7590-01-P