South Carolina Electric & Gas Company, South Carolina Public Service Authority; Virgil C. Summer Nuclear Station, Units 2 and 3; Design Reliability Assurance Program (D-RAP) Changes, 19754-19755 [2017-08633]
Download as PDF
19754
Federal Register / Vol. 82, No. 81 / Friday, April 28, 2017 / Notices
OMB Control Number: 1225–0087.
Affected Public: Private Sector—not
for-profit institutions.
Estimated Number of Respondents: 5.
Frequency: On occasion.
Total Estimated Annual Responses: 5.
Estimated Average Time per
Response: 5 minutes.
Estimated Total Annual Burden
Hours: 1 hour.
Total Estimated Annual Other Cost
Burden: $0.
Authority: 44 U.S.C. 3506(c)(2)(A).
Dated: April 24, 2017.
Michel Smyth,
Departmental Clearance Officer.
[FR Doc. 2017–08612 Filed 4–27–17; 8:45 am]
BILLING CODE 4510–23–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 52–027 and 52–028; NRC–
2008–0441]
South Carolina Electric & Gas
Company, South Carolina Public
Service Authority; Virgil C. Summer
Nuclear Station, Units 2 and 3; Design
Reliability Assurance Program (D–
RAP) Changes
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.
70 to Combined Licenses (COLs), NPF–
93 and NPF–94. The COLs were issued
to South Carolina Electric & Gas
Company and the South Carolina Public
Service Authority, (together 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.
asabaliauskas on DSK3SPTVN1PROD with NOTICES
SUMMARY:
The exemption and amendment
were issued on April 11, 2017.
ADDRESSES: Please refer to Docket ID
NRC–2008–0441 when contacting the
NRC about the availability of
information regarding this document.
DATES:
VerDate Sep<11>2014
17:38 Apr 27, 2017
Jkt 241001
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 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 September 22, 2016 and is
available in ADAMS under Accession
No. ML16270A582.
• 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:
Billy Gleaves, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–5848; email: Bill.Gleaves@
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. 70 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 (UFSAR) in the form of
departures from the incorporated plant-
PO 00000
Frm 00103
Fmt 4703
Sfmt 4703
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. Specifically,
the LAR revises the Design Reliability
Assurance Program (D–RAP) to identify
the covers for the in-containment
refueling water storage tank (IRWST)
vents and overflow weirs as the risksignificant components included in the
D–RAP and to identify that the field
control relays of each rod drive motorgenerator (MG) sets are a part of the rod
drive power supply control cabinets in
which the relays are located.
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
§§ 50.12, 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. ML17048A143.
Similar exemption documents 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. ML17048A144
and ML17048A147, respectively. The
exemption is reproduced (with the
exception of abbreviated titles and
additional citations) in Section II of this
document. The similar amendment
documents for COLs NPF–93 and NPF–
94 are available in ADAMS under
Accession Nos. ML17048A145 and
ML17048A148, 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 an application dated September
22, 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
E:\FR\FM\28APN1.SGM
28APN1
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
Agencies
[Federal Register Volume 82, Number 81 (Friday, April 28, 2017)]
[Notices]
[Pages 19754-19755]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-08633]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 52-027 and 52-028; NRC-2008-0441]
South Carolina Electric & Gas Company, South Carolina Public
Service Authority; Virgil C. Summer Nuclear Station, Units 2 and 3;
Design Reliability Assurance Program (D-RAP) Changes
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. 70 to Combined Licenses (COLs), NPF-93 and NPF-
94. The COLs were issued to South Carolina Electric & Gas Company and
the South Carolina Public Service Authority, (together 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 April 11, 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-2008-0441. 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 September 22, 2016 and is available in ADAMS under
Accession No. ML16270A582.
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: Billy Gleaves, Office of New Reactors,
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001;
telephone: 301-415-5848; email: Bill.Gleaves@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. 70 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 (UFSAR) 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. Specifically, the LAR revises
the Design Reliability Assurance Program (D-RAP) to identify the covers
for the in-containment refueling water storage tank (IRWST) vents and
overflow weirs as the risk-significant components included in the D-RAP
and to identify that the field control relays of each rod drive motor-
generator (MG) sets are a part of the rod drive power supply control
cabinets in which the relays are located.
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 Sec. Sec. 50.12, 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. ML17048A143.
Similar exemption documents 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.
ML17048A144 and ML17048A147, respectively. The exemption is reproduced
(with the exception of abbreviated titles and additional citations) in
Section II of this document. The similar amendment documents for COLs
NPF-93 and NPF-94 are available in ADAMS under Accession Nos.
ML17048A145 and ML17048A148, 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 an application dated September 22, 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
[[Page 19755]]
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 in-containment
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 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 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 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