Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric & Gas Company, South Carolina Public Service Authority, Addition of Instruments to Design Reliability Assurance Program, 35067-35068 [2016-12915]
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Federal Register / Vol. 81, No. 105 / Wednesday, June 1, 2016 / Notices
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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 2* information, as described in the
licensee’s request dated March 6, 2015.
This exemption is related to, and
necessary for, the granting of License
Amendment No. 44, which is being
issued concurrently with this
exemption.
3. As explained in Section 5,
‘‘Environmental Consideration,’’ of the
NRC staff’s Safety Evaluation that
supports this license amendment
(ADAMS Accession No. ML15191A194),
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 March 6, 2015, 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 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
April 14, 2015 (80 FR 20020).
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
VerDate Sep<11>2014
21:59 May 31, 2016
Jkt 238001
granted the exemption and issued the
amendment that the licensee requested
on February 1, 2016. The exemption and
amendment were issued to the licensee
as part of a combined package (ADAMS
Accession No. ML15191A128).
Dated at Rockville, Maryland, this 13th day
of May 2016.
For the Nuclear Regulatory Commission.
John McKirgan,
Acting Chief, Licensing Branch 4, Division
of New Reactor Licensing, Office of New
Reactors.
[FR Doc. 2016–12918 Filed 5–31–16; 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, Addition of
Instruments to Design Reliability
Assurance Program
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 change to the
certification information of Tier 1 of the
generic design control document (DCD)
and issuing License Amendment No. 45
to Combined Licenses (COL), NPF–93
and NPF–94. The COLs were issued to
South Carolina Electric & Gas Company
(SCE&G), and South Carolina Public
Service Authority (Santee Cooper)
(together called the licensee) in March
2012, for the construction and operation
of the Virgil C. Summer Nuclear Station
(VCSNS), Units 2 and 3, located in
Fairfield County, South Carolina.
DATES: June 1, 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:
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35067
• 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 the letter
dated July 6, 2015 (ADAMS Accession
No. ML15188A275). The licensee
supplemented this request by letter
dated March 24, 2016 (ADAMS
Accession No. ML16084A765).
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, One White Flint North,
11555 Rockville Pike, Rockville,
Maryland 20852. Specific information
on NRC’s PDR is available at https://
www.nrc.gov/reading-rm/pdr.html.
FOR FURTHER INFORMATION CONTACT:
William (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 Tier 1 information in the certified
DCD incorporated by reference in part
52 of title 10 of the Code of Federal
Regulations (10 CFR), appendix D,
‘‘Design Certification Rule for the
AP1000 Design,’’ and issuing License
Amendment No. 45 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 change
Tier 1 information. With the requested
amendment, the licensee sought
proposed changes related to the plantspecific Tier 1 tables related to the Class
1E DC and uninterruptible power
supply system. The Tier 1 tables contain
ITAAC and specifically, the licensee
sought proposed changes to Tier 1
ITAAC Table 2.6.3–1 contains lists
Category I equipment and Tier 1 ITAAC
Table 2.6.3–4 contains component
locations for this system. The proposed
changes to plant-specific Tier 1
information also contain corresponding
E:\FR\FM\01JNN1.SGM
01JNN1
35068
Federal Register / Vol. 81, No. 105 / Wednesday, June 1, 2016 / Notices
sradovich on DSK3TPTVN1PROD with NOTICES
COL Appendix C and UFSAR Tier 2
information that would facilitate the
replacement of four Class 1E DC and
uninterruptible power supply system
(IDS) spare termination boxes with a
single spare battery termination box.
The granting of the exemption allows
the changes to Tier 1 information
requested 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.
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 10 CFR
52.63(b)(1). The license amendment was
found to be acceptable as well. The
combined safety evaluation is available
in ADAMS under Accession No.
ML16075A107.
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). These documents
can be found in ADAMS under
Accession Nos. ML16075A126 and
ML16075A133, 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. ML16068A113 and ML16068A115,
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
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 July 6, 2015,
supplemented March 24, 2016, the
South Carolina Electric & Gas Company
acting on behalf of the South Carolina
Public Service Authority (hereafter
referred to as the licensees) requested
from the Nuclear Regulatory
Commission (NRC or Commission) an
exemption to allow changes to Tier 1
VerDate Sep<11>2014
21:59 May 31, 2016
Jkt 238001
information in the certified Design
Control Document (DCD) incorporated
by reference in Title 10 of the Code of
Federal Regulations (10 CFR) part 52,
appendix D, ‘‘Design Certification Rule
for the AP1000 Design,’’ as part of
license amendment request (LAR) 14–
10, ‘‘Addition of Instruments to Design
Reliability Assurance Program (D–
RAP).’’
For the reasons set forth in Section 3.1
of the NRC staff’s Safety Evaluation that
supports this license amendment, which
can be found at Agencywide Documents
Access and Management System
(ADAMS) Accession No. ML16075A107,
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 licensees are
granted an exemption from the certified
AP1000 DCD Tier 1 information, as
described in the licensee’s request dated
July 6, 2015, supplemented by letter
dated March 24, 2016. This exemption
is related to, and necessary for, the
granting of License Amendment No. 45,
which is being issued concurrently with
this exemption.
3. As explained in Section 5.0 of the
NRC staff’s Safety Evaluation that
supports this license amendment
(ADAMS Accession No. ML16075A107),
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
The request for the amendment and
exemption was submitted by the letter
dated July 6, 2015. The licensee
supplemented this request by the letter
dated March 24, 2016. The proposed
amendment is described in Section I,
above.
The Commission has determined for
these amendments that the application
PO 00000
Frm 00100
Fmt 4703
Sfmt 9990
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 1, 2015 (80 FR 52806). No
comments were received during the 30day comment period.
The NRC staff has found that the
amendment involves no significant
hazards consideration. The Commission
has determined that these amendments
satisfy the criteria for categorical
exclusion in accordance with 10 CFR
51.22(c)(9). Therefore, pursuant to 10
CFR 51.22(b), no environmental impact
statement or environmental assessment
need be prepared for these amendments.
The supplement dated March 24, 2016,
provided additional information that
clarified the application, did not expand
the scope of the application as originally
noticed, and did not change the staff’s
original proposed no significant hazards
consideration determination as
published in the Federal Register.
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 July 6, 2015, and supplemented by
the letter dated March 24, 2016. The
exemption and amendment were issued
on May 2, 2016, as part of a combined
package to the licensee (ADAMS
Accession No. ML16095A290).
Dated at Rockville, Maryland, this 24th day
of May 2016.
For the Nuclear Regulatory Commission.
John McKirgan,
Acting Chief, Licensing Branch 4, Division
of New Reactor Licensing, Office of New
Reactors.
[FR Doc. 2016–12915 Filed 5–31–16; 8:45 am]
BILLING CODE 7590–01–P
E:\FR\FM\01JNN1.SGM
01JNN1
Agencies
[Federal Register Volume 81, Number 105 (Wednesday, June 1, 2016)]
[Notices]
[Pages 35067-35068]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-12915]
-----------------------------------------------------------------------
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,
Addition of Instruments to Design Reliability Assurance Program
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 change to the certification information of Tier 1
of the generic design control document (DCD) and issuing License
Amendment No. 45 to Combined Licenses (COL), NPF-93 and NPF-94. The
COLs were issued to South Carolina Electric & Gas Company (SCE&G), and
South Carolina Public Service Authority (Santee Cooper) (together
called the licensee) in March 2012, for the construction and operation
of the Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3, located
in Fairfield County, South Carolina.
DATES: June 1, 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
the letter dated July 6, 2015 (ADAMS Accession No. ML15188A275). The
licensee supplemented this request by letter dated March 24, 2016
(ADAMS Accession No. ML16084A765).
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, One White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852. Specific information on NRC's PDR is
available at https://www.nrc.gov/reading-rm/pdr.html.
FOR FURTHER INFORMATION CONTACT: William (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 Tier 1 information in the
certified DCD incorporated by reference in part 52 of title 10 of the
Code of Federal Regulations (10 CFR), appendix D, ``Design
Certification Rule for the AP1000 Design,'' and issuing License
Amendment No. 45 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 change Tier 1 information. With the requested amendment,
the licensee sought proposed changes related to the plant-specific Tier
1 tables related to the Class 1E DC and uninterruptible power supply
system. The Tier 1 tables contain ITAAC and specifically, the licensee
sought proposed changes to Tier 1 ITAAC Table 2.6.3-1 contains lists
Category I equipment and Tier 1 ITAAC Table 2.6.3-4 contains component
locations for this system. The proposed changes to plant-specific Tier
1 information also contain corresponding
[[Page 35068]]
COL Appendix C and UFSAR Tier 2 information that would facilitate the
replacement of four Class 1E DC and uninterruptible power supply system
(IDS) spare termination boxes with a single spare battery termination
box.
The granting of the exemption allows the changes to Tier 1
information requested 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.
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 10 CFR 52.63(b)(1). The license
amendment was found to be acceptable as well. The combined safety
evaluation is available in ADAMS under Accession No. ML16075A107.
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). These documents can be found in ADAMS under
Accession Nos. ML16075A126 and ML16075A133, 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.
ML16068A113 and ML16068A115, 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 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 July 6, 2015, supplemented March 24, 2016, the
South Carolina Electric & Gas Company acting on behalf of the South
Carolina Public Service Authority (hereafter referred to as the
licensees) requested from the Nuclear Regulatory Commission (NRC or
Commission) an exemption to allow changes to Tier 1 information in the
certified Design Control Document (DCD) incorporated by reference in
Title 10 of the Code of Federal Regulations (10 CFR) part 52, appendix
D, ``Design Certification Rule for the AP1000 Design,'' as part of
license amendment request (LAR) 14-10, ``Addition of Instruments to
Design Reliability Assurance Program (D-RAP).''
For the reasons set forth in Section 3.1 of the NRC staff's Safety
Evaluation that supports this license amendment, which can be found at
Agencywide Documents Access and Management System (ADAMS) Accession No.
ML16075A107, 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 licensees are granted an exemption from the
certified AP1000 DCD Tier 1 information, as described in the licensee's
request dated July 6, 2015, supplemented by letter dated March 24,
2016. This exemption is related to, and necessary for, the granting of
License Amendment No. 45, which is being issued concurrently with this
exemption.
3. As explained in Section 5.0 of the NRC staff's Safety Evaluation
that supports this license amendment (ADAMS Accession No. ML16075A107),
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
The request for the amendment and exemption was submitted by the
letter dated July 6, 2015. The licensee supplemented this request by
the letter dated March 24, 2016. The proposed amendment is described in
Section I, above.
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 1, 2015 (80 FR 52806). No comments were received
during the 30-day comment period.
The NRC staff has found that the amendment involves no significant
hazards consideration. The Commission has determined that these
amendments satisfy the criteria for categorical exclusion in accordance
with 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no
environmental impact statement or environmental assessment need be
prepared for these amendments. The supplement dated March 24, 2016,
provided additional information that clarified the application, did not
expand the scope of the application as originally noticed, and did not
change the staff's original proposed no significant hazards
consideration determination as published in the Federal Register.
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 July 6, 2015, and supplemented by the letter dated March
24, 2016. The exemption and amendment were issued on May 2, 2016, as
part of a combined package to the licensee (ADAMS Accession No.
ML16095A290).
Dated at Rockville, Maryland, this 24th day of May 2016.
For the Nuclear Regulatory Commission.
John McKirgan,
Acting Chief, Licensing Branch 4, Division of New Reactor Licensing,
Office of New Reactors.
[FR Doc. 2016-12915 Filed 5-31-16; 8:45 am]
BILLING CODE 7590-01-P