Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Units 3 and 4 CA04 Structural Module ITAAC Dimensions Change, 8224-8225 [2017-01548]
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8224
Federal Register / Vol. 82, No. 14 / Tuesday, January 24, 2017 / Notices
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 52–025 and 52–026; NRC–
2008–0252]
Southern Nuclear Operating Company,
Inc., Vogtle Electric Generating Plant,
Units 3 and 4 CA04 Structural Module
ITAAC Dimensions Change
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 issuing License Amendment No. 42
to Combined Licenses (COL), NPF–91
and NPF–92. The COLs were issued to
Southern Nuclear Operating Company,
Inc. (SNC), Georgia Power Company,
Oglethorpe Power Corporation, MEAG
Power SPVM, LLC., MEAG Power SPVJ,
LLC., MEAG Power SPVP, LLC., and the
City of Dalton, Georgia (together ‘‘the
licensees’’), for construction and
operation of Vogtle Electric Generating
Plant (VEGP), Units 3 and 4, located in
Burke County, Georgia.
The granting of the exemption allows
the changes to Tier 1 information
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.
SUMMARY:
January 24, 2017.
Please refer to Docket ID
NRC–2008–0252 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
DATES:
sradovich on DSK3GMQ082PROD with NOTICES
ADDRESSES:
VerDate Sep<11>2014
19:36 Jan 23, 2017
Jkt 241001
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
a document is referenced. The request
for the amendment and exemption was
submitted by the letter dated September
18, 2015 (ADAMS Accession No.
ML15261A757).
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT:
Chandu Patel, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–3025; email: Chandu.Patel@
nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is granting an exemption
from 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. 42 to COLs, NPF–91
and NPF–92, to the licensee. The
exemption is required by Paragraph A.4
of Section VIII, ‘‘Processes for Changes
and Departures,’’ 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 related to the
design details of the containment
internal structural wall modules (CA04,
CA01, and CB65). The proposed
changes to Tier 2 information in the
VEGP Units 3 and 4 Updated Final
Safety Analysis Report (UFSAR), plantspecific Tier 1 information, and
corresponding COL Appendix C
information would allow an increase of
the concrete wall thickness tolerances.
The proposed changes would allow:
(1) A change to Tier 2 information in
UFSAR Subsection 3.8.3.6.1,
‘‘Fabrication, Erection, and Construction
of Structural Modules,’’ to allow an
increase in wall thickness tolerance
beyond the American Concrete Institute
(ACI) 117, ‘‘Standard Specifications for
Tolerance for Concrete Construction and
Material,’’ specified tolerance for some
Containment Internal Structure (CIS)
walls, and
(2) the addition of Note 10 to Tier 1
Table 3.3–1, which provides the wall
thickness tolerance deviations.
PO 00000
Frm 00051
Fmt 4703
Sfmt 4703
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.
ML15302A473.
Identical exemption documents
(except for referenced unit numbers and
license numbers) were issued to the
licensee for VEGP Units 3 and 4 (COLs
NPF–91 and NPF–92). These documents
are available in ADAMS under
Accession Nos. ML15302A418 and
ML15302A443, respectively. The
exemption is reproduced (with the
exception of abbreviated titles and
additional citations) in Section II of this
document. The amendment documents
for COLs NPF–91 and NPF–92 are
available in ADAMS under Accession
Nos. ML15302A406 and ML15302A413,
respectively. A summary of the
amendment documents is provided in
Section III of this document.
II. Exemption
Reproduced below is the exemption
document issued to VEGP, Units 3 and
4. It makes reference to the combined
safety evaluation that provides the
reasoning for the findings made by the
NRC (and listed under Item 1) in order
to grant the exemption:
1. In a letter dated September 18,
2015, Southern Nuclear Operating
Company, Inc. (licensee) requested from
the NRC an exemption to allow
departures from Tier 1 information in
the certified Design Control Document
(DCD) incorporated by reference in 10
CFR part 52, appendix D, ‘‘Design
Certification Rule for the AP1000
Design,’’ as part of license amendment
request (LAR) 15–015, ‘‘CA04 Structural
Module Inspection, Test, Analysis, and
Acceptance Criteria Dimensions
Change.’’
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. ML15302A473, the
Commission finds that:
A. The exemption is authorized by
law;
B. the exemption presents no undue
risk to public health and safety;
E:\FR\FM\24JAN1.SGM
24JAN1
Federal Register / Vol. 82, No. 14 / Tuesday, January 24, 2017 / Notices
sradovich on DSK3GMQ082PROD with NOTICES
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 Table: 3.3–1, as described in the
licensee’s request dated September 18,
2015. This exemption is related to, and
necessary for the granting of License
Amendment No. 42, 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. ML15302A473), 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.
League and its Chapter Concerned
Citizens of Shell Bluff (BREDL),
regarding the proposed amendment
request for the VEGP, Units 3 and 4.
This document can be found in ADAMS
under Accession No. ML15320A016. On
December 7, 2015, BREDL filed its
Petition and on December 23, 2015,
BREDL filed a corrected petition
(ADAMS Accession Nos. ML15341A348
and ML15357A000, respectively). On
January 4, 2016, NRC and SNC filed
their respective answers to the Petition
for Leave to Intervene and Request for
Hearing (ADAMS Accession Nos.
ML16004A471 and ML16004A479,
respectively). The Atomic Safety and
Licensing Board issued a ruling on the
VEGP Units 3 and 4 license amendment
request contention admissibility
proceeding on April 29, 2016. This
document can be found in ADAMS
under Accession No. ML16120A508.
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.
III. License Amendment Request
The request for the amendment and
exemption was submitted by the letter
dated September 18, 2015. 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
October 8, 2015 (80 FR 60937).
Comments were received during the 30day comment period.
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 18, 2015. The exemption
and amendment were issued on
December 16, 2015, as part of a
combined package to the licensee
(ADAMS Accession No. ML15302A398).
IV. Public Comments
On November 9, 2015, the staff
received a public comment from the
Blue Ridge Environmental Defense
VerDate Sep<11>2014
19:36 Jan 23, 2017
Jkt 241001
V. Conclusion
Dated at Rockville, Maryland, this 12th 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. 2017–01548 Filed 1–23–17; 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, South Carolina Public
Service Authority; Virgil C. Summer
Nuclear Station, Units 2 and 3; Tier 1
Editorial and Consistency Changes
Nuclear Regulatory
Commission.
AGENCY:
PO 00000
Frm 00052
Fmt 4703
Sfmt 4703
8225
Exemption and combined
license amendment; issuance.
ACTION:
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.
55 to Combined Licenses (COLs), 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 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 May 16, 2016, and available in
ADAMS under Accession No.
ML16137A169.
• NRC’s PDR: You may examine and
purchase copies of public documents at
SUMMARY:
E:\FR\FM\24JAN1.SGM
24JAN1
Agencies
[Federal Register Volume 82, Number 14 (Tuesday, January 24, 2017)]
[Notices]
[Pages 8224-8225]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-01548]
[[Page 8224]]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 52-025 and 52-026; NRC-2008-0252]
Southern Nuclear Operating Company, Inc., Vogtle Electric
Generating Plant, Units 3 and 4 CA04 Structural Module ITAAC Dimensions
Change
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 issuing License
Amendment No. 42 to Combined Licenses (COL), NPF-91 and NPF-92. The
COLs were issued to Southern Nuclear Operating Company, Inc. (SNC),
Georgia Power Company, Oglethorpe Power Corporation, MEAG Power SPVM,
LLC., MEAG Power SPVJ, LLC., MEAG Power SPVP, LLC., and the City of
Dalton, Georgia (together ``the licensees''), for construction and
operation of Vogtle Electric Generating Plant (VEGP), Units 3 and 4,
located in Burke County, Georgia.
The granting of the exemption allows the changes to Tier 1
information 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.
DATES: January 24, 2017.
ADDRESSES: Please refer to Docket ID NRC-2008-0252 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 a document is referenced. The
request for the amendment and exemption was submitted by the letter
dated September 18, 2015 (ADAMS Accession No. ML15261A757).
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Chandu Patel, Office of New Reactors,
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001;
telephone: 301-415-3025; email: Chandu.Patel@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is granting an exemption from 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. 42 to COLs, NPF-91 and NPF-92, to the licensee. The
exemption is required by Paragraph A.4 of Section VIII, ``Processes for
Changes and Departures,'' 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 related to the design
details of the containment internal structural wall modules (CA04,
CA01, and CB65). The proposed changes to Tier 2 information in the VEGP
Units 3 and 4 Updated Final Safety Analysis Report (UFSAR), plant-
specific Tier 1 information, and corresponding COL Appendix C
information would allow an increase of the concrete wall thickness
tolerances. The proposed changes would allow:
(1) A change to Tier 2 information in UFSAR Subsection 3.8.3.6.1,
``Fabrication, Erection, and Construction of Structural Modules,'' to
allow an increase in wall thickness tolerance beyond the American
Concrete Institute (ACI) 117, ``Standard Specifications for Tolerance
for Concrete Construction and Material,'' specified tolerance for some
Containment Internal Structure (CIS) walls, and
(2) the addition of Note 10 to Tier 1 Table 3.3-1, which provides
the wall thickness tolerance deviations.
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. ML15302A473.
Identical exemption documents (except for referenced unit numbers
and license numbers) were issued to the licensee for VEGP Units 3 and 4
(COLs NPF-91 and NPF-92). These documents are available in ADAMS under
Accession Nos. ML15302A418 and ML15302A443, respectively. The exemption
is reproduced (with the exception of abbreviated titles and additional
citations) in Section II of this document. The amendment documents for
COLs NPF-91 and NPF-92 are available in ADAMS under Accession Nos.
ML15302A406 and ML15302A413, respectively. A summary of the amendment
documents is provided in Section III of this document.
II. Exemption
Reproduced below is the exemption document issued to VEGP, Units 3
and 4. It makes reference to the combined safety evaluation that
provides the reasoning for the findings made by the NRC (and listed
under Item 1) in order to grant the exemption:
1. In a letter dated September 18, 2015, Southern Nuclear Operating
Company, Inc. (licensee) requested from the NRC an exemption to allow
departures from Tier 1 information in the certified Design Control
Document (DCD) incorporated by reference in 10 CFR part 52, appendix D,
``Design Certification Rule for the AP1000 Design,'' as part of license
amendment request (LAR) 15-015, ``CA04 Structural Module Inspection,
Test, Analysis, and Acceptance Criteria Dimensions Change.''
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.
ML15302A473, the Commission finds that:
A. The exemption is authorized by law;
B. the exemption presents no undue risk to public health and
safety;
[[Page 8225]]
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 Table: 3.3-1, as described in the licensee's
request dated September 18, 2015. This exemption is related to, and
necessary for the granting of License Amendment No. 42, 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. ML15302A473), 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 September 18, 2015. 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 October 8, 2015 (80 FR 60937). Comments were received
during the 30-day comment period.
IV. Public Comments
On November 9, 2015, the staff received a public comment from the
Blue Ridge Environmental Defense League and its Chapter Concerned
Citizens of Shell Bluff (BREDL), regarding the proposed amendment
request for the VEGP, Units 3 and 4. This document can be found in
ADAMS under Accession No. ML15320A016. On December 7, 2015, BREDL filed
its Petition and on December 23, 2015, BREDL filed a corrected petition
(ADAMS Accession Nos. ML15341A348 and ML15357A000, respectively). On
January 4, 2016, NRC and SNC filed their respective answers to the
Petition for Leave to Intervene and Request for Hearing (ADAMS
Accession Nos. ML16004A471 and ML16004A479, respectively). The Atomic
Safety and Licensing Board issued a ruling on the VEGP Units 3 and 4
license amendment request contention admissibility proceeding on April
29, 2016. This document can be found in ADAMS under Accession No.
ML16120A508.
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.
V. 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 18, 2015. The exemption and amendment were
issued on December 16, 2015, as part of a combined package to the
licensee (ADAMS Accession No. ML15302A398).
Dated at Rockville, Maryland, this 12th 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. 2017-01548 Filed 1-23-17; 8:45 am]
BILLING CODE 7590-01-P