Virgil C. Summer Nuclear Station, Units 2 and 3; South Carolina Electric and Gas; Changes to the Primary Sampling System, 63504-63506 [2013-24886]
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63504
Federal Register / Vol. 78, No. 206 / Thursday, October 24, 2013 / Notices
support the issuance of an exemption.
Thus, the granting of the proposed
exemption is consistent with the Atomic
Energy Act of 1954, as amended, and
the Commission’s regulations.
Therefore, the exemption is authorized
by law.
No Undue Risk to Public Health and
Safety
As described above, the requested
exemption is procedural in nature and
does not alter any substantive safety
requirements regarding the content of a
construction permit application. Due to
the procedural nature of this request, no
new accident precursors are created by
allowing an applicant to submit a
construction permit application in two
parts; thus, the probability of postulated
accidents is not increased. Similarly, the
consequences of postulated accidents
are not increased by an exemption that
authorizes an application to be
submitted in two parts. Therefore, there
is no undue risk 3 to public health and
safety.
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Consistent With Common Defense and
Security
As discussed above, the proposed
exemption would allow NWMI to
submit its application for a 10 CFR part
50 construction permit application in
two parts as provided for in 10 CFR
2.101(a)(5). The timing of submitting a
construction permit application has no
relation to security issues. Therefore,
the common defense and security is not
impacted by this exemption.
4.0 Conclusion
Accordingly, the Commission has
determined that, pursuant to 10 CFR
50.12, the exemption is authorized by
law, will not present an undue risk to
the public health and safety, and is
consistent with the common defense
and security. Also, special
circumstances are present. Therefore,
pursuant to 10 CFR 50.12, the
Commission hereby grants NWMI an
exemption from the 10 CFR 2.101(a)(5)
requirement that limits the regulation’s
applicability to licensing and regulatory
actions requiring environmental impact
statements, as described in the
provisions of 10 CFR 51.20(b). The
exemption granted allows NWMI to
submit the construction permit
application for its medical radioisotope
production facility in two parts, in
accordance with the remainder of the
provisions of 10 CFR 2.101(a)(5).
Pursuant to 10 CFR 51.32, the
Commission has determined that the
granting of this exemption will not have
a significant effect on the quality of the
human environment as it is procedural
in nature. Furthermore, the Commission
has determined that this exemption
request meets the criteria in 10 CFR
51.22(c)(25) for a licensing action that is
categorically excluded from the
requirement to prepare an
environmental assessment because the
granting of this exemption: (1) Does not
involve a significant increase in the
probability or consequences of an
accident previously evaluated, does not
create the possibility of a new or
different kind of accident from that
previously evaluated, and does not
involve a significant reduction in the
margin of safety and, thus there is no
significant hazards consideration; (2)
does not authorize the release of
effluents, thus there is no significant
change in the types or significant
increase in the amounts of any effluents
that may be released offsite; (3) neither
authorizes new radiological hazards nor
increases existing radiological hazards,
thus there is no significant increase in
individual or cumulative public or
occupational radiation exposure; (4)
does not authorize construction, thus
there is no significant construction
impact; (5) does not authorize any
placement of radiological components at
a facility or create any new accident
precursors, thus there is no significant
increase in the potential for or
consequences from radiological
accidents; and (6) allows the submission
of a construction permit application in
two parts, and thus involves a
scheduling requirement in accordance
with 10 CFR 51.22(c)(25)(vi)(G). This
exemption is effective upon issuance to
NWMI.
Dated at Rockville, Maryland, this 7th day
of October, 2013.
For the Nuclear Regulatory Commission.
Lawrence E. Kokajko,
Director, Division of Policy and Rulemaking,
Office of Nuclear Reactor Regulation.
[FR Doc. 2013–24882 Filed 10–23–13; 8:45 am]
BILLING CODE 7590–01–P
3 Risk is defined as the probability of an accident
multiplied by the consequences of an accident.
More information on risk as it is applies to NRC
regulatory activities can be found in the
Commission White Paper on Risk-Informed and
Performance Based Regulation, SECY–98–144
(ADAMS Accession No. ML003753601).
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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
and Gas; Changes to the Primary
Sampling System
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. 8
to Combined Licenses (COL), NPF–93
and NPF–94. The COLs were issued to
South Carolina Electric and Gas
(SCE&G) and South Carolina Public
Service Authority (Santee Cooper) (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
amendment requests to modify the
Primary Sampling System (PSS) design,
including changes to Tier 1 information
located in Tables 2.2.1–2, 2.3.13–1, and
2.3.13–3, Figures 2.2.1–1 ‘‘Containment
System’’ and 2.3.13–1 ‘‘Primary
Sampling System,’’ and Subsection
2.3.13, ‘‘Primary Sampling System’’ of
the Updated Final Safety Analysis
Report (UFSAR). 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.
SUMMARY:
Please refer to Docket ID
NRC–2008–0441 when contacting the
NRC about the availability of
information regarding this document.
You may access publicly-available
information related to this action by 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: 301–287–3422;
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 access publicly
ADDRESSES:
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available documents online in the NRC
Library at https://www.nrc.gov/readingrm/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 in this document
(if that document is available in
ADAMS) is provided the first time that
a document is referenced. The request
for the amendment and exemption were
submitted by letter dated February 7,
2013 (ADAMS Accession No.
ML13042A004). The licensee
supplemented this request on July 11,
2013 (ADAMS Accession No.
ML13197A431).
• 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:
Denise McGovern, Office of New
Reactors, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–0681; email:
Denise.McGovern@nrc.gov.
SUPPLEMENTARY INFORMATION:
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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. 8 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 to modify the design of the PSS.
As part of this request, the licensee
needed to change Tier 1 information
located in Tables 2.2.1–2, 2.3.13–1, and
2.3.13–3, Figures 2.2.1–1 ‘‘Containment
System’’ and 2.3.13–1 ‘‘Primary
Sampling System,’’ and Subsection
2.3.13, ‘‘Primary Sampling System’’ of
the UFSAR. These changes were
necessary as part of a design
modification which changes the type of
valve used as the air return check valve
from a check valve to a solenoidoperated valve (SOV); redesigns the PSS
inside-containment header; and adds a
PSS containment penetration.
Part of the justification for granting
the exemption was provided by the
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II. Exemption
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 to the provisions of 10
CFR Part 52, Appendix D, Section III.B,
to allow deviations from the certified
DCD Tier 1 Section 2.3.13, Tables 2.2.1–
2, 2.3.13–1, and 2.3.13–3, and Figures
2.2.1–1 and 2.3.13–1, as described in the
licensee’s request dated February 7,
2013, and as supplemented on July 11,
2013. This exemption is related to, and
necessary for the granting of License
Amendment No. 8, which is being
issued concurrently with this
exemption.
3. As explained in Section 5.0,
‘‘Environmental Consideration,’’ of the
NRC staff Safety Evaluation (ADAMS
Accession No. ML13212A242), 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
August 22, 2013.
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 February 7, 2013,
and supplemented by a letter dated July
11, 2013, the licensee requested from
the Commission an exemption from the
provisions of 10 CFR Part 52, Appendix
D, Section III.B, ‘‘Design Certification
Rule for the AP1000 Design, Scope, and
Contents,’’ as part of license amendment
request 13–06, ‘‘Changes to the Primary
Sampling System.’’
For the reasons set forth in Section
3.1, ‘‘Evaluation of Exemption,’’ of the
NRC staff’s Safety Evaluation, which
can be found in ADAMS under
Accession No. ML13212A242, 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
III. License Amendment Request
By letter dated February 7, 2013, the
licensee requested that the NRC amend
the COLs for VCSNS Units 2 and 3,
COLs NPF–93 and NPF–94. The
licensee supplemented this application
on July 11, 2013. The proposed
amendment would depart from Tier 2
Material previously incorporated into
the UFSAR. Additionally, these Tier 2
changes involve changes to Tier 1
Information in the UFSAR, and the
proposed amendment would also revise
the associated material that has been
included in Appendix C of each of the
VCSNS, Units 2 and 3 COLs. The
requested amendment will revise the
Tier 2 UFSAR information pertaining to
the PSS air return valve, and various
Tier 2 tables and sections regarding the
PSS design. These Tier 2 changes
require modifications to particular Tier
1 information located in Tables 2.2.1–2,
2.3.13–1, and 2.3.13–3, Figures 2.2.1–1
‘‘Containment System’’ and 2.3.13–1
‘‘Primary Sampling System,’’ and
Subsection 2.3.13, ‘‘Primary Sampling
System’’ of the UFSAR, as well as the
corresponding information in Appendix
C. These changes were necessary as part
of a design modification which changes
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. ML13212A242.
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. ML13212A226 and
ML13212A228. 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.
ML13212A208 and ML13212A211. A
summary of the amendment documents
is provided in Section III of this
document.
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Federal Register / Vol. 78, No. 206 / Thursday, October 24, 2013 / Notices
the type of valve used as the air return
check valve from a check valve to a
SOV; redesigns the PSS insidecontainment header; and adds a PSS
containment penetration.
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
March 4, 2013 (78 FR 14126). No
comments were received during the 60day 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 February 7, 2013, and supplemented
by letter dated July 11, 2013. The
exemption and amendment were issued
on August 22, 2013 as part of a
combined package to the licensee.
(ADAMS Accession No. ML13212A108).
Dated at Rockville, Maryland, this 7th day
of October 2013.
For the Nuclear Regulatory Commission.
Denise McGovern,
Senior Project Manager, Licensing Branch 4,
Division of New Reactor Licensing, Office of
New Reactors.
[FR Doc. 2013–24886 Filed 10–23–13; 8:45 am]
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BILLING CODE 7590–01–P
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FOR FURTHER INFORMATION CONTACT:
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–277 and 50–278; NRC–
2013–0232]
Exelon Generation Company, LLC;
Peach Bottom Atomic Power Station,
Units 2 and 3; Proposed License
Amendment To Increase the Maximum
Reactor Power Level
Nuclear Regulatory
Commission.
ACTION: Draft environmental assessment
and draft finding of no significant
Impact; opportunity to comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of amendments to Renewed
Facility Operating License Nos. DPR–44
and DPR–56, issued to Exelon
Generation Company, LLC (Exelon, the
licensee), for operation of the Peach
Bottom Atomic Power Station (PBAPS),
Units 2 and 3, located in York and
Lancaster Counties, Pennsylvania. The
proposed amendments would authorize
an increase in the maximum reactor
power level from 3514 megawatts
thermal (MWt) to 3951 MWt.
DATES: Comments must be filed by
November 25, 2013. Any potential party
as defined in Section 2.4 of Title 10 of
the Code of Federal Regulations (10
CFR), who believe access to Sensitive
Unclassified Non-Safeguards
Information (SUNSI) is necessary to
respond to this notice must request
document access by November 4, 2013.
ADDRESSES: You may submit comment
by any of the following methods (unless
this document describes a different
method for submitting comments on a
specific subject):
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2013–0232. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual(s) listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: Cindy Bladey,
Chief, Rules, Announcements, and
Directives Branch (RADB), Office of
Administration, Mail Stop: 3WFN, 06–
44M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
For additional direction on accessing
information and submitting comments,
see ‘‘Accessing Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
SUMMARY:
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Richard B. Ennis, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555; telephone: 301–415–1420;
email: Rick.Ennis@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Accessing Information and
Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC–2013–
0232 when contacting the NRC about
the availability of information regarding
this document. You may access
publicly-available information related to
this action by the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2013–0232.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publiclyavailable documents online in the NRC
Library at https://www.nrc.gov/readingrm/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 in this notice (if
that document is available in ADAMS)
is provided the first time that a
document is referenced. The application
for amendment is dated September 28,
2012, and is supplemented by letters
dated February 15, 2013, May 7, 2013,
May 24, 2013, June 4, 2013, June 27,
2013, July 30, 2013, July 31, 2013,
August 5, 2013, August 22, 2013,
August 29, 2013, and September 13,
2013 (ADAMS Accession Nos.
ML122860201, ML13051A032,
ML13129A143, ML13149A145,
ML13156A368, ML13182A025,
ML13211A457, ML13213A285,
ML13217A431, ML13240A002,
ML13241A418, and ML13260A076,
respectively). The application and some
of the supplements contain SUNSI
(proprietary information) and,
accordingly, the proprietary information
has been withheld from public
disclosure. Redacted versions of the
documents containing proprietary
information have been made publicly
available and can be accessed via the
applicable ADAMS accession numbers
listed above.
• 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.
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Agencies
[Federal Register Volume 78, Number 206 (Thursday, October 24, 2013)]
[Notices]
[Pages 63504-63506]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-24886]
-----------------------------------------------------------------------
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 and Gas; Changes to the Primary Sampling System
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. 8 to Combined Licenses (COL), NPF-93 and NPF-94. The COLs
were issued to South Carolina Electric and Gas (SCE&G) and South
Carolina Public Service Authority (Santee Cooper) (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
amendment requests to modify the Primary Sampling System (PSS) design,
including changes to Tier 1 information located in Tables 2.2.1-2,
2.3.13-1, and 2.3.13-3, Figures 2.2.1-1 ``Containment System'' and
2.3.13-1 ``Primary Sampling System,'' and Subsection 2.3.13, ``Primary
Sampling System'' of the Updated Final Safety Analysis Report (UFSAR).
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.
ADDRESSES: Please refer to Docket ID NRC-2008-0441 when contacting the
NRC about the availability of information regarding this document. You
may access publicly-available information related to this action by 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: 301-287-
3422; 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 access publicly
[[Page 63505]]
available documents online in the NRC Library 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 in this document (if that document is available in ADAMS) is
provided the first time that a document is referenced. The request for
the amendment and exemption were submitted by letter dated February 7,
2013 (ADAMS Accession No. ML13042A004). The licensee supplemented this
request on July 11, 2013 (ADAMS Accession No. ML13197A431).
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: Denise McGovern, Office of New
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-0681; email: Denise.McGovern@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. 8 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 to modify the design
of the PSS. As part of this request, the licensee needed to change Tier
1 information located in Tables 2.2.1-2, 2.3.13-1, and 2.3.13-3,
Figures 2.2.1-1 ``Containment System'' and 2.3.13-1 ``Primary Sampling
System,'' and Subsection 2.3.13, ``Primary Sampling System'' of the
UFSAR. These changes were necessary as part of a design modification
which changes the type of valve used as the air return check valve from
a check valve to a solenoid-operated valve (SOV); redesigns the PSS
inside-containment header; and adds a PSS containment penetration.
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. ML13212A242.
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. ML13212A226 and ML13212A228. 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. ML13212A208 and
ML13212A211. 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 February 7, 2013, and supplemented by a letter
dated July 11, 2013, the licensee requested from the Commission an
exemption from the provisions of 10 CFR Part 52, Appendix D, Section
III.B, ``Design Certification Rule for the AP1000 Design, Scope, and
Contents,'' as part of license amendment request 13-06, ``Changes to
the Primary Sampling System.''
For the reasons set forth in Section 3.1, ``Evaluation of
Exemption,'' of the NRC staff's Safety Evaluation, which can be found
in ADAMS under Accession No. ML13212A242, 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 to the
provisions of 10 CFR Part 52, Appendix D, Section III.B, to allow
deviations from the certified DCD Tier 1 Section 2.3.13, Tables 2.2.1-
2, 2.3.13-1, and 2.3.13-3, and Figures 2.2.1-1 and 2.3.13-1, as
described in the licensee's request dated February 7, 2013, and as
supplemented on July 11, 2013. This exemption is related to, and
necessary for the granting of License Amendment No. 8, which is being
issued concurrently with this exemption.
3. As explained in Section 5.0, ``Environmental Consideration,'' of
the NRC staff Safety Evaluation (ADAMS Accession No. ML13212A242), 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 August 22, 2013.
III. License Amendment Request
By letter dated February 7, 2013, the licensee requested that the
NRC amend the COLs for VCSNS Units 2 and 3, COLs NPF-93 and NPF-94. The
licensee supplemented this application on July 11, 2013. The proposed
amendment would depart from Tier 2 Material previously incorporated
into the UFSAR. Additionally, these Tier 2 changes involve changes to
Tier 1 Information in the UFSAR, and the proposed amendment would also
revise the associated material that has been included in Appendix C of
each of the VCSNS, Units 2 and 3 COLs. The requested amendment will
revise the Tier 2 UFSAR information pertaining to the PSS air return
valve, and various Tier 2 tables and sections regarding the PSS design.
These Tier 2 changes require modifications to particular Tier 1
information located in Tables 2.2.1-2, 2.3.13-1, and 2.3.13-3, Figures
2.2.1-1 ``Containment System'' and 2.3.13-1 ``Primary Sampling
System,'' and Subsection 2.3.13, ``Primary Sampling System'' of the
UFSAR, as well as the corresponding information in Appendix C. These
changes were necessary as part of a design modification which changes
[[Page 63506]]
the type of valve used as the air return check valve from a check valve
to a SOV; redesigns the PSS inside-containment header; and adds a PSS
containment penetration.
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 March 4, 2013 (78 FR 14126). No comments were received
during the 60-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 February 7, 2013, and supplemented by letter dated July
11, 2013. The exemption and amendment were issued on August 22, 2013 as
part of a combined package to the licensee. (ADAMS Accession No.
ML13212A108).
Dated at Rockville, Maryland, this 7th day of October 2013.
For the Nuclear Regulatory Commission.
Denise McGovern,
Senior Project Manager, Licensing Branch 4, Division of New Reactor
Licensing, Office of New Reactors.
[FR Doc. 2013-24886 Filed 10-23-13; 8:45 am]
BILLING CODE 7590-01-P