Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Changes to the Chemical Volume Control System, 50455-50457 [2013-20144]
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Federal Register / Vol. 78, No. 160 / Monday, August 19, 2013 / Notices
containment pressure and assuring that
leakage through the primary
containment does not exceed allowable
leakage rate values.
The proposed exemption would allow
RBS to continue to use an alternate
definition of Pa of 7.6 psig. This use of
the alternate definition for Pa meets the
intent of 10 CFR part 50, appendix J
because it provides testing of the
primary containment parameters at a
bounding pressure that is calculated to
be possible throughout containment
over a sustained period following a
design basis accident.
TKELLEY on DSK3SPTVN1PROD with NOTICES
The Need for the Proposed Action
The proposed exemption is needed to
allow RBS to continue to use an
alternate definition for Pa which results
in the use of a lower pressure for
appendix J containment testing. Use of
the lower pressure reduces the burden
of modifying the test procedures,
seeking NRC authorization to change the
current TS value, and conducting the
testing at the higher pressure. In
addition, applying the literal definition
for Pa would not serve the underlying
purpose of the rule which is to test the
primary containment parameters at a
peak pressure calculated to exist over
the long term following a design basis
accident.
Environmental Impacts of the Proposed
Action
The NRC has completed its evaluation
of the proposed action and concludes
that the exemption described above
meets the intended purpose of the
requirements in 10 CFR part 50,
appendix J. The lower calculated Pa
value provides a representative
bounding pressure for evaluating the
leak-tight integrity of the primary
reactor containment and related
penetrations.
The proposed action will not
significantly increase the probability or
consequences of accidents. No changes
are being made in the types of effluents
that may be released offsite. There is no
significant increase in the amount of
any effluent released offsite. There is no
significant increase in occupational or
public radiation exposure. Therefore,
there are no significant radiological
environmental impacts associated with
the proposed action.
With regard to potential nonradiological impacts, the proposed
action does not have any foreseeable
impacts to land, air, or water resources,
including impacts to biota. In addition,
there are also no known socioeconomic
or environmental justice impacts
associated with such proposed action.
Therefore, there are no significant non-
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radiological environmental impacts
associated with the proposed action.
Accordingly, the NRC concludes that
there are no significant environmental
impacts associated with the proposed
action.
Environmental Impacts of the
Alternatives to the Proposed Action
As an alternative to the proposed
action, the staff considered denial of the
proposed action (i.e., the ‘‘no-action’’
alternative). Denial of the application
would result in no change in current
environmental impacts. The
environmental impacts of the proposed
action and the alternative action are
similar.
Alternative Use of Resources
The action does not involve the use of
any different resources than those
previously considered in the ‘‘Final
Environmental Statement,’’ NUREG–
1073, January 1985, for the RBS.
Agencies and Persons Notified
In accordance with its stated policy,
on August 6, 2013, the staff notified the
Louisiana State official, Ji Wiley, of the
Louisiana Department of Environmental
Quality, Radiation Protection Division,
regarding the environmental impact of
the proposed action. The State official
had no comments.
III. Finding of No Significant Impact
On the basis of the environmental
assessment, the NRC concludes that the
proposed action will not have a
significant effect on the quality of the
human environment. Accordingly, the
NRC has determined not to prepare an
environmental impact statement for the
proposed action.
For further details with respect to the
proposed action, see the licensee’s letter
dated August 23, 2012.
Dated at Rockville, Maryland, this 9th day
of August 2013. For the Nuclear Regulatory
Commission.
Michael T. Markley,
Chief, Plant Licensing Branch IV, Division
of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2013–20146 Filed 8–16–13; 8:45 am]
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NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 52–025, and 52–026; NRC–
2008–0252]
Vogtle Electric Generating Station,
Units 3 and 4; Southern Nuclear
Operating Company; Changes to the
Chemical Volume Control System
Nuclear Regulatory
Commission.
ACTION: Exemption and combined
license amendment; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is both 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. 12
to Combined Licenses (COL), NPF–91
and NPF–92. The COLs were issued to
Southern Nuclear Operating Company,
Inc., and Georgia Power Company,
Oglethorpe Power Corporation,
Municipal Electric Authority of Georgia,
and the City of Dalton, Georgia (the
licensee), for construction and operation
of the Vogtle Electric Generating Plant
(VEGP), Units 3 and 4, located in Burke
County, Georgia. The amendment
requests changes that modify the
Chemical and Volume Control System
(CVS), including changes to information
located in Tier 1 Tables 2.3.2–1 and
2.3.2–2, and Tier 1 Figures 2.2.1–1 and
2.3.2–1. The granting of the exemption
allows the changes to Tier 1 information
as specified in the license amendment
request. 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–2008–0252 when contacting the
NRC about the availability of
information regarding this document.
You may access information related to
this document, which the NRC
possesses and is publicly available,
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: 301–287–3422;
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
available documents online in the NRC
Library at https://www.nrc.gov/readingrm/adams.html. To begin the search,
SUMMARY:
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Federal Register / Vol. 78, No. 160 / Monday, August 19, 2013 / Notices
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. ML13172A326.
Identical exemption documents
(except for referenced unit numbers and
license numbers) were issued to the
licensee for Vogtle Units 3 and 4 (COLs
NPF–91 and NPF–92). These documents
can be found in ADAMS under
Accession Nos. ML13172A218 and
ML13172A223. 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.
ML13172A242 and ML13172A299. A
summary of the amendment documents
is provided in Section III of this
document.
II. Exemption
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 Tables 2.3.2–1 and 2.3.2–2,
and Figures 2.2.1–1 and 2.3.2–1, as
described in the licensee’s request dated
January 11, 2013, and as supplemented
on February 27, 2013 and June 11, 2013.
This exemption is related to, and
necessary for the granting of License
Amendment No. 12, which is being
issued concurrently with this
exemption.
3. As explained in Section 5.0,
‘‘Environmental Consideration,’’ of the
NRC staff’s Safety Evaluation (ADAMS
Accession No. ML13172A326), 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
July 25, 2013.
I. Introduction
TKELLEY on DSK3SPTVN1PROD with NOTICES
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 January 11,
2013 (ADAMS Accession No.
ML13016A091). The licensee
supplemented this request on February
27, 2013 (ADAMS Accession No.
ML13059A499) and June 11, 2013
(ADAMS Accession No. ML13163A356).
• NRCs 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:
Anthony Minarik, Office of New
Reactors, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–6185; email:
Anthony.Minarik@nrc.gov.
SUPPLEMENTARY INFORMATION:
Reproduced below is the exemption
document issued to Vogtle Unit 3 and
Unit 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 January 11, 2013,
and as supplemented by letters dated
February 27, 2013 and June 11, 2013,
the licensee requested from the
Commission an exemption from the
provisions of 10 CFR part 52, appendix
D, Section III.B, as part of license
amendment request 13–002, ‘‘Changes
to the Chemical and Volume Control
System (CVS) (LAR–13–002).
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. ML13172A326, 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
III. License Amendment Request
By letter dated January 11, 2013, the
licensee requested that the NRC amend
the COLs for VEGP, Units 3 and 4, COLs
NPF–91 and NPF–92. The licensee
supplemented this application on
February 27, 2013, and June 11, 2013.
The proposed amendment would depart
from the UFSAR Tier 1 material, and
would revise the associated material
that has been included in Appendix C
of each of the VEGP, Units 3 and 4,
COLs. The requested amendment will
revise the Tier 2 UFSAR information
pertaining to the CVS, found throughout
the UFSAR. These Tier 2 changes
require modifications to particular
information located in Tier 1 Tables
2.3.2–1 and 2.3.2–2, and Tier 1 Figures
2.2.1–1 and 2.3.2–1. These changes were
necessary as part of a design
modification which provides a springassisted check valve to the Reactor
Coolant System Purification Return Line
in order to maintain overpressure
protection, replaces an isolation check
valve in the CVS with an air operated
globe valve, and separates the zinc and
hydrogen injection lines.
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 NRC is issuing 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 License
Amendment No. 12 to COLs, NPF–91
and NPF–92, issued 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 CVS.
As part of this request, the licensee
needed to change information located in
Tier 1 Tables 2.3.2–1 and 2.3.2–2, and
Tier 1 Figures 2.2.1–1 and 2.3.2–1.
These changes were necessary as part of
a design modification which provides a
spring-assisted check valve to the
Reactor Coolant System Purification
Return Line in order to maintain
overpressure protection, replaces an
isolation check valve in the CVS with an
air operated globe valve, and separates
the zinc and hydrogen injection lines.
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
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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 14137). The
supplements had no effect on the no
significant hazards consideration
determination and 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 January 11, 2013, and supplemented
by letters February 27, 2013 and June
11, 2013. The exemption and
amendment were issued on July 25,
2013 as part of a combined package to
the licensee. (ADAMS Accession No.
ML13172A181).
Dated at Rockville, Maryland, this 12th day
of August, 2013.
For the Nuclear Regulatory Commission.
Lawrence Burkhart,
Chief, Licensing Branch 4, Division of New
Reactor Licensing, Office of New Reactors.
[FR Doc. 2013–20144 Filed 8–16–13; 8:45 am]
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TKELLEY on DSK3SPTVN1PROD with NOTICES
Advisory Committee on Reactor
Safeguards (ACRS) Meeting of the
ACRS Subcommittee on Digital I&C;
Notice of Meeting
The ACRS Subcommittee on Digital
I&C will hold a briefing on September
19, 2013, Room T–2B3, 11545 Rockville
Pike, Rockville, Maryland.
The entire meeting will be open to
public attendance.
The agenda for the subject meeting
shall be as follows:
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Thursday, September 19, 2013–8:30
a.m. until 5:00 p.m.
The Subcommittee will review the
results and status of NRC research
activities involving identification of
digital system failure modes and use of
hazard analysis methods for digital
safety systems. The Subcommittee will
hear presentations by and hold
discussions with the Electric Power
Research Institute (EPRI), the NRC staff,
and other interested persons regarding
this matter. The Subcommittee will
gather information, analyze relevant
issues and facts, and formulate
proposed positions and actions, as
appropriate, for deliberation by the Full
Committee.
Members of the public desiring to
provide oral statements and/or written
comments should notify the Designated
Federal Official (DFO), Christina
Antonescu (Telephone 301–415–6792 or
Email: Christina.Antonescu@nrc.gov)
five days prior to the meeting, if
possible, so that appropriate
arrangements can be made. Thirty-five
hard copies of each presentation or
handout should be provided to the DFO
thirty minutes before the meeting. In
addition, one electronic copy of each
presentation should be emailed to the
DFO one day before the meeting. If an
electronic copy cannot be provided
within this timeframe, presenters
should provide the DFO with a CD
containing each presentation at least
thirty minutes before the meeting.
Electronic recordings will be permitted
only during those portions of the
meeting that are open to the public.
Detailed procedures for the conduct of
and participation in ACRS meetings
were published in the Federal Register
on October 18, 2012, (77 FR 64146–
64147).
Detailed meeting agendas and meeting
transcripts are available on the NRC
Web site at https://www.nrc.gov/readingrm/doc-collections/acrs. Information
regarding topics to be discussed,
changes to the agenda, whether the
meeting has been canceled or
rescheduled, and the time allotted to
present oral statements can be obtained
from the Web site cited above or by
contacting the identified DFO.
Moreover, in view of the possibility that
the schedule for ACRS meetings may be
adjusted by the Chairman as necessary
to facilitate the conduct of the meeting,
persons planning to attend should check
with these references if such
rescheduling would result in a major
inconvenience.
If attending this meeting, please enter
through the One White Flint North
building, 11555 Rockville Pike,
PO 00000
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50457
Rockville, MD. After registering with
security, please contact Mr. Theron
Brown (Telephone 240–888–9835) to be
escorted to the meeting room.
Dated: August 1, 2013.
Cayetano Santos,
Chief, Technical Support Branch, Advisory
Committee on Reactor Safeguards.
[FR Doc. 2013–20142 Filed 8–16–13; 8:45 am]
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Advisory Committee on Reactor
Safeguards (ACRS); Meeting of the
ACRS Subcommittee on Fukushima;
Notice of Meeting
The ACRS Subcommittee on
Fukushima will hold a meeting on
September 4, 2013, Room T–2B1, 11545
Rockville Pike, Rockville, Maryland.
The entire meeting will be open to
public attendance.
The agenda for the subject meeting
shall be as follows:
Wednesday, September 4, 2013–8:30
a.m. until 12:00 p.m.
The Subcommittee will review and
discuss options for addressing the Near
Term Task Force (NTTF)
Recommendation 1: Enhanced
Regulatory Framework. The
Subcommittee will hear presentations
by and hold discussions with the NRC
staff, the Nuclear Energy Institute, and
other interested persons regarding this
matter. The Subcommittee will gather
information, analyze relevant issues and
facts, and formulate proposed positions
and actions, as appropriate, for
deliberation by the Full Committee.
Members of the public desiring to
provide oral statements and/or written
comments should notify the Designated
Federal Official (DFO), Hossein
Nourbakhsh (Telephone 301–415–5622
or Email: Hossein.Nourbakhsh@nrc.gov)
five days prior to the meeting, if
possible, so that appropriate
arrangements can be made. Thirty-five
hard copies of each presentation or
handout should be provided to the DFO
thirty minutes before the meeting. In
addition, one electronic copy of each
presentation should be emailed to the
DFO one day before the meeting. If an
electronic copy cannot be provided
within this timeframe, presenters
should provide the DFO with a CD
containing each presentation at least
thirty minutes before the meeting.
Electronic recordings will be permitted
only during those portions of the
meeting that are open to the public.
Detailed procedures for the conduct of
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]]>Agencies
[Federal Register Volume 78, Number 160 (Monday, August 19, 2013)]
[Notices]
[Pages 50455-50457]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-20144]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 52-025, and 52-026; NRC-2008-0252]
Vogtle Electric Generating Station, Units 3 and 4; Southern
Nuclear Operating Company; Changes to the Chemical Volume Control
System
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption and combined license amendment; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is both 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. 12 to Combined Licenses (COL), NPF-91 and NPF-92. The
COLs were issued to Southern Nuclear Operating Company, Inc., and
Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric
Authority of Georgia, and the City of Dalton, Georgia (the licensee),
for construction and operation of the Vogtle Electric Generating Plant
(VEGP), Units 3 and 4, located in Burke County, Georgia. The amendment
requests changes that modify the Chemical and Volume Control System
(CVS), including changes to information located in Tier 1 Tables 2.3.2-
1 and 2.3.2-2, and Tier 1 Figures 2.2.1-1 and 2.3.2-1. The granting of
the exemption allows the changes to Tier 1 information as specified in
the license amendment request. 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-2008-0252 when contacting the
NRC about the availability of information regarding this document. You
may access information related to this document, which the NRC
possesses and is publicly available, 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: 301-287-
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 available documents online in the NRC
Library at https://www.nrc.gov/reading-rm/adams.html. To begin the
search,
[[Page 50456]]
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 January 11, 2013 (ADAMS Accession No. ML13016A091). The
licensee supplemented this request on February 27, 2013 (ADAMS
Accession No. ML13059A499) and June 11, 2013 (ADAMS Accession No.
ML13163A356).
NRCs 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: Anthony Minarik, Office of New
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-6185; email: Anthony.Minarik@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing 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 License Amendment No. 12 to COLs, NPF-91 and NPF-92,
issued 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 CVS. As part of this request, the licensee needed to change
information located in Tier 1 Tables 2.3.2-1 and 2.3.2-2, and Tier 1
Figures 2.2.1-1 and 2.3.2-1. These changes were necessary as part of a
design modification which provides a spring-assisted check valve to the
Reactor Coolant System Purification Return Line in order to maintain
overpressure protection, replaces an isolation check valve in the CVS
with an air operated globe valve, and separates the zinc and hydrogen
injection lines.
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. ML13172A326.
Identical exemption documents (except for referenced unit numbers
and license numbers) were issued to the licensee for Vogtle Units 3 and
4 (COLs NPF-91 and NPF-92). These documents can be found in ADAMS under
Accession Nos. ML13172A218 and ML13172A223. 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. ML13172A242 and
ML13172A299. A summary of the amendment documents is provided in
Section III of this document.
II. Exemption
Reproduced below is the exemption document issued to Vogtle Unit 3
and Unit 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 January 11, 2013, and as supplemented by
letters dated February 27, 2013 and June 11, 2013, the licensee
requested from the Commission an exemption from the provisions of 10
CFR part 52, appendix D, Section III.B, as part of license amendment
request 13-002, ``Changes to the Chemical and Volume Control System
(CVS) (LAR-13-002).
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. ML13172A326, 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 Tables 2.3.2-1 and 2.3.2-2,
and Figures 2.2.1-1 and 2.3.2-1, as described in the licensee's request
dated January 11, 2013, and as supplemented on February 27, 2013 and
June 11, 2013. This exemption is related to, and necessary for the
granting of License Amendment No. 12, which is being issued
concurrently with this exemption.
3. As explained in Section 5.0, ``Environmental Consideration,'' of
the NRC staff's Safety Evaluation (ADAMS Accession No. ML13172A326),
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 July 25, 2013.
III. License Amendment Request
By letter dated January 11, 2013, the licensee requested that the
NRC amend the COLs for VEGP, Units 3 and 4, COLs NPF-91 and NPF-92. The
licensee supplemented this application on February 27, 2013, and June
11, 2013. The proposed amendment would depart from the UFSAR Tier 1
material, and would revise the associated material that has been
included in Appendix C of each of the VEGP, Units 3 and 4, COLs. The
requested amendment will revise the Tier 2 UFSAR information pertaining
to the CVS, found throughout the UFSAR. These Tier 2 changes require
modifications to particular information located in Tier 1 Tables 2.3.2-
1 and 2.3.2-2, and Tier 1 Figures 2.2.1-1 and 2.3.2-1. These changes
were necessary as part of a design modification which provides a
spring-assisted check valve to the Reactor Coolant System Purification
Return Line in order to maintain overpressure protection, replaces an
isolation check valve in the CVS with an air operated globe valve, and
separates the zinc and hydrogen injection lines.
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.
[[Page 50457]]
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 14137). The supplements had no effect
on the no significant hazards consideration determination and 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 January 11, 2013, and supplemented by letters February 27,
2013 and June 11, 2013. The exemption and amendment were issued on July
25, 2013 as part of a combined package to the licensee. (ADAMS
Accession No. ML13172A181).
Dated at Rockville, Maryland, this 12th day of August, 2013.
For the Nuclear Regulatory Commission.
Lawrence Burkhart,
Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of
New Reactors.
[FR Doc. 2013-20144 Filed 8-16-13; 8:45 am]
BILLING CODE 7590-01-P
