Duke Energy Carolinas, LLC; Environmental Assessment and Finding of No Significant Impact, Oconee Nuclear Station, Units 1, 2, and 3, 21594-21595 [2012-8547]
Download as PDF
<![CDATA[
21594
Federal Register / Vol. 77, No. 69 / Tuesday, April 10, 2012 / Notices
are also available at https://www.nrc.gov/
reactors/new-reactors/col.html.
These documents may also be viewed
electronically on the public computers
located at the NRC’s PDR, O 1 F21, One
White Flint North, 11555 Rockville
Pike, Rockville, MD 20852. The PDR
reproduction contractor will copy
documents for a fee.
Dated at Rockville, Maryland, this 2nd day
of April, 2012.
For The Nuclear Regulatory Commission.
Mark Tonacci,
Chief, Licensing Branch 4, Division of New
Reactor Licensing, Office of New Reactors.
[FR Doc. 2012–8548 Filed 4–9–12; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–269, 50–270, and 50–28;
NRC–2012–0088]
Duke Energy Carolinas, LLC;
Environmental Assessment and
Finding of No Significant Impact,
Oconee Nuclear Station, Units 1, 2, and
3
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of an exemption to Renewed
Facility Operating Licenses DPR–38,
DPR–47, and DPR–55, issued to Duke
Energy Carolinas, LLC (the licensee), for
operation of the Oconee Nuclear
Station, Units 1, 2, and 3, located in
Oconee County in South Carolina, in
accordance with Title 10 of the Code of
Federal Regulations (10 CFR) 50.12.
Therefore, as required by 10 CFR 51.21,
the NRC performed an environmental
assessment. Based on the results of the
environmental assessment, the NRC is
issuing a finding of no significant
impact.
srobinson on DSK4SPTVN1PROD with NOTICES
Environmental Assessment
Identification of the Proposed Action
Part 50, Appendix G requires that
fracture toughness requirements for
ferritic materials of pressure-retaining
components of the reactor coolant
pressure boundary of light-water
nuclear power reactors provide
adequate margins of safety during any
condition of normal operation,
including anticipated operational
occurrences and system hydrostatic
tests, to which the pressure boundary
may be subjected over its service
lifetime, 10 CFR 50.61 provides fracture
toughness requirements for protection
against pressurized thermal shock (PTS)
events.
The proposed action would grant an
exemption from certain requirements of
VerDate Mar<15>2010
16:26 Apr 09, 2012
Jkt 226001
10 CFR 50.61, ‘‘Fracture Toughness
Requirements for Protection Against
Pressurized Thermal Shock Events,’’
and 10 CFR part 50 Appendix G,
‘‘Fracture Toughness Requirements.’’
The exemption would allow use of
alternate initial reference nil ductility
temperature (RTNDT) as described in the
NRC approved topical reports, BAW–
2308, Revisions 1–A and 2–A, for
determining the adjusted RTNDT of
Linde 80 weld materials present in the
beltline region of the Oconee Nuclear
Station, (ONS) Units 1, 2, and 3 reactor
pressure vessels.
The proposed action is in accordance
with the licensee’s application dated
August 3, 2011 (Agencywide Documents
Access and Management System
(ADAMS) Accession No.
ML11223A010).
The Need for the Proposed Action
The proposed action is needed to
allow the licensee to use alternate initial
RTNDT (reference nil ductility
temperature), as described in the NRCapproved topical reports (TRs), BAW–
2308, ‘‘Initial RTNDT of Linde 80 Weld
Materials,’’ Revisions 1–A and 2–A, for
determining the adjusted RTNDT of
Linde 80 weld materials present in the
beltline region of the ONS, Units 1, 2,
and 3 reactor vessels (RVs).
Environmental Impacts of the Proposed
Action
The NRC has completed its
environmental assessment of an
exemption. The staff has concluded that
the proposed action to allow the use of
alternate initial reference nil ductility
temperature (RTNDT) as described in the
NRC approved topical reports BAW–
2308, Revisions 1–A and 2–A for
determining the adjusted RTNDT of
Linde 80 weld materials present in the
beltline region of the ONS, Units 1, 2,
and 3 reactor pressure vessels, would
not significantly affect plant safety and
would not have a significant adverse
effect on the probability of an accident
occurring.
The proposed action would not result
in an increased radiological hazard
beyond those previously analyzed in the
updated final safety analysis report for
ONS, Units 1, 2, and 3. There will be no
change to radioactive effluents that
effect radiation exposures to plant
workers and members of the public. No
changes will be made to plant buildings
or the site property. The proposed
action does not involve a change to
plant building or land areas on the ONS
site. Therefore, no changes or different
types of radiological impacts are
expected as a result of the proposed
exemption.
PO 00000
Frm 00073
Fmt 4703
Sfmt 4703
The proposed action does not result
in changes to land use or water use, or
result in changes to the quality or
quantity of non-radiological effluents.
No changes to the National Pollution
Discharge Elimination System permit
are needed. No effects on the aquatic or
terrestrial habitat in the vicinity of the
plant, or to threatened, endangered, or
protected species under the Endangered
Species Act, or impacts to essential fish
habitat covered by the MagnusonStevens Act are expected. There are no
impacts to the air or ambient air quality.
There are no impacts to historical and
cultural resources. There would be no
noticeable effect on socioeconomic
conditions in the region. Therefore, no
changes to or different types of nonradiological environmental impacts are
expected as a result of the proposed
action. Accordingly, the NRC concludes
that there are no significant
environmental impacts associated with
the proposed action.
The details of the staff’s safety
evaluation will be provided as part of
the letter to the licensee approving
issuance of the license amendment.
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 for the ONS,
Units 1, 2, and 3, dated March 1972, and
Final Supplemental Environmental
Impact Statement (NUREG–1437,
Supplement 2) dated December 1999
(ADAMS Accession No. ML003770518).
Agencies and Persons Consulted
In accordance with its stated policy,
on February 27, 2012, the staff
consulted with the South Carolina State
official, Mr. Mark Yeager of the South
Carolina Department of Health and
Environmental Control, regarding the
environmental impact of the proposed
action. The State official had no
comments.
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
E:\FR\FM\10APN1.SGM
10APN1
Federal Register / Vol. 77, No. 69 / Tuesday, April 10, 2012 / Notices
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 3, 2011. Documents may
be examined, and/or copied for a fee, at
the NRC’s Public Document Room
(PDR), located at One White Flint North,
Room O1–F21, 11555 Rockville Pike
(first floor), Rockville, Maryland 20852.
Publicly available documents created or
received at the NRC are accessible
electronically through the Agencywide
Documents Access and Management
System (ADAMS) in the NRC Library at
https://www.nrc.gov/reading-rm/
adams.html. Persons who do not have
access to ADAMS or who encounter
problems in accessing the documents
located in ADAMS should contact the
NRC’s PDR reference staff by telephone
at 1–800–397–4209 or 301–415–4737, or
send an email to pdr.resource@nrc.gov.
Dated at Rockville, Maryland, this 30th day
of March 2012.
For the Nuclear Regulatory Commission.
John Stang,
Senior Project Manager, Plant Licensing
Branch II–1, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2012–8547 Filed 4–9–12; 8:45 am]
request document access by April 20,
2012.
You may access information
and comment submissions related to
this document, which the NRC
possesses and is publicly available, by
searching on https://www.regulations.gov
under Docket ID NRC–2012–0082.
You may submit comments by the
following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2012–0082. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–492–3668;
email: Carol.Gallagher@nrc.gov.
• Mail comments to: Cindy Bladey,
Chief, Rules, Announcements, and
Directives Branch (RADB), Office of
Administration, Mail Stop: TWB–05–
B01M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
• Fax comments to: RADB at 301–
492–3446.
For additional direction on accessing
information and submitting comments,
see ‘‘Accessing Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
ADDRESSES:
SUPPLEMENTARY INFORMATION:
BILLING CODE 7590–01–P
I. Accessing Information and
Submitting Comments
NUCLEAR REGULATORY
COMMISSION
A. Accessing Information
[NRC–2012–0082]
Applications and Amendments to
Facility Operating Licenses and
Combined Licenses Involving
Proposed No Significant Hazards
Considerations and Containing
Sensitive Unclassified Non-Safeguards
Information and Order Imposing
Procedures for Access to Sensitive
Unclassified Non-Safeguards
Information
Nuclear Regulatory
Commission.
ACTION: License amendment request;
opportunity to comment, request a
hearing and petition for leave to
intervene, order.
AGENCY:
Comments must be filed by May
10, 2012. A request for a hearing or
leave to intervene must be filed by June
11, 2012. Any potential party as defined
in Title 10 of the Code of Federal
Regulations (10 CFR) 2.4 who believes
access to Sensitive Unclassified NonSafeguards Information (SUNSI) is
necessary to respond to this notice must
srobinson on DSK4SPTVN1PROD with NOTICES
DATES:
VerDate Mar<15>2010
16:26 Apr 09, 2012
Jkt 226001
Please refer to Docket ID NRC–2012–
0082 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, by the following
methods:
• Federal Rulemaking Web Site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2012–0082.
• 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,
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.
• 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.
PO 00000
Frm 00074
Fmt 4703
Sfmt 4703
21595
B. Submitting Comments
Please include Docket ID NRC–2012–
0082 in the subject line of your
comment submission, in order to ensure
that the NRC is able to make your
comment submission available to the
public in this docket.
The NRC cautions you not to include
identifying or contact information in
comment submissions that you do not
want to be publicly disclosed. The NRC
posts all comment submissions at http:
//www.regulations.gov as well as
entering the comment submissions into
ADAMS, and the NRC does not edit
comment submissions to remove
identifying or contact information.
If you are requesting or aggregating
comments from other persons for
submission to the NRC, then you should
inform those persons not to include
identifying or contact information in
their comment submissions that they do
not want to be publicly disclosed. Your
request should state that the NRC will
not edit comment submissions to
remove such information before making
the comment submissions available to
the public or entering the comment
submissions into ADAMS.
II. Background
Pursuant to Section 189a.(2) of the
Atomic Energy Act of 1954, as amended
(the Act), the U.S. Nuclear Regulatory
Commission (the Commission or NRC
staff) is publishing this notice. The Act
requires the Commission to publish
notice of any amendments issued, or
proposed to be issued and grants the
Commission the authority to issue and
make immediately effective any
amendment to an operating license or
combined license, as applicable, upon a
determination by the Commission that
such amendment involves no significant
hazards consideration, notwithstanding
the pendency before the Commission of
a request for a hearing from any person.
This notice includes notices of
amendments containing SUNSI.
Notice of Consideration of Issuance of
Amendments to Facility Operating
Licenses and Combined Licenses,
Proposed No Significant Hazards
Consideration Determination, and
Opportunity for a Hearing
The Commission has made a
proposed determination that the
following amendment requests involve
no significant hazards consideration.
Under the Commission’s regulations in
10 CFR 50.92, this means that operation
of the facility in accordance with the
proposed amendment would not (1)
involve a significant increase in the
probability or consequences of an
E:\FR\FM\10APN1.SGM
10APN1
]]>Agencies
[Federal Register Volume 77, Number 69 (Tuesday, April 10, 2012)]
[Notices]
[Pages 21594-21595]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-8547]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-269, 50-270, and 50-28; NRC-2012-0088]
Duke Energy Carolinas, LLC; Environmental Assessment and Finding
of No Significant Impact, Oconee Nuclear Station, Units 1, 2, and 3
The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an exemption to Renewed Facility Operating Licenses DPR-38,
DPR-47, and DPR-55, issued to Duke Energy Carolinas, LLC (the
licensee), for operation of the Oconee Nuclear Station, Units 1, 2, and
3, located in Oconee County in South Carolina, in accordance with Title
10 of the Code of Federal Regulations (10 CFR) 50.12. Therefore, as
required by 10 CFR 51.21, the NRC performed an environmental
assessment. Based on the results of the environmental assessment, the
NRC is issuing a finding of no significant impact.
Environmental Assessment
Identification of the Proposed Action
Part 50, Appendix G requires that fracture toughness requirements
for ferritic materials of pressure-retaining components of the reactor
coolant pressure boundary of light-water nuclear power reactors provide
adequate margins of safety during any condition of normal operation,
including anticipated operational occurrences and system hydrostatic
tests, to which the pressure boundary may be subjected over its service
lifetime, 10 CFR 50.61 provides fracture toughness requirements for
protection against pressurized thermal shock (PTS) events.
The proposed action would grant an exemption from certain
requirements of 10 CFR 50.61, ``Fracture Toughness Requirements for
Protection Against Pressurized Thermal Shock Events,'' and 10 CFR part
50 Appendix G, ``Fracture Toughness Requirements.'' The exemption would
allow use of alternate initial reference nil ductility temperature
(RTNDT) as described in the NRC approved topical reports,
BAW-2308, Revisions 1-A and 2-A, for determining the adjusted
RTNDT of Linde 80 weld materials present in the beltline
region of the Oconee Nuclear Station, (ONS) Units 1, 2, and 3 reactor
pressure vessels.
The proposed action is in accordance with the licensee's
application dated August 3, 2011 (Agencywide Documents Access and
Management System (ADAMS) Accession No. ML11223A010).
The Need for the Proposed Action
The proposed action is needed to allow the licensee to use
alternate initial RTNDT (reference nil ductility
temperature), as described in the NRC-approved topical reports (TRs),
BAW-2308, ``Initial RTNDT of Linde 80 Weld Materials,''
Revisions 1-A and 2-A, for determining the adjusted RTNDT of
Linde 80 weld materials present in the beltline region of the ONS,
Units 1, 2, and 3 reactor vessels (RVs).
Environmental Impacts of the Proposed Action
The NRC has completed its environmental assessment of an exemption.
The staff has concluded that the proposed action to allow the use of
alternate initial reference nil ductility temperature
(RTNDT) as described in the NRC approved topical reports
BAW-2308, Revisions 1-A and 2-A for determining the adjusted
RTNDT of Linde 80 weld materials present in the beltline
region of the ONS, Units 1, 2, and 3 reactor pressure vessels, would
not significantly affect plant safety and would not have a significant
adverse effect on the probability of an accident occurring.
The proposed action would not result in an increased radiological
hazard beyond those previously analyzed in the updated final safety
analysis report for ONS, Units 1, 2, and 3. There will be no change to
radioactive effluents that effect radiation exposures to plant workers
and members of the public. No changes will be made to plant buildings
or the site property. The proposed action does not involve a change to
plant building or land areas on the ONS site. Therefore, no changes or
different types of radiological impacts are expected as a result of the
proposed exemption.
The proposed action does not result in changes to land use or water
use, or result in changes to the quality or quantity of non-
radiological effluents. No changes to the National Pollution Discharge
Elimination System permit are needed. No effects on the aquatic or
terrestrial habitat in the vicinity of the plant, or to threatened,
endangered, or protected species under the Endangered Species Act, or
impacts to essential fish habitat covered by the Magnuson-Stevens Act
are expected. There are no impacts to the air or ambient air quality.
There are no impacts to historical and cultural resources. There would
be no noticeable effect on socioeconomic conditions in the region.
Therefore, no changes to or different types of non-radiological
environmental impacts are expected as a result of the proposed action.
Accordingly, the NRC concludes that there are no significant
environmental impacts associated with the proposed action.
The details of the staff's safety evaluation will be provided as
part of the letter to the licensee approving issuance of the license
amendment.
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 for
the ONS, Units 1, 2, and 3, dated March 1972, and Final Supplemental
Environmental Impact Statement (NUREG-1437, Supplement 2) dated
December 1999 (ADAMS Accession No. ML003770518).
Agencies and Persons Consulted
In accordance with its stated policy, on February 27, 2012, the
staff consulted with the South Carolina State official, Mr. Mark Yeager
of the South Carolina Department of Health and Environmental Control,
regarding the environmental impact of the proposed action. The State
official had no comments.
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
[[Page 21595]]
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 3, 2011. Documents may be examined, and/
or copied for a fee, at the NRC's Public Document Room (PDR), located
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852. Publicly available documents created
or received at the NRC are accessible electronically through the
Agencywide Documents Access and Management System (ADAMS) in the NRC
Library at https://www.nrc.gov/reading-rm/adams.html. Persons who do not
have access to ADAMS or who encounter problems in accessing the
documents located in ADAMS should contact the NRC's PDR reference staff
by telephone at 1-800-397-4209 or 301-415-4737, or send an email to
pdr.resource@nrc.gov.
Dated at Rockville, Maryland, this 30th day of March 2012.
For the Nuclear Regulatory Commission.
John Stang,
Senior Project Manager, Plant Licensing Branch II-1, Division of
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2012-8547 Filed 4-9-12; 8:45 am]
BILLING CODE 7590-01-P
