Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 57180-57186 [2013-22469]
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0334–2013–0003, 1 item, 1 temporary
item). Records relating to merchandise
refunds.
4. Department of Defense, Defense
Security Service (DAA–0446–2013–
0001, 13 items, 13 temporary items).
Records relating to security training
including instructor syllabuses, student
summaries, and course reference
materials.
5. Department of Health and Human
Services, Centers for Medicare &
Medicaid Services (DAA–0440–2013–
0010, 1 item, 1 temporary item). Master
files of an electronic information system
used to assess customer service of staterun health insurance assistance
programs.
6. Department of Homeland Security,
U.S. Coast Guard (DAA–0026–2013–
0009, 4 items, 4 temporary items).
Records of printing services.
7. Department of Labor, Bureau of
Labor Statistics (DAA–0257–2013–0002,
1 item, 1 temporary item). Employee
non-disclosure agreements.
8. Department of the Navy, U.S.
Marine Corps (DAA–0127–2013–0008, 1
item, 1 temporary item). Master files of
an electronic information system used
to manage procurement, tracking, and
distribution of publications.
9. Department of the Navy, U.S.
Marine Corps (DAA–0127–2013–0010, 1
item, 1 temporary item). Master files of
an electronic information system used
to collect data for security and
background investigations.
10. Department of State, Foreign
Service Grievance Board (DAA–0059–
2013–0002, 9 items, 7 temporary items).
Included are records of proceedings,
decisions, member files, and
administrative records. Proposed for
permanent retention are annual reports
and formal minutes.
11. Department of Transportation,
Federal Highway Administration (DAA–
0406–2013–0003, 1 item, 1 temporary
item). Master files of an electronic
information system used to track the
costs of highway construction.
12. Office of the Director of National
Intelligence, Office of the Deputy
Director of National Intelligence for
Intelligence Integration (N1–576–11–
12), 13 items, 6 temporary items.
Records of the President’s Daily Brief
including electronic backups, reference
materials, copies of service level
agreements, and non-substantive drafts
and working papers. Proposed for
permanent retention are case files
associated with the production and
delivery of the brief, policy records,
calendars, and substantive working
papers.
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Dated: September 10, 2013.
Paul M. Wester, Jr.,
Chief Records Officer for the U.S.
Government.
Activity for Which Permit Is Requested
[FR Doc. 2013–22544 Filed 9–16–13; 8:45 am]
BILLING CODE 7515–01–P
NATIONAL SCIENCE FOUNDATION
Notice of Permit Applications Received
Under the Antarctic Conservation Act
of 1978 (Pub. L. 95–541)
National Science Foundation.
ACTION: Notice of Permit Applications
Received under the Antarctic
Conservation Act of 1978, Public Law
95–541.
AGENCY:
The National Science
Foundation (NSF) is required to publish
a notice of permit applications received
to conduct activities regulated under the
Antarctic Conservation Act of 1978.
NSF has published regulations under
the Antarctic Conservation Act at Title
45 Part 670 of the Code of Federal
Regulations. This is the required notice
of permit applications received.
DATES: Interested parties are invited to
submit written data, comments, or
views with respect to this permit
application by October 17, 2013. This
application may be inspected by
interested parties at the Permit Office,
address below.
ADDRESSES: Comments should be
addressed to Permit Office, Room 755,
Division of Polar Programs, National
Science Foundation, 4201 Wilson
Boulevard, Arlington, Virginia 22230.
FOR FURTHER INFORMATION CONTACT:
Adrian Dahood, ACA Permit Officer, at
the above address or ACApermits@
nsf.gov or (703) 292–7149.
SUPPLEMENTARY INFORMATION: The
National Science Foundation, as
directed by the Antarctic Conservation
Act of 1978 (Pub. L. 95–541), as
amended by the Antarctic Science,
Tourism and Conservation Act of 1996,
has developed regulations for the
establishment of a permit system for
various activities in Antarctica and
designation of certain animals and
certain geographic areas as requiring
special protection. The regulations
establish such a permit system to
designate Antarctic Specially Protected
Areas.
SUMMARY:
Application Details
1. Applicant: Ted Cheeseman, Permit
Application: 2014–018,
Cheeseman’s Ecology Safaris, Santa
Cruz, CA
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Take (Salvage); The applicant requests
a permit to collect feathers and small
tissue samples from up to 20 Emperor
penguin carcasses on Snow Hill Island.
The applicant is working in
collaboration with a UK scientist who
will receive and analyze the samples to
better understand emperor penguin
population structure, migration and
demographic processes. Only carcasses
that are a sufficient distance away from
the colony would be selected for
sampling. This would ensure that no
live animals are disturbed during
sampling.
Location
Snow Hill Island Emperor Penguin
Colony.
Dates
October 14, 2013 to October 31, 2013.
Nadene G. Kennedy,
Polar Coordination Specialist, Division of
Polar Programs.
[FR Doc. 2013–22568 Filed 9–16–13; 8:45 am]
BILLING CODE 7555–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2013–0209]
Biweekly Notice; Applications and
Amendments to Facility Operating
Licenses and Combined Licenses
Involving No Significant Hazards
Considerations
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)
is publishing this regular biweekly
notice. The Act requires the
Commission 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 biweekly notice includes all
notices of amendments issued, or
proposed to be issued from August 22,
2013, to September 4, 2013. The last
biweekly notice was published on
September 3, 2013 (78 FR 54280).
ADDRESSES: You may submit comments
by any of the following methods (unless
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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–2013–0209. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov.
• Mail comments to: Cindy Bladey,
Chief, Rules, Announcements, and
Directives Branch (RADB), Office of
Administration, Mail Stop: 3WFN–06–
A44MP, 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.
SUPPLEMENTARY INFORMATION:
I. Accessing Information and
Submitting Comments
tkelley on DSK3SPTVN1PROD with NOTICES
A. Accessing Information
Please refer to Docket ID NRC–2013–
0209 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–2013–0209.
• 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.
Documents may be viewed in ADAMS
by performing a search on the document
date and docket number.
• 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.
B. Submitting Comments
Please include Docket ID NRC–2013–
0209 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
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comment submissions that you do not
want to be publicly disclosed. The NRC
posts all comment submissions at https://
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.
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
§ 50.92 of Title 10 of the Code of Federal
Regulations (10 CFR), 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
accident previously evaluated; or (2)
create the possibility of a new or
different kind of accident from any
accident previously evaluated; or (3)
involve a significant reduction in a
margin of safety. The basis for this
proposed determination for each
amendment request is shown below.
The Commission is seeking public
comments on this proposed
determination. Any comments received
within 30 days after the date of
publication of this notice will be
considered in making any final
determination.
Normally, the Commission will not
issue the amendment until the
expiration of 60 days after the date of
publication of this notice. The
Commission may issue the license
amendment before expiration of the 60day period provided that its final
determination is that the amendment
involves no significant hazards
consideration. In addition, the
Commission may issue the amendment
prior to the expiration of the 30-day
comment period should circumstances
change during the 30-day comment
period such that failure to act in a
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timely way would result, for example in
derating or shutdown of the facility.
Should the Commission take action
prior to the expiration of either the
comment period or the notice period, it
will publish in the Federal Register a
notice of issuance. Should the
Commission make a final No Significant
Hazards Consideration Determination,
any hearing will take place after
issuance. The Commission expects that
the need to take this action will occur
very infrequently.
Within 60 days after the date of
publication of this notice, any person(s)
whose interest may be affected by this
action may file a request for a hearing
and a petition to intervene with respect
to issuance of the amendment to the
subject facility operating license or
combined license. Requests for a
hearing and a petition for leave to
intervene shall be filed in accordance
with the Commission’s ’’Rules of
Practice for Domestic Licensing
Proceedings’’ in 10 CFR Part 2.
Interested person(s) should consult a
current copy of 10 CFR 2.309, which is
available at the NRC’s PDR, located at
One White Flint North, Room O1–F21,
11555 Rockville Pike (first floor),
Rockville, Maryland 20852. NRC
regulations are accessible electronically
from the NRC Library on the NRC Web
site at https://www.nrc.gov/reading-rm/
doc-collections/cfr/ If a request for a
hearing or petition for leave to intervene
is filed by the above date, the
Commission or a presiding officer
designated by the Commission or by the
Chief Administrative Judge of the
Atomic Safety and Licensing Board
Panel, will rule on the request and/or
petition; and the Secretary or the Chief
Administrative Judge of the Atomic
Safety and Licensing Board will issue a
notice of a hearing or an appropriate
order.
As required by 10 CFR 2.309, a
petition for leave to intervene shall set
forth with particularity the interest of
the petitioner in the proceeding, and
how that interest may be affected by the
results of the proceeding. The petition
should specifically explain the reasons
why intervention should be permitted
with particular reference to the
following general requirements: 1) the
name, address, and telephone number of
the requestor or petitioner; 2) the nature
of the requestor’s/petitioner’s right
under the Act to be made a party to the
proceeding; 3) the nature and extent of
the requestor’s/petitioner’s property,
financial, or other interest in the
proceeding; and 4) the possible effect of
any decision or order which may be
entered in the proceeding on the
requestor’s/petitioner’s interest. The
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petition must also identify the specific
contentions which the requestor/
petitioner seeks to have litigated at the
proceeding.
Each contention must consist of a
specific statement of the issue of law or
fact to be raised or controverted. In
addition, the requestor/petitioner shall
provide a brief explanation of the bases
for the contention and a concise
statement of the alleged facts or expert
opinion which support the contention
and on which the requestor/petitioner
intends to rely in proving the contention
at the hearing. The requestor/petitioner
must also provide references to those
specific sources and documents of
which the petitioner is aware and on
which the requestor/petitioner intends
to rely to establish those facts or expert
opinion. The petition must include
sufficient information to show that a
genuine dispute exists with the
applicant on a material issue of law or
fact. Contentions shall be limited to
matters within the scope of the
amendment under consideration. The
contention must be one which, if
proven, would entitle the requestor/
petitioner to relief. A requestor/
petitioner who fails to satisfy these
requirements with respect to at least one
contention will not be permitted to
participate as a party.
Those permitted to intervene become
parties to the proceeding, subject to any
limitations in the order granting leave to
intervene, and have the opportunity to
participate fully in the conduct of the
hearing.
If a hearing is requested, the
Commission will make a final
determination on the issue of no
significant hazards consideration. The
final determination will serve to decide
when the hearing is held. If the final
determination is that the amendment
request involves no significant hazards
consideration, the Commission may
issue the amendment and make it
immediately effective, notwithstanding
the request for a hearing. Any hearing
held would take place after issuance of
the amendment. If the final
determination is that the amendment
request involves a significant hazards
consideration, then any hearing held
would take place before the issuance of
any amendment.
All documents filed in NRC
adjudicatory proceedings, including a
request for hearing, a petition for leave
to intervene, any motion or other
document filed in the proceeding prior
to the submission of a request for
hearing or petition to intervene, and
documents filed by interested
governmental entities participating
under 10 CFR 2.315(c), must be filed in
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accordance with the NRC E-Filing rule
(72 FR 49139, August 28, 2007). The EFiling process requires participants to
submit and serve all adjudicatory
documents over the internet, or in some
cases to mail copies on electronic
storage media. Participants may not
submit paper copies of their filings
unless they seek an exemption in
accordance with the procedures
described below.
To comply with the procedural
requirements of E-Filing, at least 10
days prior to the filing deadline, the
participant should contact the Office of
the Secretary by email at
hearing.docket@nrc.gov, or by telephone
at 301–415–1677, to request (1) a digital
information (ID) certificate, which
allows the participant (or its counsel or
representative) to digitally sign
documents and access the E-Submittal
server for any proceeding in which it is
participating; and (2) advise the
Secretary that the participant will be
submitting a request or petition for
hearing (even in instances in which the
participant, or its counsel or
representative, already holds an NRCissued digital ID certificate). Based upon
this information, the Secretary will
establish an electronic docket for the
hearing in this proceeding if the
Secretary has not already established an
electronic docket.
Information about applying for a
digital ID certificate is available on the
NRC’s public Web site at https://
www.nrc.gov/site-help/e-submittals/
apply-certificates.html. System
requirements for accessing the ESubmittal server are detailed in the
NRC’s ‘‘Guidance for Electronic
Submission,’’ which is available on the
agency’s public Web site at https://
www.nrc.gov/site-help/esubmittals.html. Participants may
attempt to use other software not listed
on the Web site, but should note that the
NRC’s E-Filing system does not support
unlisted software, and the NRC Meta
System Help Desk will not be able to
offer assistance in using unlisted
software.
If a participant is electronically
submitting a document to the NRC in
accordance with the E-Filing rule, the
participant must file the document
using the NRC’s online, Web-based
submission form. In order to serve
documents through Electronic
Information Exchange System, users
will be required to install a Web
browser plug-in from the NRC Web site.
Further information on the Web-based
submission form, including the
installation of the Web browser plug-in,
is available on the NRC’s public Web
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site at https://www.nrc.gov/site-help/esubmittals.html.
Once a participant has obtained a
digital ID certificate and a docket has
been created, the participant can then
submit a request for hearing or petition
for leave to intervene. Submissions
should be in Portable Document Format
(PDF) in accordance with NRC guidance
available on the NRC public Web site at
https://www.nrc.gov/site-help/esubmittals.html. A filing is considered
complete at the time the documents are
submitted through the NRC’s E-Filing
system. To be timely, an electronic
filing must be submitted to the E-Filing
system no later than 11:59 p.m. Eastern
Time on the due date. Upon receipt of
a transmission, the E-Filing system
time-stamps the document and sends
the submitter an email notice
confirming receipt of the document. The
E-Filing system also distributes an email
notice that provides access to the
document to the NRC Office of the
General Counsel and any others who
have advised the Office of the Secretary
that they wish to participate in the
proceeding, so that the filer need not
serve the documents on those
participants separately. Therefore,
applicants and other participants (or
their counsel or representative) must
apply for and receive a digital ID
certificate before a hearing request/
petition to intervene is filed so that they
can obtain access to the document via
the E-Filing system.
A person filing electronically using
the agency’s adjudicatory E-Filing
system may seek assistance by
contacting the NRC Meta System Help
Desk through the ‘‘Contact Us’’ link
located on the NRC Web site at https://
www.nrc.gov/site-help/esubmittals.html, by email at
MSHD.Resource@nrc.gov, or by a tollfree call at 1–866–672–7640. The NRC
Meta System Help Desk is available
between 8 a.m. and 8 p.m., Eastern
Time, Monday through Friday,
excluding government holidays.
Participants who believe that they
have a good cause for not submitting
documents electronically must file an
exemption request, in accordance with
10 CFR 2.302(g), with their initial paper
filing requesting authorization to
continue to submit documents in paper
format. Such filings must be submitted
by: (1) first class mail addressed to the
Office of the Secretary of the
Commission, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, Attention: Rulemaking and
Adjudications Staff; or (2) courier,
express mail, or expedited delivery
service to the Office of the Secretary,
Sixteenth Floor, One White Flint North,
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11555 Rockville Pike, Rockville,
Maryland 20852, Attention: Rulemaking
and Adjudications Staff. Participants
filing a document in this manner are
responsible for serving the document on
all other participants. Filing is
considered complete by first-class mail
as of the time of deposit in the mail, or
by courier, express mail, or expedited
delivery service upon depositing the
document with the provider of the
service. A presiding officer, having
granted an exemption request from
using E-Filing, may require a participant
or party to use E-Filing if the presiding
officer subsequently determines that the
reason for granting the exemption from
use of E-Filing no longer exists.
Documents submitted in adjudicatory
proceedings will appear in the NRC’s
electronic hearing docket which is
available to the public at https://
ehd1.nrc.gov/ehd/, unless excluded
pursuant to an order of the Commission,
or the presiding officer. Participants are
requested not to include personal
privacy information, such as social
security numbers, home addresses, or
home phone numbers in their filings,
unless an NRC regulation or other law
requires submission of such
information. However, a request to
intervene will require including
information on local residence in order
to demonstrate a proximity assertion of
interest in the proceeding. With respect
to copyrighted works, except for limited
excerpts that serve the purpose of the
adjudicatory filings and would
constitute a Fair Use application,
participants are requested not to include
copyrighted materials in their
submission.
Petitions for leave to intervene must
be filed no later than 60 days from the
date of publication of this notice.
Requests for hearing, petitions for leave
to intervene, and motions for leave to
file new or amended contentions that
are filed after the 60-day deadline will
not be entertained absent a
determination by the presiding officer
that the filing demonstrates good cause
by satisfying the following three factors
in 10 CFR 2.309(c)(1): (i) the
information upon which the filing is
based was not previously available; (ii)
the information upon which the filing is
based is materially different from
information previously available; and
(iii) the filing has been submitted in a
timely fashion based on the availability
of the subsequent information.
For further details with respect to this
license amendment application, see the
application for amendment which is
available for public inspection at the
NRC’s PDR, located at One White Flint
North, Room O1–F21, 11555 Rockville
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Pike (first floor), Rockville, Maryland
20852. Publicly available documents
created or received at the NRC are
accessible electronically through
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 PDR
Reference staff at 1–800–397–4209, 301–
415–4737, or by email to pdr.resource@
nrc.gov.
South Carolina Electric and Gas, Docket
Nos. 52–027 and 52–028, Virgil C.
Summer Nuclear Station (VCSNS) Units
2 and 3, Fairfield County, South
Carolina
Date of amendment request: August
30, 2013.
Description of amendment request:
The proposed change would amend
Combined License Nos. NPF–93 and
NPF–94 for the Virgil C. Summer
Nuclear Station (VCSNS) Units 2 and 3
by departing from the Combined
License Appendix C information and
the plant-specific Design Control
Document (DCD) Tier 2 material by
revising the safety function and
classification of Liquid Radwaste
System (WLS) drain hubs in the
Chemical and Volume Control System
and Passive Core Cooling System (PXS)
compartments. In addition, the
proposed changes would modify the
PXS compartment drain piping
connection; WLS valve types, and
depiction of components in the WLS
figures.
Because this proposed change
requires a departure from Tier 1
information in the Westinghouse
Advanced Passive 1000 DCD, the
licensee also requested an exemption
from the requirements of the Generic
DCD Tier 1 in accordance with
52.63(b)(1).
Basis for proposed no significant
hazards consideration determination:
As required by 10 CFR 50.91(a), the
licensee has provided its analysis of the
issue of no significant hazards
consideration, which is presented
below:
1. Does the proposed amendment involve
a significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No
The design function of the WLS is
containment isolation and the prevention of
backflow in the drain lines from the CVS
compartment and the PXS compartment to
the containment sump which prevents cross
flooding of these compartments. The
proposed changes to the WLS drainage
function; the CVS and PXS compartment
drain hubs; and the WLS valve types do not
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affect these design functions or any other
system design function. Revising the drain
hub safety classification, the PXS drains
connection type, and the WLS valve types do
not involve any accident initiating event or
component failure. The changes to how
components (valves, filters) are depicted in
the figure provide consistency with the figure
legend and do not alter any system functions.
The system will utilize the same codes and
standards previously used for the system.
Since there are no impacts on accident
initiating events or component failures, the
probability of an accident previously
evaluated is not affected. The radioactive
material source terms and release paths used
in the safety analyses are unchanged, thus
the radiological releases in the Updated Final
Safety Analysis Report (UFSAR) accident
analyses are not affected.
Therefore, the proposed amendment does
not involve a significant increase in the
probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create
the possibility of a new or different kind of
accident from any accident previously
evaluated?
Response: No
The proposed changes to the WLS system
do not adversely affect the design or quality
of any structure, system or component.
Revising the WLS safety functions and reclassifying the drain hubs as nonsafetyrelated does not create a new fault or
sequence of events that could result in a
radioactive material release nor do the
changes to the WLS piping connections,
valve types and the depiction of components
on the figure have any impact on any
accident previously evaluated.
Therefore, the proposed amendment does
not create the possibility of a new or different
kind of accident.
3. Does the proposed amendment involve
a significant reduction in a margin of safety?
Response: No
The proposed changes to the WLS system
drain hubs, piping connection, valve type,
and Tier 1 figure depiction would not affect
any radioactive material barrier. No safety
analysis or design basis acceptance limit/
criterion is challenged or exceeded by the
proposed change, thus no margin of safety is
reduced.
Therefore, the proposed amendment does
not involve a significant reduction in a
margin of safety.
The NRC staff has reviewed the
licensee’s analysis and, based on this
review, it appears that the three
standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff
proposes to determine that the
amendment request involves no
significant hazards consideration.
Attorney for licensee: Ms. Kathryn M.
Sutton, Morgan, Lewis & Bockius LLC,
1111 Pennsylvania Avenue NW.,
Washington, DC 20004–2514.
NRC Branch Chief: Lawrence
Burkhart.
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Southern Nuclear Operating Company,
Inc., Docket Nos. 50–424 and 50–425,
Vogtle Electric Generating Plant, Units 1
and 2, Burke County, Georgia
tkelley on DSK3SPTVN1PROD with NOTICES
Date of amendment request: August
20, 2013.
Description of amendment request:
The proposed amendments would
revise the Vogtle Electric Generating
(VEGP) Emergency Plan by revising the
Emergency Action Level (EAL)
thresholds for certain Initiating
Conditions. The proposed change will
remove certain Main Steam Line (MSL)
radiation monitors from the reference
initiating conditions to address
limitations of these monitors.
Basis for proposed no significant
hazards consideration determination:
As required by 10 CFR 50.91(a), the
licensee has provided its analysis of the
issue of no significant hazards
consideration, which is presented
below:
1. Does the proposed amendment involve
a significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No
The proposed change to the emergency
plan does not impact the physical function
of plant structures, systems, or components
(SSCs) or the manner in which SSCs perform
their design function. The proposed changes
neither adversely affect accident initiators or
precursors, nor alter design assumptions.
The proposed changes do not alter or
prevent the ability of operable SSCs to
perform their intended function to mitigate
the consequences of an initiating event
within assumed acceptance limits. No
operating procedures or administrative
controls that function to prevent or mitigate
accidents are affected by the proposed
change.
Therefore, the proposed change does not
involve a significant increase in the
probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the
possibility of a new or different kind of
accident from any accident previously
evaluated?
Response: No.
The proposed changes do not impact the
accident analysis. The changes do not
involve a physical alteration of the plant (i.e.,
no new or different type of equipment will
be installed), a change in the method of plant
operation, or new operator actions. The
proposed change will not introduce failure
modes that could result in a new accident,
and the change does not alter assumptions
made in the safety analysis. The proposed
changes revise EALs, which establish the
thresholds for placing the plant in an
emergency classification. EALs are not
initiators of any accidents.
Therefore, the proposed change does not
create the possibility of a new or different
kind of accident from any accident
previously evaluated.
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3. Does the proposed change involve a
significant reduction in a margin of safety?
Response: No.
Margin of safety is associated with
confidence in the ability of the fission
product barriers (i.e., fuel cladding, reactor
coolant system pressure boundary, and
containment structure) to limit the level of
radiation dose to the public. The proposed
changes are associated with the EALs and do
not impact operation of the plant or its
response to transients or accidents. The
changes do not affect the TSs or the operating
license. The proposed changes do not involve
a change in the method of plant operation,
and no accident analyses will be affected by
the proposed changes. Additionally, the
proposed changes will not relax any criteria
used to establish safety limits and will not
relax any safety system settings. The safety
analysis acceptance criteria are not affected
by these changes. The proposed changes will
not result in plant operation in a
configuration outside the design basis. The
proposed change does not adversely affect
systems that respond to safely shutdown the
plant and to maintain the plant in a safe
shutdown condition.
The revised EAL provides more
appropriate and accurate criteria for
determining protective measures that should
be considered within and outside the site
boundary to protect health and safety. The
emergency plan will continue to activate an
emergency response commensurate with the
extent of degradation of plant safety.
Therefore, the proposed change does not
involve a significant reduction in a margin of
safety.
Based on the above, SNC has determined
that operation of the facility in accordance
with the proposed changes does not involve
a significant hazards consideration as defined
in 10 CFR 50.92(c), in that it does not: (1)
involve a significant increase in the
probability or consequences of an accident
previously evaluated; or (2) create the
possibility of a new or different kind of
accident from any accident previously
evaluated.
The NRC staff has reviewed the
licensee’s analysis and, based on this
review, it appears that the three
standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff
proposes to determine that the
amendment request involves no
significant hazards consideration.
Attorney for licensee: Leigh D. Perry,
SVP & General Counsel, Southern
Nuclear Operating Company, 40
Inverness Center Parkway, Birmingham,
AL 35242.
NRC Branch Chief: Robert Pascarelli.
Previously Published Notices 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 following notices were previously
published as separate individual
PO 00000
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notices. The notice content was the
same as above. They were published as
individual notices either because time
did not allow the Commission to wait
for this biweekly notice or because the
action involved exigent circumstances.
They are repeated here because the
biweekly notice lists all amendments
issued or proposed to be issued
involving no significant hazards
consideration.
For details, see the individual notice
in the Federal Register on the day and
page cited. This notice does not extend
the notice period of the original notice.
Tennessee Valley Authority, Docket No.
50–259, Browns Ferry Nuclear Plant,
Unit 1, Limestone County, Alabama
Date of application for amendments:
August 14, 2013.
Description of amendments request:
The proposed amendment would delete
the Notes that cover the Reactor Coolant
System (RCS) Pressure and Temperature
Limits curves on Technical
Specification 3.4.9, ‘‘RCS Pressure and
Temperature (P/T) Limits,’’ Figures
3.4.9–1 and 3.4.9–2 that are applicable
from 12 Effective Full Power Years
(EFPY) to 16 EFPY and allows the usage
of the figures up to 16 EFPY. The
current notes state, ‘‘Do Not Use This
Figure. This curve applies to operations
> 12 EFPY. For current operation, use
previous curve, which is valid up to 12
EFPY.’’
Date of publication of individual
notice in the Federal Register: August
23, 2013 (78 FR 52571).
Expiration date of individual notice:
September 6, 2013 (Public comments)
and October 22, 2013 (Hearing requests).
Notice of Issuance of Amendments to
Facility Operating Licenses and
Combined Licenses
During the period since publication of
the last biweekly notice, the
Commission has issued the following
amendments. The Commission has
determined for each of 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
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Federal Register / Vol. 78, No. 180 / Tuesday, September 17, 2013 / Notices
tkelley on DSK3SPTVN1PROD with NOTICES
published in the Federal Register as
indicated.
Unless otherwise indicated, 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. If the Commission has
prepared an environmental assessment
under the special circumstances
provision in 10 CFR 51.22(b) and has
made a determination based on that
assessment, it is so indicated.
For further details with respect to the
action see (1) the applications for
amendment, (2) the amendment, and (3)
the Commission’s related letter, Safety
Evaluation and/or Environmental
Assessment as indicated. All of these
items are available for public inspection
at the Commission’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. If you do not
have access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the PDR’s
Reference staff at 1–800–397–4209, 301–
415–4737 or by email to pdr.resource@
nrc.gov.
Carolina Power and Light Company, et
al., Docket No. 50–261, H.B. Robinson
Steam Electric Plant, Unit No. 2,
Darlington County, South Carolina
Date of application for amendment:
August 29, 2012, as supplemented by
letters dated March 6, 2013, April 9,
2013, and August 22, 2013.
Brief description of amendment: The
license amendment combined two
changes that affected the same
Technical Specification (TS) sections.
The first part implemented revisions
consistent with TS Task Force—510,
Revision 2, ‘‘Revision to Steam
Generator (SG) Program Inspection
Frequencies and Tube Sample
Selection.’’ The second part revised TS
5.5.9 ‘‘Steam Generator Program’’ to
exclude portions of the SG tube below
the top of the SG tubesheet form
periodic inspections by implementing
the permanent alternate criteria ‘‘H*’’.
Date of issuance: August 29, 2013.
Effective date: This license
amendment is effective as of the date of
its issuance and shall be implemented
within 30 days.
VerDate Mar<15>2010
17:05 Sep 16, 2013
Jkt 229001
Amendment No.: 235.
Renewed Facility Operating License
No. DPR–23: Amendment changed the
license and TSs.
Date of initial notice in Federal
Register: October 16, 2012, 2012 (77 FR
63348). The supplements dated March
6, 2013, April 9, 2013, and August 22,
2013, provided additional information
that clarified the application, did not
expand the scope of the application as
originally noticed, and did not change
the staff’s original proposed no
significant hazards consideration
determination as published in the
Federal Register.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated August 29,
2013.
No significant hazards consideration
comments received: No.
Duke Energy Carolinas, LLC, Docket
Nos. 50–269, 50–270, and 50–287,
Oconee Nuclear Station, Units 1, 2, and
3, Oconee County, South Carolina
Date of application of amendments:
October 30, 2012, as supplemented by
letters dated July 16 and July 26, 2013.
Brief description of amendments: The
amendments revised the Technical
Specifications related to limits on
outage times for the Keowee Hydro
Units, which are the onsite electrical
power supply for the Oconee Nuclear
Station.
Date of Issuance: August 23, 2013.
Effective date: As of the date of
issuance and shall be implemented
within 30 days from the date of
issuance.
Amendment Nos.: 382, 384, and 383.
Renewed Facility Operating License
Nos. DPR–38, DPR–47, and DPR–55:
Amendments revised the licenses and
the technical specifications.
Date of initial notice in Federal
Register: February 19, 2013, 78 FR
11691. The supplements dated July 16
and July 26, 2013, provided additional
information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the staff’s original
proposed no significant hazards
consideration determination.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated August 23,
2013.
No significant hazards consideration
comments received: No.
Florida Power and Light Company, et
al., Docket Nos. 50–335 and 50–389, St.
Lucie Plant Unit Nos. 1 and 2, St. Lucie
County, Florida
Date of application for amendment:
December 27, 2012.
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57185
Brief description of amendment: The
amendments revised the Technical
Specifications (TSs) to align with
Combustion Engineering Owners Group
TS language describing required
licensed Senior Reactor Operator duties
during fuel-handling activities.
Date of issuance: August 30, 2013.
Effective date: As of the date of
issuance and shall be implemented
within 90 days.
Amendment Nos.: 216 and 166.
Facility Operating License Nos. DPR–
77 and DPR–79: Amendments revised
the License and TS.
Date of initial notice in Federal
Register: March 19, 2013 (78 FR
16884).
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated August 30,
2013.
No significant hazards consideration
comments received: No.
Northern States Power Company—
Minnesota (NSPM), Docket No. 50–263,
Monticello Nuclear Generating Plant
(MNGP), Wright County, Minnesota
Date of application for amendment:
August 21, 2012, as supplemented on
November 7, 2012, and March 22, 2013.
Brief description of amendment: The
amendment revises the MNGP Renewed
Facility Operating Licensing and
Technical Specifications to (1) correct
typographical errors; (2) remove
obsolete information; (3) remove
outdated references to a letter that, in
part, specified spent fuel pool storage
capability; (4) make editorial changes;
and (5) correct a pagination error from
a previously-issued license amendment.
Date of issuance: August 28, 2013.
Effective date: As of the date of
issuance and shall be implemented
within 90 days from the date of
issuance.
Amendment No.: 175.
Renewed Facility Operating License
No. DPR–22: Amendment revises the
Renewed Facility Operating License and
Technical Specifications.
Date of initial notice in Federal
Register: December 26, 2012 (77 FR
76081). The supplements dated
November 7, 2012, and March 22, 2013,
provided additional information that
clarified the application, did not expand
the scope of the application as originally
noticed, and did not change the staff’s
original proposed no significant hazards
consideration determination.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated August 28,
2013.
No significant hazards consideration
comments received: No.
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Federal Register / Vol. 78, No. 180 / Tuesday, September 17, 2013 / Notices
Northern States Power Company—
Minnesota, Docket Nos. 50–282 and 50–
306, Prairie Island Nuclear Generating
Plant, Units 1 and 2, Goodhue County,
Minnesota
Date of application for amendments:
August 19, 2011, supplemented by
letters dated May 16, 2012, September 4,
2012, February 8, 2013, and July 17,
2013.
Brief description of amendments: The
amendments revised TS 3.7.17, ‘‘Spent
Fuel Pool Storage,’’ and TS 4.3.1, ‘‘Fuel
Storage Criticality’’ to provide new
spent fuel pool (SFP) loading
restrictions that meet subcriticality for
all postulated conditions. The TS
changes will correct non-conservatisms
in the SFP criticality analysis-of-record.
Date of issuance: August 29, 2013.
Effective date: As of the date of
issuance and shall be implemented
within 120 days.
Amendment Nos.: Unit 1—209; Unit
2—196.
Renewed Facility Operating License
Nos. DPR–42 and DPR–60: Amendments
revised the Facility Operating Licenses
and Technical Specifications.
Date of initial notice in Federal
Register: February 14, 2012 (77 FR
8291). The supplemental letters dated
May 16, 2012, September 4, 2012,
February 8, 2013, and July 17, 2013,
provided additional information that
clarified the application, did not expand
the scope of the application as originally
noticed, and did not change the staff’s
original proposed no significant hazards
consideration determination as
published in the Federal Register.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated August 29,
2013.
No significant hazards consideration
comments received: No.
tkelley on DSK3SPTVN1PROD with NOTICES
Tennessee Valley Authority, Docket
Nos. 50–259, 50–260, and 50–296,
Browns Ferry Nuclear Plant (BFN),
Units 1, 2, and 3, Limestone County,
Alabama
Date of application for amendments:
August 28, 2012, as supplemented by
letter dated August 29, 2013.
Description of amendment request:
The amendments deleted references to
the American Society of Mechanical
Engineers (ASME) Code, Section XI, and
added references to the ASME Code for
Operation and Maintenance of Nuclear
Power Plants to Section 5.5.6, ‘‘Inservice
Testing Program,’’ to the Technical
Specifications. The amendment also
allows a 25-percent extension of
surveillance interval using the
Surveillance Requirement 3.0.2
VerDate Mar<15>2010
17:05 Sep 16, 2013
Jkt 229001
provisions to other normal and
accelerated frequencies specified as two
years or less in the Inservice Test
Program.
Date of issuance: August 30, 2013.
Effective date: Date of issuance, to be
implemented within 60 days.
Amendment Nos.: Unit 1—283, Unit
2—310, and Unit 3—269.
Renewed Facility Operating License
Nos. DPR–33, DPR–52, and DPR–68:
Amendments revised the licenses and
Technical Specifications.
Date of initial notice in Federal
Register: November 27, 2012 (77 FR
70844). The supplement dated August
29, 2013, provided additional
information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the staff’s original
proposed no significant hazards
consideration determination as
published in the Federal Register.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated August 30,
2013.
No significant hazards consideration
comments received: No.
Wolf Creek Nuclear Operating
Corporation, Docket No. 50–482, Wolf
Creek Generating Station, Coffey
County, Kansas
Date of amendment request: October
18, 2012, as supplemented by letter
dated March 20, 2013.
Brief description of amendment: The
amendment revised paragraph 2.C(5)(a)
of the renewed facility operating license
and the fire protection program as
described in the Updated Safety
Analysis Report (USAR) to allow a
deviation from the separation
requirements of 10 CFR Part 50,
Appendix R, Section III.G.2, as
documented in Appendix 9.5E of the
Wolf Creek Generating Station USAR,
for the volume control tank outlet
valves.
Date of issuance: August 23, 2013.
Effective date: As of its date of
issuance and shall be implemented
within 90 days of the date of issuance.
Amendment No.: 205.
Renewed Facility Operating License
No. NPF–42. The amendment revised
the Operating License.
Date of initial notice in Federal
Register: December 11, 2012 (77 FR
73692). The supplemental letter dated
March 20, 2013, provided additional
information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the staff’s original
proposed no significant hazards
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Fmt 4703
Sfmt 4703
consideration determination as
published in the Federal Register.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated August 23,
2013.
No significant hazards consideration
comments received: No.
Dated at Rockville, Maryland, this 6th day
of September 2013.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2013–22469 Filed 9–16–13; 8:45 am]
BILLING CODE 7590–01–P
SECURITIES AND EXCHANGE
COMMISSION
[Release No. 34–70372; File No. SR–
NYSEARCA–2013–88]
Self-Regulatory Organizations; NYSE
Arca, Inc.; Notice of Filing and
Immediate Effectiveness of Proposed
Rule Change To Amend Certain Rules
Pertaining to the Trading of Options in
Order To Change the Expiration Date
for Most Option Contracts to the Third
Friday of the Expiration Month Instead
of the Saturday Following the Third
Friday
September 11, 2013.
Pursuant to Section 19(b)(1) 1 of the
Securities Exchange Act of 1934 (the
‘‘Act’’) 2 and Rule 19b–4 thereunder,3
notice is hereby given that, on
September 5, 2013, NYSE Arca, Inc. (the
‘‘Exchange’’ or ‘‘NYSE Arca’’) filed with
the Securities and Exchange
Commission (the ‘‘Commission’’) the
proposed rule change as described in
Items I and II below, which Items have
been prepared by the self-regulatory
organization. The Commission is
publishing this notice to solicit
comments on the proposed rule change
from interested persons.
I. Self-Regulatory Organization’s
Statement of the Terms of Substance of
the Proposed Rule Change
The Exchange proposes to amend
certain of its rules pertaining to the
trading of options in order to change the
expiration date for most option
contracts to the third Friday of the
expiration month instead of the
Saturday following the third Friday. The
text of the proposed rule change is
available on the Exchange’s Web site at
1 15
U.S.C.78s(b)(1).
U.S.C. 78a.
3 17 CFR 240.19b–4.
2 15
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Agencies
[Federal Register Volume 78, Number 180 (Tuesday, September 17, 2013)]
[Notices]
[Pages 57180-57186]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-22469]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2013-0209]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
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) is publishing this regular biweekly notice. The Act
requires the Commission 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 biweekly notice includes all notices of amendments issued, or
proposed to be issued from August 22, 2013, to September 4, 2013. The
last biweekly notice was published on September 3, 2013 (78 FR 54280).
ADDRESSES: You may submit comments by any of the following methods
(unless
[[Page 57181]]
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-2013-0209. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov.
Mail comments to: Cindy Bladey, Chief, Rules,
Announcements, and Directives Branch (RADB), Office of Administration,
Mail Stop: 3WFN-06-A44MP, 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.
SUPPLEMENTARY INFORMATION:
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2013-0209 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-2013-0209.
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, 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. Documents may be viewed in
ADAMS by performing a search on the document date and docket number.
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.
B. Submitting Comments
Please include Docket ID NRC-2013-0209 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 https://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.
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 Sec. 50.92 of Title 10 of the Code of
Federal Regulations (10 CFR), 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 accident
previously evaluated; or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. The basis
for this proposed determination for each amendment request is shown
below.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period should circumstances change during the 30-day
comment period such that failure to act in a timely way would result,
for example in derating or shutdown of the facility. Should the
Commission take action prior to the expiration of either the comment
period or the notice period, it will publish in the Federal Register a
notice of issuance. Should the Commission make a final No Significant
Hazards Consideration Determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
Within 60 days after the date of publication of this notice, any
person(s) whose interest may be affected by this action may file a
request for a hearing and a petition to intervene with respect to
issuance of the amendment to the subject facility operating license or
combined license. Requests for a hearing and a petition for leave to
intervene shall be filed in accordance with the Commission's ''Rules of
Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2.
Interested person(s) should consult a current copy of 10 CFR 2.309,
which is available at the NRC's PDR, located at One White Flint North,
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland
20852. NRC regulations are accessible electronically from the NRC
Library on the NRC Web site at https://www.nrc.gov/reading-rm/doc-collections/cfr/ If a request for a hearing or petition for leave to
intervene is filed by the above date, the Commission or a presiding
officer designated by the Commission or by the Chief Administrative
Judge of the Atomic Safety and Licensing Board Panel, will rule on the
request and/or petition; and the Secretary or the Chief Administrative
Judge of the Atomic Safety and Licensing Board will issue a notice of a
hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: 1) the name, address, and telephone
number of the requestor or petitioner; 2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; 3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and 4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestor's/petitioner's interest. The
[[Page 57182]]
petition must also identify the specific contentions which the
requestor/petitioner seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
requestor/petitioner shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing.
The requestor/petitioner must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
requestor/petitioner intends to rely to establish those facts or expert
opinion. The petition must include sufficient information to show that
a genuine dispute exists with the applicant on a material issue of law
or fact. Contentions shall be limited to matters within the scope of
the amendment under consideration. The contention must be one which, if
proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing held would take place after issuance
of the amendment. If the final determination is that the amendment
request involves a significant hazards consideration, then any hearing
held would take place before the issuance of any amendment.
All documents filed in NRC adjudicatory proceedings, including a
request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC E-Filing rule (72 FR 49139,
August 28, 2007). The E-Filing process requires participants to submit
and serve all adjudicatory documents over the internet, or in some
cases to mail copies on electronic storage media. Participants may not
submit paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at hearing.docket@nrc.gov, or by
telephone at 301-415-1677, to request (1) a digital information (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a request or
petition for hearing (even in instances in which the participant, or
its counsel or representative, already holds an NRC-issued digital ID
certificate). Based upon this information, the Secretary will establish
an electronic docket for the hearing in this proceeding if the
Secretary has not already established an electronic docket.
Information about applying for a digital ID certificate is
available on the NRC's public Web site at https://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing
the E-Submittal server are detailed in the NRC's ``Guidance for
Electronic Submission,'' which is available on the agency's public Web
site at https://www.nrc.gov/site-help/e-submittals.html. Participants
may attempt to use other software not listed on the Web site, but
should note that the NRC's E-Filing system does not support unlisted
software, and the NRC Meta System Help Desk will not be able to offer
assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, Web-based submission form. In order to
serve documents through Electronic Information Exchange System, users
will be required to install a Web browser plug-in from the NRC Web
site. Further information on the Web-based submission form, including
the installation of the Web browser plug-in, is available on the NRC's
public Web site at https://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with NRC guidance
available on the NRC public Web site at https://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC Office of the General Counsel and any others
who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System
Help Desk through the ``Contact Us'' link located on the NRC Web site
at https://www.nrc.gov/site-help/e-submittals.html, by email at
MSHD.Resource@nrc.gov, or by a toll-free call at 1-866-672-7640. The
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m.,
Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) first class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, Sixteenth
Floor, One White Flint North,
[[Page 57183]]
11555 Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking
and Adjudications Staff. Participants filing a document in this manner
are responsible for serving the document on all other participants.
Filing is considered complete by first-class mail as of the time of
deposit in the mail, or by courier, express mail, or expedited delivery
service upon depositing the document with the provider of the service.
A presiding officer, having granted an exemption request from using E-
Filing, may require a participant or party to use E-Filing if the
presiding officer subsequently determines that the reason for granting
the exemption from use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
https://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the
Commission, or the presiding officer. Participants are requested not to
include personal privacy information, such as social security numbers,
home addresses, or home phone numbers in their filings, unless an NRC
regulation or other law requires submission of such information.
However, a request to intervene will require including information on
local residence in order to demonstrate a proximity assertion of
interest in the proceeding. With respect to copyrighted works, except
for limited excerpts that serve the purpose of the adjudicatory filings
and would constitute a Fair Use application, participants are requested
not to include copyrighted materials in their submission.
Petitions for leave to intervene must be filed no later than 60
days from the date of publication of this notice. Requests for hearing,
petitions for leave to intervene, and motions for leave to file new or
amended contentions that are filed after the 60-day deadline will not
be entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the following three
factors in 10 CFR 2.309(c)(1): (i) the information upon which the
filing is based was not previously available; (ii) the information upon
which the filing is based is materially different from information
previously available; and (iii) the filing has been submitted in a
timely fashion based on the availability of the subsequent information.
For further details with respect to this license amendment
application, see the application for amendment which is available for
public inspection at the NRC's 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 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 PDR Reference staff at 1-800-397-4209,
301-415-4737, or by email to pdr.resource@nrc.gov.
South Carolina Electric and Gas, Docket Nos. 52-027 and 52-028, Virgil
C. Summer Nuclear Station (VCSNS) Units 2 and 3, Fairfield County,
South Carolina
Date of amendment request: August 30, 2013.
Description of amendment request: The proposed change would amend
Combined License Nos. NPF-93 and NPF-94 for the Virgil C. Summer
Nuclear Station (VCSNS) Units 2 and 3 by departing from the Combined
License Appendix C information and the plant-specific Design Control
Document (DCD) Tier 2 material by revising the safety function and
classification of Liquid Radwaste System (WLS) drain hubs in the
Chemical and Volume Control System and Passive Core Cooling System
(PXS) compartments. In addition, the proposed changes would modify the
PXS compartment drain piping connection; WLS valve types, and depiction
of components in the WLS figures.
Because this proposed change requires a departure from Tier 1
information in the Westinghouse Advanced Passive 1000 DCD, the licensee
also requested an exemption from the requirements of the Generic DCD
Tier 1 in accordance with 52.63(b)(1).
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No
The design function of the WLS is containment isolation and the
prevention of backflow in the drain lines from the CVS compartment
and the PXS compartment to the containment sump which prevents cross
flooding of these compartments. The proposed changes to the WLS
drainage function; the CVS and PXS compartment drain hubs; and the
WLS valve types do not affect these design functions or any other
system design function. Revising the drain hub safety
classification, the PXS drains connection type, and the WLS valve
types do not involve any accident initiating event or component
failure. The changes to how components (valves, filters) are
depicted in the figure provide consistency with the figure legend
and do not alter any system functions. The system will utilize the
same codes and standards previously used for the system. Since there
are no impacts on accident initiating events or component failures,
the probability of an accident previously evaluated is not affected.
The radioactive material source terms and release paths used in the
safety analyses are unchanged, thus the radiological releases in the
Updated Final Safety Analysis Report (UFSAR) accident analyses are
not affected.
Therefore, the proposed amendment does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No
The proposed changes to the WLS system do not adversely affect
the design or quality of any structure, system or component.
Revising the WLS safety functions and re-classifying the drain hubs
as nonsafety-related does not create a new fault or sequence of
events that could result in a radioactive material release nor do
the changes to the WLS piping connections, valve types and the
depiction of components on the figure have any impact on any
accident previously evaluated.
Therefore, the proposed amendment does not create the
possibility of a new or different kind of accident.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No
The proposed changes to the WLS system drain hubs, piping
connection, valve type, and Tier 1 figure depiction would not affect
any radioactive material barrier. No safety analysis or design basis
acceptance limit/criterion is challenged or exceeded by the proposed
change, thus no margin of safety is reduced.
Therefore, the proposed amendment does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Ms. Kathryn M. Sutton, Morgan, Lewis &
Bockius LLC, 1111 Pennsylvania Avenue NW., Washington, DC 20004-2514.
NRC Branch Chief: Lawrence Burkhart.
[[Page 57184]]
Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50-
425, Vogtle Electric Generating Plant, Units 1 and 2, Burke County,
Georgia
Date of amendment request: August 20, 2013.
Description of amendment request: The proposed amendments would
revise the Vogtle Electric Generating (VEGP) Emergency Plan by revising
the Emergency Action Level (EAL) thresholds for certain Initiating
Conditions. The proposed change will remove certain Main Steam Line
(MSL) radiation monitors from the reference initiating conditions to
address limitations of these monitors.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No
The proposed change to the emergency plan does not impact the
physical function of plant structures, systems, or components (SSCs)
or the manner in which SSCs perform their design function. The
proposed changes neither adversely affect accident initiators or
precursors, nor alter design assumptions.
The proposed changes do not alter or prevent the ability of
operable SSCs to perform their intended function to mitigate the
consequences of an initiating event within assumed acceptance
limits. No operating procedures or administrative controls that
function to prevent or mitigate accidents are affected by the
proposed change.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes do not impact the accident analysis. The
changes do not involve a physical alteration of the plant (i.e., no
new or different type of equipment will be installed), a change in
the method of plant operation, or new operator actions. The proposed
change will not introduce failure modes that could result in a new
accident, and the change does not alter assumptions made in the
safety analysis. The proposed changes revise EALs, which establish
the thresholds for placing the plant in an emergency classification.
EALs are not initiators of any accidents.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any accident previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
Margin of safety is associated with confidence in the ability of
the fission product barriers (i.e., fuel cladding, reactor coolant
system pressure boundary, and containment structure) to limit the
level of radiation dose to the public. The proposed changes are
associated with the EALs and do not impact operation of the plant or
its response to transients or accidents. The changes do not affect
the TSs or the operating license. The proposed changes do not
involve a change in the method of plant operation, and no accident
analyses will be affected by the proposed changes. Additionally, the
proposed changes will not relax any criteria used to establish
safety limits and will not relax any safety system settings. The
safety analysis acceptance criteria are not affected by these
changes. The proposed changes will not result in plant operation in
a configuration outside the design basis. The proposed change does
not adversely affect systems that respond to safely shutdown the
plant and to maintain the plant in a safe shutdown condition.
The revised EAL provides more appropriate and accurate criteria
for determining protective measures that should be considered within
and outside the site boundary to protect health and safety. The
emergency plan will continue to activate an emergency response
commensurate with the extent of degradation of plant safety.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
Based on the above, SNC has determined that operation of the
facility in accordance with the proposed changes does not involve a
significant hazards consideration as defined in 10 CFR 50.92(c), in
that it does not: (1) involve a significant increase in the
probability or consequences of an accident previously evaluated; or
(2) create the possibility of a new or different kind of accident
from any accident previously evaluated.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Leigh D. Perry, SVP & General Counsel,
Southern Nuclear Operating Company, 40 Inverness Center Parkway,
Birmingham, AL 35242.
NRC Branch Chief: Robert Pascarelli.
Previously Published Notices 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 following notices were previously published as separate
individual notices. The notice content was the same as above. They were
published as individual notices either because time did not allow the
Commission to wait for this biweekly notice or because the action
involved exigent circumstances. They are repeated here because the
biweekly notice lists all amendments issued or proposed to be issued
involving no significant hazards consideration.
For details, see the individual notice in the Federal Register on
the day and page cited. This notice does not extend the notice period
of the original notice.
Tennessee Valley Authority, Docket No. 50-259, Browns Ferry Nuclear
Plant, Unit 1, Limestone County, Alabama
Date of application for amendments: August 14, 2013.
Description of amendments request: The proposed amendment would
delete the Notes that cover the Reactor Coolant System (RCS) Pressure
and Temperature Limits curves on Technical Specification 3.4.9, ``RCS
Pressure and Temperature (P/T) Limits,'' Figures 3.4.9-1 and 3.4.9-2
that are applicable from 12 Effective Full Power Years (EFPY) to 16
EFPY and allows the usage of the figures up to 16 EFPY. The current
notes state, ``Do Not Use This Figure. This curve applies to operations
> 12 EFPY. For current operation, use previous curve, which is valid up
to 12 EFPY.''
Date of publication of individual notice in the Federal Register:
August 23, 2013 (78 FR 52571).
Expiration date of individual notice: September 6, 2013 (Public
comments) and October 22, 2013 (Hearing requests).
Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of 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
[[Page 57185]]
published in the Federal Register as indicated.
Unless otherwise indicated, 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. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items are available for public inspection at
the Commission'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. If you do not have access to ADAMS
or if there are problems in accessing the documents located in ADAMS,
contact the PDR's Reference staff at 1-800-397-4209, 301-415-4737 or by
email to pdr.resource@nrc.gov.
Carolina Power and Light Company, et al., Docket No. 50-261, H.B.
Robinson Steam Electric Plant, Unit No. 2, Darlington County, South
Carolina
Date of application for amendment: August 29, 2012, as supplemented
by letters dated March 6, 2013, April 9, 2013, and August 22, 2013.
Brief description of amendment: The license amendment combined two
changes that affected the same Technical Specification (TS) sections.
The first part implemented revisions consistent with TS Task Force--
510, Revision 2, ``Revision to Steam Generator (SG) Program Inspection
Frequencies and Tube Sample Selection.'' The second part revised TS
5.5.9 ``Steam Generator Program'' to exclude portions of the SG tube
below the top of the SG tubesheet form periodic inspections by
implementing the permanent alternate criteria ``H*''.
Date of issuance: August 29, 2013.
Effective date: This license amendment is effective as of the date
of its issuance and shall be implemented within 30 days.
Amendment No.: 235.
Renewed Facility Operating License No. DPR-23: Amendment changed
the license and TSs.
Date of initial notice in Federal Register: October 16, 2012, 2012
(77 FR 63348). The supplements dated March 6, 2013, April 9, 2013, and
August 22, 2013, provided additional information that clarified the
application, did not expand the scope of the application as originally
noticed, and did not change the staff's original proposed no
significant hazards consideration determination as published in the
Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 29, 2013.
No significant hazards consideration comments received: No.
Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287,
Oconee Nuclear Station, Units 1, 2, and 3, Oconee County, South
Carolina
Date of application of amendments: October 30, 2012, as
supplemented by letters dated July 16 and July 26, 2013.
Brief description of amendments: The amendments revised the
Technical Specifications related to limits on outage times for the
Keowee Hydro Units, which are the onsite electrical power supply for
the Oconee Nuclear Station.
Date of Issuance: August 23, 2013.
Effective date: As of the date of issuance and shall be implemented
within 30 days from the date of issuance.
Amendment Nos.: 382, 384, and 383.
Renewed Facility Operating License Nos. DPR-38, DPR-47, and DPR-55:
Amendments revised the licenses and the technical specifications.
Date of initial notice in Federal Register: February 19, 2013, 78
FR 11691. The supplements dated July 16 and July 26, 2013, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated August 23, 2013.
No significant hazards consideration comments received: No.
Florida Power and Light Company, et al., Docket Nos. 50-335 and 50-389,
St. Lucie Plant Unit Nos. 1 and 2, St. Lucie County, Florida
Date of application for amendment: December 27, 2012.
Brief description of amendment: The amendments revised the
Technical Specifications (TSs) to align with Combustion Engineering
Owners Group TS language describing required licensed Senior Reactor
Operator duties during fuel-handling activities.
Date of issuance: August 30, 2013.
Effective date: As of the date of issuance and shall be implemented
within 90 days.
Amendment Nos.: 216 and 166.
Facility Operating License Nos. DPR-77 and DPR-79: Amendments
revised the License and TS.
Date of initial notice in Federal Register: March 19, 2013 (78 FR
16884).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 30, 2013.
No significant hazards consideration comments received: No.
Northern States Power Company--Minnesota (NSPM), Docket No. 50-263,
Monticello Nuclear Generating Plant (MNGP), Wright County, Minnesota
Date of application for amendment: August 21, 2012, as supplemented
on November 7, 2012, and March 22, 2013.
Brief description of amendment: The amendment revises the MNGP
Renewed Facility Operating Licensing and Technical Specifications to
(1) correct typographical errors; (2) remove obsolete information; (3)
remove outdated references to a letter that, in part, specified spent
fuel pool storage capability; (4) make editorial changes; and (5)
correct a pagination error from a previously-issued license amendment.
Date of issuance: August 28, 2013.
Effective date: As of the date of issuance and shall be implemented
within 90 days from the date of issuance.
Amendment No.: 175.
Renewed Facility Operating License No. DPR-22: Amendment revises
the Renewed Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: December 26, 2012 (77
FR 76081). The supplements dated November 7, 2012, and March 22, 2013,
provided additional information that clarified the application, did not
expand the scope of the application as originally noticed, and did not
change the staff's original proposed no significant hazards
consideration determination.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 28, 2013.
No significant hazards consideration comments received: No.
[[Page 57186]]
Northern States Power Company--Minnesota, Docket Nos. 50-282 and 50-
306, Prairie Island Nuclear Generating Plant, Units 1 and 2, Goodhue
County, Minnesota
Date of application for amendments: August 19, 2011, supplemented
by letters dated May 16, 2012, September 4, 2012, February 8, 2013, and
July 17, 2013.
Brief description of amendments: The amendments revised TS 3.7.17,
``Spent Fuel Pool Storage,'' and TS 4.3.1, ``Fuel Storage Criticality''
to provide new spent fuel pool (SFP) loading restrictions that meet
subcriticality for all postulated conditions. The TS changes will
correct non-conservatisms in the SFP criticality analysis-of-record.
Date of issuance: August 29, 2013.
Effective date: As of the date of issuance and shall be implemented
within 120 days.
Amendment Nos.: Unit 1--209; Unit 2--196.
Renewed Facility Operating License Nos. DPR-42 and DPR-60:
Amendments revised the Facility Operating Licenses and Technical
Specifications.
Date of initial notice in Federal Register: February 14, 2012 (77
FR 8291). The supplemental letters dated May 16, 2012, September 4,
2012, February 8, 2013, and July 17, 2013, provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change the staff's
original proposed no significant hazards consideration determination as
published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 29, 2013.
No significant hazards consideration comments received: No.
Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296,
Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3, Limestone County,
Alabama
Date of application for amendments: August 28, 2012, as
supplemented by letter dated August 29, 2013.
Description of amendment request: The amendments deleted references
to the American Society of Mechanical Engineers (ASME) Code, Section
XI, and added references to the ASME Code for Operation and Maintenance
of Nuclear Power Plants to Section 5.5.6, ``Inservice Testing
Program,'' to the Technical Specifications. The amendment also allows a
25-percent extension of surveillance interval using the Surveillance
Requirement 3.0.2 provisions to other normal and accelerated
frequencies specified as two years or less in the Inservice Test
Program.
Date of issuance: August 30, 2013.
Effective date: Date of issuance, to be implemented within 60 days.
Amendment Nos.: Unit 1--283, Unit 2--310, and Unit 3--269.
Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68:
Amendments revised the licenses and Technical Specifications.
Date of initial notice in Federal Register: November 27, 2012 (77
FR 70844). The supplement dated August 29, 2013, provided additional
information that clarified the application, did not expand the scope of
the application as originally noticed, and did not change the staff's
original proposed no significant hazards consideration determination as
published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 30, 2013.
No significant hazards consideration comments received: No.
Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek
Generating Station, Coffey County, Kansas
Date of amendment request: October 18, 2012, as supplemented by
letter dated March 20, 2013.
Brief description of amendment: The amendment revised paragraph
2.C(5)(a) of the renewed facility operating license and the fire
protection program as described in the Updated Safety Analysis Report
(USAR) to allow a deviation from the separation requirements of 10 CFR
Part 50, Appendix R, Section III.G.2, as documented in Appendix 9.5E of
the Wolf Creek Generating Station USAR, for the volume control tank
outlet valves.
Date of issuance: August 23, 2013.
Effective date: As of its date of issuance and shall be implemented
within 90 days of the date of issuance.
Amendment No.: 205.
Renewed Facility Operating License No. NPF-42. The amendment
revised the Operating License.
Date of initial notice in Federal Register: December 11, 2012 (77
FR 73692). The supplemental letter dated March 20, 2013, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated August 23, 2013.
No significant hazards consideration comments received: No.
Dated at Rockville, Maryland, this 6th day of September 2013.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2013-22469 Filed 9-16-13; 8:45 am]
BILLING CODE 7590-01-P