[Federal Register Volume 78, Number 180 (Tuesday, September 17, 2013)]
[Notices]
[Pages 57180-57186]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2013-22469]


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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 http://www.regulations.gov and search for Docket ID NRC-2013-0209. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: [email protected].
     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 http://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 http://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 [email protected]. 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 http://www.regulations.gov as well as entering the comment submissions into 
ADAMS, and the NRC does not edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information in their comment submissions 
that they do not want to be publicly disclosed. Your request should 
state that the NRC will not edit comment submissions to remove such 
information before making the comment submissions available to the 
public or entering the comment submissions into ADAMS.
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 http://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 [email protected], 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 http://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 http://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 http://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 http://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 http://www.nrc.gov/site-help/e-submittals.html, by email at 
[email protected], 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,

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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 
http://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 http://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 [email protected].

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.

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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

    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 http://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 [email protected].

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