[Federal Register Volume 77, Number 54 (Tuesday, March 20, 2012)]
[Notices]
[Pages 16271-16278]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2012-6261]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[NRC-2012-0061]


Biweekly Notice: Applications and Amendments to Facility 
Operating 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 
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 February 23 to March 7, 2012. The last 
biweekly notice was published on March 6, 2012 (77 FR 13369).

ADDRESSES: You may access information and comment submissions related 
to this document, which the NRC possesses and is publicly available, by 
searching on http://www.regulations.gov under Docket ID NRC-2012-0061.
    You may submit comments by the following methods:
    <bullet> Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0061. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: <a href="/cdn-cgi/l/email-protection#befddfccd1d290f9dfd2d2dfd9d6dbccfed0ccdd90d9d1c8"><span class="__cf_email__" data-cfemail="0f4c6e7d606321486e63636e68676a7d4f617d6c21686079">[email protected]</span></a>.
    <bullet> Mail comments to: Cindy Bladey, Chief, Rules, 
Announcements, and Directives Branch (RADB), Office of Administration, 
Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
    <bullet> Fax comments to: RADB at 301-492-3446.
    For additional direction on accessing information and submitting 
comments, see ``Accessing Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

SUPPLEMENTARY INFORMATION:

[[Page 16272]]

I. Accessing Information and Submitting Comments

A. Accessing Information

    Please refer to Docket ID NRC-2012-0061 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:
    <bullet> Federal Rulemaking Web Site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0061.
    <bullet> 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 <a href="/cdn-cgi/l/email-protection#fd8d998fd38f988e92888f9e98bd938f9ed39a928b"><span class="__cf_email__" data-cfemail="176773653965726478626574725779657439707861">[email protected]</span></a>. Documents may be viewed in 
ADAMS by performing a search on the document date and docket number.
    <bullet> 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-2012-0061 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, 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 Title 10 of the Code of Federal 
Regulations (10 CFR) 50.92, this means that operation of the facility 
in accordance with the proposed amendment would not (1) involve a 
significant increase in the probability or consequences of an accident 
previously evaluated; (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. 
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. The NRC's 
regulations are accessible online at the NRC Library on the NRC's 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 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

[[Page 16273]]

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's 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 <a href="/cdn-cgi/l/email-protection#523a3733203b3c357c363d31393726123c20317c353d24"><span class="__cf_email__" data-cfemail="375f5256455e5950195358545c52437759455419505841">[email protected]</span></a>, or by 
telephone at 301-415-1677, to request (1) a digital identification (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 the Electronic Information Exchange System, 
users will be required to install a Web browser plug-in from the NRC's 
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 the NRC's guidance 
available on the NRC's 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's 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's Web site 
at http://www.nrc.gov/site-help/e-submittals.html, by email at 
<a href="/cdn-cgi/l/email-protection#bbf6e8f3ff95e9dec8d4cec9d8defbd5c9d895dcd4cd"><span class="__cf_email__" data-cfemail="a2eff1eae68cf0c7d1cdd7d0c1c7e2ccd0c18cc5cdd4">[email protected]</span></a>, 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, 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

[[Page 16274]]

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. 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. Non-timely filings 
will not be entertained absent a determination by the presiding officer 
that the petition or request should be granted or the contentions 
should be admitted, based on a balancing of the factors specified in 10 
CFR 2.309(c)(1)(i)-(viii).
    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 <a href="/cdn-cgi/l/email-protection#671703154915021408121504022709150449000811"><span class="__cf_email__" data-cfemail="59293d2b772b3c2a362c2b3a3c19372b3a773e362f">[email protected]</span></a>.

Duke Energy Carolinas, LLC, et al., Docket Nos. 50-413 and 50-414, 
Catawba Nuclear Station, Units 1 and 2, York County, South Carolina

    Date of amendment request: July 21, 2011.
    Description of amendment request: The amendments would revise 
Technical Specifications (TSs) 3.3.2, ``Engineered Safety Feature 
Actuation System (ESFAS) Instrumentation,'' 3.5.4, ``Refueling Water 
Storage Tank (RWST),'' and 3.6.6, ``Containment Spray System.''
    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 changes delete superseded TS requirements following 
the implementation of NRC approved modifications. As such, they do 
not adversely affect accident initiators or precursors nor do they 
alter the design assumptions, conditions, or configurations of the 
facility. The proposed changes do not alter or prevent the ability 
of Structures, Systems, and Components (SSCs) to perform their 
intended function to mitigate the consequences of an initiating 
event within the assumed acceptance limits. In review of the 
discussion above, it can be concluded that the probability or 
consequences of any accident previously evaluated will not be 
affected.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    This amendment request will not impact the accident analyses. 
The proposed changes delete superseded TS requirements following the 
implementation of NRC approved modifications. As such, they will not 
alter the requirements of any of the subject SSCs or their function 
during accident conditions. No new or different accidents will 
result from the proposed changes. The changes do not involve a 
physical alteration of the plant (i.e., no new or different type of 
equipment will be installed) or any changes in methods governing 
normal plant operation. The changes do not alter assumptions made in 
the safety analyses. The proposed changes are consistent with the 
safety analyses assumptions. In review of the discussion above, it 
can be concluded that these changes will not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed changes delete superseded TS requirements following 
the implementation of NRC approved modifications. As such, they do 
not alter the manner in which safety limits, limiting safety system 
settings, or limiting conditions for operation are determined. The 
safety analyses 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 changes do 
not adversely affect systems that respond to safely shut down the 
plant and to maintain the plant in a safe shutdown condition. In 
review of the discussion above, it can be concluded that the 
proposed changes will 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 
amendments requested involve no significant hazards consideration.
    Attorney for licensee: Lara S. Nichols, Associate General Counsel, 
Duke Energy Corporation, 526 South Church Street--EC07H, Charlotte, NC 
28202.
    NRC Branch Chief: Nancy Salgado.

    Entergy Gulf States Louisiana, LLC, and Entergy Operations, Inc., 
Docket No. 50-458, River Bend Station, Unit 1, West Feliciana Parish, 
Louisiana
    Entergy Nuclear Operations, Inc., Docket Nos. 50-155 and 72-043 
(ISFSI), Big Rock Point Plant, Charlevoix County, Michigan
    Entergy Nuclear Operations, Inc., Docket Nos. 50-003, 50-247 and 
50-286, Indian Point Nuclear Generating Units 1, 2 and 3, Westchester 
County, New York
    Entergy Nuclear Operations, Inc., Docket No. 50-333, James A. 
FitzPatrick Nuclear Power Plant, Oswego County, New York
    Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades 
Nuclear Plant, Van Buren County, Michigan
Entergy Nuclear Operations, Inc., Docket No. 50-293, Pilgrim Nuclear 
Power Station, Plymouth County, Massachusetts
Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, 
Inc., Docket No. 50-271, Vermont Yankee Nuclear Power Station, Vernon, 
Vermont
Entergy Operations, Inc., Docket Nos. 50-313 and 50-368, Arkansas 
Nuclear One, Units 1 and 2, Pope County, Arkansas
Entergy Operations, Inc., System Energy Resources, Inc., South 
Mississippi Electric Power Association, and Entergy Mississippi, Inc., 
Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1, Claiborne 
County, Mississippi
Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric 
Station, Unit 3, St. Charles Parish, Louisiana

    Date of amendment request: December 13, 2011.
    Description of amendment request: The amendments would approve 
changes to the Quality Assurance Program Manual (QAPM) and Technical 
Specifications (TSs) for the above specified plants. The proposed 
changes standardize unit staff qualification requirements for the 
Entergy fleet. Certain changes to the QAPM are a reduction in 
commitment and, in accordance with 10 CFR 50.54(a)(4), NRC approval is 
required prior to implementation. The related TS changes for unit staff 
qualifications are requested in accordance with 10 CFR 50.90.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the

[[Page 16275]]

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 changes involve the revision or relocation of 
administrative requirements associated with unit staff 
qualifications and will not impact the design, operation, testing, 
performance, or reliability of any plant system or component. The TS 
changes will require plants currently required to be qualified per 
ANSI [American National Standards Institute] N18.1-1971 to be 
qualified to the later standard of ANSI/ANS [American Nuclear 
Society] 3.1-1978. The changes do not affect licensed operator 
qualifications or training, which will continue to comply with 
applicable regulations. Qualification requirements for the Shift 
Technical Advisor (STA) are revised to comply with a later standard 
that provides more prescriptive qualifications and ensures that the 
STA maintains an active status. The changes do not affect operating 
procedures or operator response to any accidents previously 
evaluated in the Updated Final Safety Analysis Report (UFSAR).
    Therefore, the proposed change 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 amendment is administrative in nature and does not 
introduce any credible new failure mechanisms, malfunctions, or 
accident initiators. The changes will not alter the plant 
configuration, require new plant equipment to be installed, alter 
accident analysis assumptions, introduce any new accident 
initiators, or affect the function of plant systems or the manner in 
which systems are operated, maintained, modified, tested, or 
inspected.
    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 amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed amendment involves the revision or relocation of 
administrative requirements associated with unit staff 
qualifications. The proposed change is administrative in nature and 
does not involve any physical changes to the plant or alter the 
manner in which plant systems are operated, maintained, modified, 
tested, or inspected. The proposed change does not alter the manner 
in which safety limits, limiting safety system settings or limiting 
conditions for operation are determined. The safety analysis 
acceptance criteria are not affected by this change. The proposed 
change 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.
    Therefore, the proposed change 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.
    Attorneys for licensee: Joseph A. Aluise, Associate General 
Counsel--Nuclear, Entergy Services, Inc., 639 Loyola Avenue, New 
Orleans, LA 70113 (for River Bend Station, Unit 1, Arkansas Nuclear 
One, Units 1 and 2, Grand Gulf Nuclear Station, Unit 1, and Waterford 
Steam Electric Station, Unit 3); and William C. Dennis, Assistant 
General Counsel, Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, 
White Plains, NY 10601 (for Big Rock Point Plant (ISFSI), James A. 
Fitzpatrick Nuclear Power Plant, Indian Point Nuclear Generating Units 
1, 2, and 3, Palisades Nuclear Plant, Pilgrim Nuclear Power Station, 
and Vermont Yankee Nuclear Power Station).
    NRC Branch Chief: Michael T. Markley.

Notice of Issuance of Amendments to Facility Operating 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, proposed no significant hazards consideration 
determination, and opportunity for a hearing in connection with these 
actions, was 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 NRC's Public Document Room (PDR), located at One White Flint North, 
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 
20852. Publicly available documents created or received at the NRC are 
accessible online 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 
<a href="/cdn-cgi/l/email-protection#86f6e2f4a8f4e3f5e9f3f4e5e3c6e8f4e5a8e1e9f0"><span class="__cf_email__" data-cfemail="275743550955425448525544426749554409404851">[email protected]</span></a>.

Detroit Edison Company, Docket No. 50-341, Fermi 2, Monroe County, 
Michigan

    Date of application for amendment: August 12, 2011, supplemented by 
letter dated October 20, 2011.
    Brief description of amendment: The amendment revised TS 3.8.3, 
``Diesel Fuel Oil and Starting Air,'' by relocating the current stored 
diesel fuel oil numerical volume requirements from the Technical 
Specification to the TS Bases consistent with Technical Specification 
Task Force TSTF-501.
    Date of issuance: February 24, 2012.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment No.: 188.
    Facility Operating License No. NPF-43: Amendment revised the 
Technical Specifications and License.
    Date of initial notice in Federal Register: October 4, 2011 (76 FR 
61394).
    The supplemental letter dated October 20, 2011 did not change 
staff's original proposed no significant hazards consideration 
determination as published in the initial Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated February 24, 2012.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. 50-373, LaSalle County 
Station, Unit 1, LaSalle County, Illinois


[[Page 16276]]


    Date of application for amendment: October 12, 2011, as 
supplemented by letter(s) dated January 30, 2012, and February 13, 
2012.
    Brief description of amendment: The amendment request proposed 
changes to the Technical Specifications (TSs) to revise Section 2.1.1, 
``Reactor Core SLs'' minimum critical power ratio safety limit (MCPR 
SL) from >= 1.11 to >= 1.13 for two-loop recirculation operation and 
from >= 1.12 to >= 1.15 for a single-loop recirculation operation.
    Date of issuance: March 1, 2012.
    Effective date: As of the date of issuance and shall be implemented 
after Cycle 14 is completed and prior to the operation of Cycle 15.
    Amendment No.: 205.
    Facility Operating License Nos. NPF-11: The amendment revised the 
Technical Specifications and License.
    Date of initial notice in Federal Register: January 3, 2012 (77 FR 
139).
    The January 30, 2012, and February 13, 2012, supplements contained 
clarifying information, did not expand the scope of the application as 
originally noticed, and did not change the staff's original proposed no 
significant hazards consideration (NSHC) determination.
    The Commission's related evaluation of the amendment and final NSHC 
determination is contained in a Safety Evaluation dated March 1, 2012.
    No significant hazards consideration comments received: No.

Florida Power and Light Company, Docket Nos. 50-250 and 50-251, Turkey 
Point Plant, Units 3 and 4, Miami-Dade County, Florida

    Date of application for amendment: February 21, 2011, as 
supplemented by letter dated July 21, 2011.
    Brief description of amendment: Selected figures and values from 
the technical specifications (TSs) are being relocated to the Core 
Operating Limits Report (COLR), including TS Figure 2.1-1 cited in TS 
2.1.1, selected portions of Note 1 on Overtemperature [Delta] T and 
Note 3 on Overpower [Delta] T cited in TS Table 2.2-1, TS Figure 3.1-1 
cited in TS 3/4.1.1.1, Shutdown Margin value cited in TS 3/4.1.1.2, 
Moderator Temperature Coefficient values cited in TS 3/4.1.1.3, and 
Departure from Nucleate Boiling values cited in TS 3.2.5. The 
description of the COLR in TS 6.9.1.7 is also revised to reflect these 
changes. The affected TS figures and technical limits cited above are 
only being relocated to the COLR and are not being changed under this 
license amendment.
    Date of issuance: February 23, 2012.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: Unit 3--247 and Unit 4--243.
    Renewed Facility Operating License Nos. DPR-31 and DPR-41: 
Amendments revised the Technical Specifications and Surveillance 
Requirements.
    Date of initial notice in Federal Register: May 31, 2011 (76 FR 
31374). The supplement dated July 21, 2011, 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 amendments is contained 
in a Safety Evaluation dated February 23, 2012.
    No significant hazards consideration comments received: No.

NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold 
Energy Center, Linn County, Iowa

    Date of application for amendment: February 23, 2011, as 
supplemented by letters dated April 20, August 15, November 1, 2011, 
and February 3, 2012.
    Brief description of amendment: The amendment revised the Technical 
Specifications (TSs) by relocating specific surveillance frequencies to 
a licensee-controlled program with the guidance of Nuclear Energy 
Institute (NEI) 04-10, ``Risk-Informed Technical Specifications 
Initiative 5b, Risk-Informed Method for Control of Surveillance 
Frequencies.'' The amendment adopted NRC-approved Technical 
Specification Task Force (TSTF)-425, Revision 3, ``Relocate 
Surveillance Frequencies to Licensee Control--RITSTF [Risk-Informed 
TSTF] Initiative 5b.'' When implemented, TSTF-425 relocates most 
periodic frequencies of TS surveillances to a licensee-controlled 
program, the Surveillance Frequency Control Program, and provides 
requirements for the new program in the Administrative Controls section 
of the TSs.
    Date of issuance: February 24, 2012.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days.
    Amendment No.: 280.
    Renewed Facility Operating License No. DPR-49: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: May 17, 2011 (76 FR 
28474).
    The supplemental letters dated April 20, August 15, November 1, 
2011 and February 3, 2012, 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 February 24, 2012.
    No significant hazards consideration comments received: No.

NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit 
1, Rockingham County, New Hampshire

    Date of amendment request: April 21, 2011.
    Description of amendment request: The amendment revised operability 
requirements for the leakage detection systems, eliminated redundant 
Technical Specification (TS) requirements, and revised the TS actions 
to include conditions and required actions for inoperable leakage 
detection systems similar to those in NUREG 1431, ``Standard Technical 
Specifications--Westinghouse Plants.'' The amendment also incorporated 
the requirements of TSTF-513, Revision 3, ``Revise [Pressurized Water 
Reactor] Operability Requirements and Actions for [Reactor Coolant 
System] Leakage Instrumentation.''
    Date of issuance: February 23, 2012.
    Effective date: As of its date of issuance and shall be implemented 
within 90 days.
    Amendment No.: 129.
    Facility Operating License No. NPF-86: The amendment revised the TS 
and the License.
    Date of initial notice in Federal Register: August 9, 2011 (76 FR 
48913).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated February 23, 2012.
    No significant hazards consideration comments received: No.

NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit 
1, Rockingham County, New Hampshire

    Date of amendment request: November 17, 2011.
    Description of amendment request: The proposed change revises 
Technical Specification 3.3.3.5, ``Remote Shutdown System Table 3.3-
9,'' by removing the location information of transfer switches, control 
circuits, and instruments.
    Date of issuance: February 28, 2012.
    Effective date: As of its date of issuance and shall be implemented 
within 30 days.
    Amendment No.: 130.

[[Page 16277]]

    Facility Operating License No. NPF-86: The amendment revised the TS 
and the License.
    Date of initial notice in Federal Register: December 27, 2011 (76 
FR 80976).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated February 28, 2012.
    No significant hazards consideration comments received: No.

South Carolina Electric & Gas Company, South Carolina Public Service 
Authority, Docket No. 50-395, Virgil C. Summer Nuclear Station, Unit 1, 
Fairfield County, South Carolina

    Date of application for amendment: May 2, 2011.
    Brief description of amendment: This license amendment revised the 
Technical Specifications (TSs) 3.4.6.1, ``RCS [Reactor Coolant System] 
Leakage Detection Systems,'' to define a new time limit for restoring 
inoperable RCS leakage detection instrumentation to operable status, 
establish alternate methods of monitoring RCS leakage when monitors are 
inoperable, and to reflect the requested changes and more accurately 
reflect the contents of the facility design bases related to the 
operability of the RCS leakage detection instrumentation.
    Date of issuance: February 22, 2012.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days.
    Amendment No.: 186.
    Renewed Facility Operating License No. NPF-12: Amendment revises 
the License and TSs.
    Date of initial notice in Federal Register: July 12, 2011 (76 FR 
40941).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated February 22, 2012.
    No significant hazards consideration comments received: No.
South Carolina Electric & Gas Company, Docket No. 50-395, Virgil C. 
Summer, Nuclear Station Unit 1, Jenkinsville, South Carolina

    Date of application for amendment: April 18, 2011, and supplemented 
by letter dated September 26, 2011.
    Brief description of amendment: This amendment revised the VCSNS 
Technical Specification Table 4.3-2 for the ``Engineered Safety Feature 
Actuation System Instrumentation'' to allow the surveillance frequency 
to be expanded from quarterly to every 18 months or refueling for the 
specific Westinghouse type AR relays used as Solid State Protection 
System slave relays or auxiliary relays.
    Date of Issuance: March 6, 2012.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days.
    Amendment No: 187.
    Renewed Facility Operating License No. NPF-12: Amendment revised 
the Licenses and Technical Specifications.
    Date of initial notice in Federal Register: August 16, 2011 (76 FR 
50763).
    The licensee's supplemental letter contained clarifying 
information, did not change the scope of the original license amendment 
request, did not change the NRC staff's initial proposed finding of no 
significant hazards consideration determination, and did not expand the 
scope of the original Federal Register notice.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 6, 2012.
    No significant hazards consideration comments received: No.

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 application for amendment: March 3, 2011.
    Brief description of amendment: The amendments revised the 
Technical Specifications (TS) 3.3.1 Reactor Trip System Instrumentation 
Table 3.3.1-1 and TS 3.3.2 Emergency System Feature Actuation System 
Table 3.3.2-1. Specifically, the change incorporates the Technical 
Specification Task Force Traveler TSTF-493-A, ``Clarify Application of 
Setpoint Methodology for LSSS [limiting safety system setting] 
Function. The setpoint methodology incorporates revised (more 
conservative) calculations associated with the P-14, Steam Generator 
Water Level High-High instrument setpoint and associated allowable 
value. Also, the amendments contain administrative changes. 
Specifically, the amendment correct a typographical error on TS Table 
3.3.1-1, page 9 of 9, and deletes an expired allowance provided by TS 
Table 3.3.2-1, Note J.
    Date of issuance: February 27, 2012.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment Nos.: Unit 1--165 and Unit 2--147.
    Facility Operating License Nos. NPF-68 and NPF-81: Amendments 
revised the licenses and the technical specifications.
    Date of initial notice in Federal Register: May 24, 2011 (re-
noticed on July 12, 2011).
    The supplements dated August 12, 2011, and December 9, 2011, 
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 Safety Evaluation dated February 27, 2012.
    No significant hazards consideration comments received: No.

Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, 
North Anna Power Station, Units 1 and 2, Louisa County, Virginia

    Date of application for amendment: July 19, 2010, and supplemented 
by additional information dated September 9, 2010, January 26, 2011, 
and May 16, 2011, contained clarifying information only and did not 
change the initial no significant hazards determination or expand the 
scope of the initial application.
    Brief description of amendment: The proposed amendments revise 
Technical Specification 5.6.5.b, ``Core Operating Limits Report 
(COLR),'' to include Appendix C, ``Qualification of the Westinghouse 
WRB-2M CHF Correlation in the Dominion VIPRE-D Computer Code.'' This 
would allow NAPS to use the VIPRE-D/WRB-2M and VIPRE-D/W-3 correlation 
pairs to perform licensing calculations with Westinghouse RFA-2 fuel in 
the cores.
    Date of issuance: February 29, 2012.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment Nos.: Unit 1--266 and Unit 2--247.
    Renewed Facility Operating License Nos. NPF-4 and NPF-7: Amendments 
changed the licenses and the technical specifications.
    Date of initial notice in Federal Register: July 26, 2011 (76 FR 
44618).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated February 29, 2012.
    No significant hazards consideration comments received: No.

Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, 
North Anna Power Station, Units 1 and 2, Louisa County, Virginia

    Date of application for amendment: October 21, 2010, as 
supplemented by letter dated June 23, 2011, and August 22, 2011, 
contained clarifying information only and did not change the initial no 
significant hazards determination or expand the scope of the initial 
application.

[[Page 16278]]

    Brief description of amendment: The proposed amendments revised 
Technical Specification 5.6.5.b, ``Core Operating Limits Report 
(COLR),'' to permit the use of the ``Westinghouse Best Estimate--Large 
Break Loss-of-Coolant Accident (BE-LBLOCA) Evaluation Methodology using 
the Automated Statistical Treatment of Uncertainty Method (ASTRUM)'' 
for the analysis of LBLOCA.
    Date of issuance: February 29, 2012.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment Nos.: Unit 1--267 and Unit 2--248.
    Renewed Facility Operating License Nos. NPF-4 and NPF-7: Amendments 
changed the licenses and the technical specifications.
    Date of initial notice in Federal Register: November 30, 2010 (75 
FR 74097).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated February 29, 2012.
    No significant hazards consideration comments received: No.

    For the Nuclear Regulatory Commission.

    Dated at Rockville, Maryland, this 8th day of March 2012.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2012-6261 Filed 3-19-12; 8:45 am]
BILLING CODE 7590-01-P


</pre><script data-cfasync="false" src="/cdn-cgi/scripts/5c5dd728/cloudflare-static/email-decode.min.js"></script></body>
</html>