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Daily Rules, Proposed Rules, and Notices of the Federal Government

NUCLEAR REGULATORY COMMISSION

[NRC-2012-0236]

Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards ConsiderationsBackground

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 September 20, 2012 to October 3, 2012. The last biweekly notice was published on October 2, 2012 (77 FR 60146-60160).

Addresses:You may access information and comment submissions related to this document, which the NRC possesses and are publicly available, by searching onhttp://www.regulations.govunder Docket ID NRC-2012-0236. You may submit comments by any of the following methods:

*Federal Rulemaking Web site:Go tohttp://www.regulations.govand search for Docket ID NRC-2012-0236. Address questions about NRC dockets to Carol Gallagher; telephone: 301-492-3668; email:Carol.Gallagher@nrc.gov.

*Mail comments to:Cindy Bladey, Chief, Rules, Announcements, and Directives Branch (RADB), Office of Administration, Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

*Fax comments to:RADB at 301-492-3446.

For additional direction on accessing information and submitting comments, see "Accessing Information and Submitting Comments" in theSupplementary Informationsection of this document.

Supplementary Information:

I. Accessing Information and Submitting CommentsA. Accessing Information

Please refer to Docket ID NRC-2012-0236 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 are publicly available, by any of the following methods:

*Federal Rulemaking Web site:Go tohttp://www.regulations.govand search for Docket ID NRC-2012-0236.

*NRC's Agencywide Documents Access and Management System (ADAMS):You may access publicly available documents online in the NRC Library athttp://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 topdr.resource@nrc.gov.Documents may be viewed in ADAMS by performing a search on the document date and docket number.

*NRC's PDR:You may examine and purchase copies of public documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.

B. Submitting Comments

Please include Docket ID NRC-2012-0236 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 that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions athttp://www.regulations.govas well as enter the comment submissions into ADAMS. The NRC does not routinely 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 that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely 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 section 50.92 of Title 10 of theCode 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 theFederal Registera 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. The NRC regulations are accessible electronically from the NRC Library on the NRC's Web site athttp://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 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 finaldetermination 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 the 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 athearing.docket@nrc.gov, 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 athttp://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 athttp://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 athttp://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 guidance available on the NRC's public Web site athttp://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 Web site athttp://www.nrc.gov/site-help/e-submittals.html, by email atMSHD.Resource@nrc.gov,or by a toll-free call at 1-866 672-7640. The NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., Eastern Time, Monday through Friday, excluding government holidays.

Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) First class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to the Office of the Secretary, Sixteenth Floor, One White Flint North, 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 athttp://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. 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 leaveto 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 athttp://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC's PDR Reference staff at 1-800-397-4209, 301-415-4737, or by email topdr.resource@nrc.gov.

Carolina Power and Light Company, Docket Nos. 50-325 and 50-324, Brunswick Steam Electric Plant, Units 1 and 2, Brunswick County, North Carolina.

Date of amendment request:June 19, 2012.

Description of amendment request:The proposed license amendments would revise the Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The TS change proposes to extend the Completion Time (CT) of TS 3.8.1 Required Action D.4 for an inoperable diesel generator (DG). A commensurate change is also proposed to extend the maximum CT of TS 3.8.1 Required Actions C.3 and D.4. The licensee stated that it will add a supplemental alternating current power source (i.e., a supplemental diesel generator) with the capability to power any E-bus within one hour from the Station Blackout (SBO) event, and with the capacity to bring the affected unit to cold shutdown, to support this request.

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:

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:David T. Conley, Senior Counsel--Manager Legal Department, Progress Energy Service Company, LLC, Post Office Box 1551, Raleigh, NC 27602.

NRC Acting Branch Chief:Jessie Quichocho.

Carolina Power and Light Company, Docket Nos. 50-325 and 50-324, Brunswick Steam Electric Plant, Units 1 and 2, Brunswick County, North Carolina;Florida Power Corporation, et al., Docket No. 50-302, Crystal River Unit 3 Nuclear Generating Plant, Citrus County, FloridaCarolina Power & Light Company, et al., Docket No. 50-400, Shearon Harris Nuclear Power Plant, Unit 1, Wake and Chatham Counties, North Carolina;Carolina Power & Light Company, Docket No. 50-261, H. B. Robinson Steam Electric Plant,Unit 2, Darlington County, South Carolina

Date of amendment request:September 12, 2012.

Description of amendment request:The proposed license amendments would revise the Facility Operating Licenses for the Brunswick Steam Electric Plant, Units 1 and 2, H. B. Robinson Steam Electric Plant, Unit 2, Shearon Harris Nuclear Power Plant, Unit 1, and Crystal River Unit No. 3 Nuclear Generating Plant. The NRC issued license amendments, dated July 29, 2011, that approved the licensees' cyber security plan and associated implementation milestone schedule. Milestone 6 requires the identification, documentation, and implementation of cyber security controls for critical digital assets that could adversely impact the design function of physical security target set equipment by no later than December 31, 2012. The license amendment request would change the existing facility operating licenses for the Physical Protection/Security license condition for these plants to reference the change to an implementation schedule milestone and a proposed Revised Cyber Security Plan Implementation Schedule for the scope of Milestone 6.

Basis for proposed no significant hazards consideration determination:As required by10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:

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:Lara S. Nichols, Deputy General Counsel, Duke Energy Corporation, 550 South Tyron Street, Mail Code DEC45A, Charlotte, NC 28202.

NRC Acting Branch Chief:Jessie Quichocho.

Carolina Power and Light Company, Docket No. 50-261, H. B. Robinson Steam Electric Plant, Unit 2, (HBRSEP) Darlington County, South Carolina

Date of amendment request:August 6, 2012.

Description of amendment request:The proposed change would revise the Technical Specification (TS) requirements for inoperable snubbers by adding Limiting Condition for Operation (LCO) 3.0.8. The change is consistent with NRC approved Revision 4 to Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-372, "Addition of LCO 3.0.8, Inoperability of Snubbers."

The NRC staff issued a notice of availability of a model safety evaluation and model no significant hazards consideration (NSHC) determination for referencing in license amendment applications in theFederal Registeron May 4, 2005 (70 FR 23252). The licensee affirmed the applicability of the model NSHC determination in its application dated August 6, 2012.

Basis for proposed no significant hazards consideration determination:As required by10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:

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:David T. Conley, Manager--Senior Counsel--Legal Department, Progress Energy Service Company, LLC, Post Office Box 1551, Raleigh, North Carolina 27602.

NRC Acting Branch Chief:Jessie F. Quichocho.

Carolina Power & Light Company, Docket No. 50-261, H. B. Robinson Steam Electric Plant, Unit 2, (HBRSEP) Darlington County, South Carolina

Date of amendment request:August 29, 2012.

Description of amendment request:The proposed change combines two changes that affect the same Technical Specification (TS) sections into one license amendment. The first part proposes to implement revisions consistent with Technical Specification Task Force (TSTF)-510, Revision 2, "Revision to Steam Generator (SG) Program Inspection Frequencies and Tube Sample Selection." The second part proposes to permanently revise TS 5.5.9 "Steam Generator Program" to exclude portions of the SG tube below the top of the SG tubesheet from periodic inspections by implementing the permanent alternate repair criteria "H.*" References 2, 3, 8, 23 and 32 referred to in the licensees analysis can be found in the license amendment request under ADAMS Accession No. ML12275A176.

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:

The NRC staff has reviewed the license'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:David T. Conley, Manager--Senior Counsel--Legal Department, Progress Energy Service Company, LLC, Post Office Box 1551, Raleigh, North Carolina 27602.

NRC Acting Branch Chief:Jessie F. Quichocho.

Dominion Energy Kewaunee, Inc., Docket No. 50-305, Kewaunee Power Station (KPS), Kewaunee County, Wisconsin

Date of amendment request:July 30, 2012.

Description of amendment request:The proposed amendment would modify KPS Technical Specifications requirements regarding steam generator tube inspections and reporting as described in Technical Specification Task Force (TSTF)-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection."

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:

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:Lillian M. Cuoco, Senior Counsel, Dominion Resources Services, Inc., Counsel for Dominion Energy Kewaunee, Inc., 120 Tredegar Street, Richmond, VA 23219.

NRC Acting Branch Chief:Istvan Frankl.

Entergy Nuclear Operations, Inc., Docket No 50-286, Indian Point Nuclear Generating Unit 3, Westchester County, New York

Date of amendment request:August 14, 2012.

Description of amendment request:The proposed amendment would revise Technical Specification 3.5.4, "Refueling Water Storage Tank," such that the non-seismically qualified piping of the spent fuel pool purification system may be connected to the refueling water storage tank (RWST) seismic piping by manual operation of a RWST seismically qualified boundary valve under administrative controls for a limited period of time (i.e., 14 days per fuel cycle for filtration for removal of suspended solids from the RWST water). This change will only be applicable until Refueling Outage 18 (Spring 2015) ends.

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:

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:Mr. William C. Dennis, Assistant General Counsel, Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, White Plains, NY 10601.

NRC Branch Chief:George Wilson.

Entergy Nuclear Operations, Inc., Docket No. 50-286, Indian Point Nuclear Generating Unit 3, Westchester County, New York

Date of amendment request:August 14, 2012.

Description of amendment request:The amendment changes the licensing basis regarding the emergency diesel generator (EDG) fuel oil storage requirements. The current licensing basis, which requires sufficient EDG fuel oil to operate two EDGs at minimum safeguards for seven days, will be revised to provide sufficient EDG fuel oil to operate three EDGs at modified rated capacity for seven days. The Conditions, Required Actions, and Completion Times of Technical Specification (TS) 3.8.3, "Diesel Fuel Oil, and Starting Air," will be modifiedto be more consistent with the Nuclear Regulatory Commission's improved Standard Technical Specifications. Finally, TS 3.8.3 will be modified to relocate specific numerical values for EDG fuel oil storage requirements from the TSs to the TS Bases in accordance with TS Task Force (TSTF) 501 Revision 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:

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:Mr. William C. Dennis, Assistant General Counsel, Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, White Plains, NY 10601.

NRC Branch Chief:George Wilson.

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 29, 2012.

Description of amendment request:The proposed change would amend Combined License Nos.: NPF-93 and NPF-94 for Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3, respectively, by adding four non-Class 1E containment electrical penetration assemblies (EPAs). Containment EPAs are a passive extension of containment which provide the passage of the electric conductors through a single aperture in the nuclear containment structure, while providing a pressure barrier between the inside and the outside of the containment structure.

Basis for proposed no significant hazards consideration determination:As required by10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:

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:Mark E. Tonacci.

Virginia Electric and Power Company, Docket Nos. 50-280 and 50-281, Surry Power Station, Units 1 and 2, Surry County, Virginia

Date of amendment request:July 31, 2012.

Description of amendment request:The proposed amendment would modify the Technical Specifications requirements regarding steam generator tube inspections and reporting as described in TSTF-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection."

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:

Attorney for licensee:Lillian M. Cuoco, Senior Counsel, Dominion Resources Services, Inc., 120 Tredegar St., RS-2, Richmond, VA 23219.

NRC Branch Chief:Robert J. Pascarelli.

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 published in theFederal Registeras 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 electronically through the Agencywide Documents Access and Management System (ADAMS) in the NRC Library athttp://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 topdr.resource@nrc.gov.

Dominion Nuclear Connecticut, Inc., Docket No. 50-423, Millstone Power Station, Unit 3, New London County, Connecticut

Date of amendment request:November 17, 2011.

Description of amendment request:The proposed amendment would add Optimized ZIRLOTMas an allowable fuel rod cladding material and add the Westinghouse topical report on Optimized ZIRLOTMto the Millstone Power Station, Unit 3 Technical Specifications. In addition, a typographical error would be corrected.

Date of issuance:September 24, 2012.

Effective date:As of the date of issuance, and shall be implemented within 60 days.Amendment No.:253.

Renewed Facility Operating License No. NPF-69:Amendment revised the License and Technical Specifications.

Date of initial notice in Federal Register: May 15, 2012 (77 FR 28629).

The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 24, 2012.

No significant hazards consideration comments received:No.

Dominion Nuclear Connecticut, Inc., Docket No. 50-423, Millstone Power Station, Unit 3, New London County, Connecticut

Date of amendment request:July 23, 2012.

Description of amendment request:The proposed amendment would conform the Millstone Power Station Unit 3 (MPS3) licenses to reflect a name change for Central Vermont Public Service Corporation (CVPS) resultingfrom a subsequent restructuring in which CVPS will be consolidated with Gaz Metro's other electric utility subsidiary in Vermont, Green Mountain Power Corporation.

Date of issuance:October 3, 2012.

Effective date:As of the date of issuance, and shall be implemented within 30 days.Amendment No.:254.

Renewed Facility Operating License No. NPF-49:Amendment revised the License.

Date of initial notice in Federal Register: July 20, 2012 (77 FR 42768).

The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 21, 2012.

No significant hazards consideration comments received:No.

Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire Nuclear Station, Units 1 and 2, Mecklenburg County, North Carolina

Date of application for amendments:September 26, 2011, as supplemented April 16, 2012.

Brief description of amendments:The amendments revised the Technical Specifications (TSs) to incorporate aspects of NUREG-1431, "Standard Technical Specifications--Westinghouse [Electric Company] Plants," STS 3.8.3, "Diesel Fuel Oil, Lube Oil, and Starting Air," Condition E, regarding Diesel Generator starting air receiver pressure limits.

Date of issuance:September 28, 2012.

Effective date:As of the date of issuance and shall be implemented within 30 days from the date of issuance.

Amendment Nos.:Unit 1--267 and Unit 2--247.

Renewed Facility Operating License Nos. NPF-9 and NPF-17:Amendments revised the licenses and the technical specifications.

Date of initial notice in Federal Register: May 29, 2012 (77 FR 31659).

The supplement dated April 16, 2012, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination.

The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated September 28, 2012.

No significant hazards consideration comments received:No.

Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire Nuclear Station, Units 1 and 2, Mecklenburg County, North Carolina

Date of application for amendments:December 5, 2011.

Brief description of amendments:The amendments revised Technical Specification (TS) 3.3.1, Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 16(e) to replace the phrase "Turbine Impulse Pressure" with "Turbine Inlet Pressure."

Date of issuance:October 1, 2012.

Effective date:As of the date of issuance and shall be implemented within 30 days from the date of issuance.

Amendment Nos.:Unit 1--268 and Unit 2--248.

Renewed Facility Operating License Nos. NPF-9 and NPF-17:Amendments revised the licenses and the technical specifications.

Date of initial notice in Federal Register: August 9, 2012 (77 FR 47677).

The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated October 1, 2012.

No significant hazards consideration comments received:No.

Duke Energy Carolinas, LLC, Docket No. 50-269, Oconee Nuclear Station, Unit 1, Oconee County, South Carolina

Date of application of amendments:April 3, 2012

Brief description of amendments:The amendment revised the Technical Specifications related to the integrated leak rate test of the reactor containment building.

Date of Issuance:October 1, 2012.

Effective date:As of the date of issuance and shall be implemented within 30 days from the date of issuance.

Amendment No.:381.

Renewed Facility Operating License No. DPR-38:Amendment revised the license and the technical specifications.

Date of initial notice in Federal Register: July 10, 2012, 77 FR 40651.

The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated October 1, 2012.

No significant hazards consideration comments received:No.

Entergy Gulf States Louisiana, LLC, and Entergy Operations, Inc., Docket No. 50-458, River Bend Station, Unit 1 (RBS), West Feliciana Parish, Louisiana

Date of amendment request:September 12, 2011, as supplemented by letters dated October 13, 2011, March 22, 2012, and April 3, 2012.

Brief description of amendment:The amendment approved a change to the site Emergency Plan to relocate the existing backup emergency operations facility for RBS from its current location at the Entergy Operations-Baton Rouge Division Office, located at 1509 Government Street in Baton Rouge, Louisiana, approximately 23 miles southeast of RBS, to the Entergy Customer Service Center, located at 5564 Essen Lane in Baton Rouge, Louisiana, approximately 28 miles southeast of RBS.

Date of issuance:September 24, 2012.

Effective date:As of the date of issuance and shall be implemented 60 days from the date of issuance.

Amendment No.:175.

Facility Operating License No. NPF-47:The amendment revised the RBS Emergency Plan.

Date of initial notice in Federal Register: December 27, 2011 (76 FR 80975). The supplemental letters dated October 13, 2011, March 22, 2012, and April 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 theFederal Register.

The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 24, 2012.

No significant hazards consideration comments received:No.

Entergy Nuclear Operations, Inc., Docket No. 50-333, James A. FitzPatrick Nuclear Power Plant, Oswego County, New York

Date of application for amendment:August 16, 2011, as supplemented by letters dated March 30, June 13, August 1, August 16, and September 14, 2012.

Brief description of amendment:The amendment revises the James A. FitzPatrick's (JAF's) current licensing basis, in the Updated Final Safety Analysis Report, to support installation of new reserve station service transformers (RSST) with on-load tap changers (OLTC). The new RSSTs with OLTCs will compensate for the wider range of offsite power voltage variations so that acceptable voltages at the safety-related equipment will be better maintained. The new RSSTs provided with OLTCs would facilitate operations in the automatic mode.

The OLTCs are sub-components of two new RSSTs that will be installed at JAF during the refueling outage scheduled for September 2012.

Date of issuance:September 26, 2012.

Effective date:As of the date of issuance, and shall be implementedwithin 90 days The implementation of the amendment shall include revision of the Updated Final Safety Analysis Report as described in the licensee's application for this amendment.

Amendment No.:302.

Renewed Facility Operating License No. DPR-59:The amendment revised the License and the Updated Final Safety Analysis Report.

Date of initial notice in Federal Register: November 15, 2011 (76 FR 70768).

The supplements dated March 30, June 13, August 1, August 16, and September 14, 2012 provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in theFederal Register.

The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 26, 2012.

No significant hazards consideration comments received:No.

FirstEnergy Nuclear Operating Company, Docket Nos. 50-334 and 50-412, Beaver Valley Power Station (BVPS), Units 1 and 2, Beaver County, Pennsylvania;Docket No. 50-346, Davis-Besse Nuclear Power Station (DBNPS), Unit 1, Ottawa County, Ohio;Docket No. 50-440, Perry Nuclear Power Plant (PNPP), Unit 1, Lake County, Ohio

Date of application for amendments:September 20, 2011, as supplemented by letter dated June 21, 2012.

Brief description of amendments:The proposed amendments would change the licenses of BVPS, Units 1 and 2, DBNPS, and PNPP to reflect the name change of an owner licensee from "FirstEnergy Nuclear Generation Corp." to "FirstEnergy Nuclear Generation, LLC." The proposed amendment is administrative in nature. The proposed amendment will also correct errors regarding the name of FirstEnergy Nuclear Generation Corp in the DBNPS and PNNP Facility Operating Licenses.

Date of issuance:October 2, 2012.

Effective date:At date of issuance.

Amendment Nos.:No. 290 to Facility Operating License No. DPR-66 and No. 177 to Facility Operating License No. NPF-73 for BVPS, Units 1 and 2, respectively, and No. 286 to Facility Operating License No. NPF-3 for DBNPS, and No. 161 to Facility Operating License No. NPF-58 for PNPP.

Facility Operating License Nos. DPR-66, NPF-73, NPF-3, and NPF-58:The amendments revised the Facility Operating Licenses.

Date of initial notice in Federal Register: October 18, 2011 (76 FR 64391).

The supplemental letter dated June 21, 2012, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed finding of no significant hazards consideration determination published in theFederal Register.

The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated October 2, 2012.

No significant hazards consideration comments received:No.

Florida Power and Light Company, et al., Docket Nos. 50-389, St. Lucie Plant, Unit 2,St. Lucie County, Florida.

Date of application for amendment:February 25, 2011, as supplemented by the letters dated November 4 and December 8, 2011, and April 30 and May 4 and 7, 2012.

Brief description of amendment:This amendment raises the maximum fuel enrichment for fresh fuel storage from a maximum of 4.5 weight percent uranium-235 to a maximum lattice averaged value of 4.6 weight percent uranium-235. The Technical Specification changes associated with fuel stored in the spent fuel pool include increasing the maximum initial enrichment from 4.5 weight percent uranium-235 to a maximum planar average initial enrichment of 4.6 weight percent uranium-235, credit for empty storage locations, credit for use of METAMICTMinserts, credit for installation of full-length full-strength, five-fingered control element assemblies, and definition of three special configurations referred to in the nuclear criticality safety analysis as inspection and maintenance configurations.

Date of issuance:September 18, 2012.

Effective date:This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

Amendment No:162.

Renewed Facility Operating License No. NPF-16:Amendment revised the Operating License and the Technical Specifications.

Date of initial notice in Federal Register: September 1, 2011 (76 FR 54503).

The supplemental letters provided additional information that clarified the application and did not expand the scope of the application as originally noticed and published in theFederal Register.

The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 18, 2012.

No significant hazards consideration comments received:No.

Florida Power and Light Company, et al., Docket Nos. 50-389, St. Lucie Plant, Unit 2, St. Lucie County, Florida.

Date of application for amendment:February 25, 2011 as supplemented by letters dated February 25, May 24, July 22, August 18 (three letters), August 25 (three letters), August 29, September 2, September 8 (two letters), September 22, October 5, October 10, October 12 (two letters), October 31, November 2, November 3, November 4, November 7, November 14 (three letters), November 23 (three letters), December 8, December 14, December 20, December 27, December 29, 2011, January 14, 2012 (two letters), January 18 (two letters), January 21 (two letters), February 29, March 6 (two letters), March 8, March 15, March 16, March 17 (two letters), March 25, March 31 (two letters), April 5 (two letters), April 6, April 10, April 19 (seven letters), April 30, May 4, May 7, May 18, and July 23, 2012.

Brief description of amendments:The proposed amendments would increase the licensed core power level for St. Lucie Unit 2 from 2070 megawatts thermal (MWt) to 3020 MWt. This represents a net increase in the core thermal power of approximately 11.85 percent, including a 10-percent power uprate and a 1.7 percent measurement uncertainty recapture, over the current licensed thermal power level and is defined as an extended power uprate. The proposed amendments would change the renewed facility operating license and the technical specifications (TSs) to support operation at the increased core thermal power level, including changes to the maximum licensed reactor core thermal power, reactor core safety limits, and reactor protection system and engineered safety feature actuation system limiting safety system settings. Additional TS changes include reactor coolant system heatup and cooldown limitations, accumulator and refueling water storage tank boron concentrations, main steam safety valve lift settings, emergency diesel generator fuel storage and core operating limits report references. A complete list of the proposed TS changes and the licensee's basis for change can be found in Attachment 1 of the licensee's application (ADAMS Accession No. ML110730116).

Date of issuance:September 24, 2012.

Effective date:This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

Amendment No.:163.

Renewed Facility Operating License No. NPF-16:Amendment revised the Operating License and the Technical Specifications.

Date of initial notice in Federal Register: September 1, 2011 (76 FR 54503).

The supplemental letters provided additional information that clarified the application and did not expand the scope of the application as originally noticed and published in theFederal Register.

The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 24, 2012.

No significant hazards consideration comments received:No.

Nebraska Public Power District, Docket No. 50-298, Cooper Nuclear Station, Nemaha County, Nebraska

Date of amendment request:September 16, 2011, as supplemented by letters dated May 2, May 24, and September 17, 2012.

Brief description of amendment:The amendment revised the Cooper Nuclear Station Technical Specifications (TS) and Operating License to implement a 24-month fuel cycle and adopt TS Task Force (TSTF) Traveler TSTF-493, Revision 4, "Clarify Application of Setpoint Methodology for LSSS [Limiting Safety System Settings] Functions," Option A. Specifically, the amendment revised certain TS Surveillance Requirement frequencies that are specified as "18 months" by changing them to "24 months" in accordance with the guidance provided in NRC Generic Letter 91-04, "Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle."

Date of issuance:September 28, 2012.

Effective date:As of the date of issuance and shall be implemented within 60 days of issuance.

Amendment No.:242.

Renewed Facility Operating License No. DPR-46:Amendment revised the Facility Operating License and Technical Specifications.

Date of initial notice in Federal Register: March 6, 2012 (77 FR 13371). The supplemental letters dated May 2, May 24, and September 17, 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 theFederal Register.

The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 28, 2012.

No significant hazards consideration comments received:No.

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

Date of application for amendments:May 1, 2012, as supplemented by letters dated June 27, 2012, and July 26, 2012.

Brief description of amendments:The amendment revises existing TS 3.3.5.1, on a one-time basis only, by adding a note to TS Table 3.3.5.1-1, Function 1d, Modes 4 and 5. This one-time license amendment enables DAEC to re-coat the internal surface of the Suppression Chamber during Refueling Outage 23.

Date of issuance:September 27, 2012.

Effective date:This license amendment is effective as of the date of issuance and shall be implemented within 30 days from date of issuance.

Amendment No.:283.

Renewed Facility Operating License No. DPR-49:Amendment revised the Renewed Facility Operating License and Technical Specifications.

Date of initial notice in Federal Register: July 10, 2012 (77 FR 40654).

The licensee's June 27, 2012, and July 26, 2012, supplemental letters contained clarifying information, did not change the scope of the original 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 originalFederal Registernotice.

The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 27, 2012.

No significant hazards consideration comments received:Yes.

Tennessee Valley Authority, Docket Nos. 50-327 and 50-328, Sequoyah Nuclear Plant, Units 1 and 2, Hamilton County, Tennessee

Date of application for amendment:June 17, 2011, supplemented by letters dated July 27, 2011, November 14, 2011, March 23, April 26, May 15, May 24, and June 26, 2012 (TS-SQN-2011-07).

Brief description of amendment:The amendments revised the licensing basis and the Technical Specifications (TSs) to permit the use of a more robust AREVA Advanced W17 high thermal performance fuel. This new fuel has been selected to address fuel assembly distortion and its resultant fuel-handling issues. The AREVA Advanced W17 HTP fuel assembly design consists of standard uranium dioxide fuel pellets with gadolinium oxide burnable poison and M5TMcladding. The new fuel design ensures mechanical compatibility with the existing fuel, reactor core, control rods, steam supply system, and fuel-handling system. The transition from the existing fuel (AREVA Mark-BW) to new fuel is planned to occur over two refueling cycles for each unit.

Date of issuance:September 26, 2012.

Effective date:As of the date of issuance and shall be implemented prior to startup from fall 2013 refueling outage (RFO) for Unit 1, and prior to startup from fall 2012 RFO for Unit 2.

Amendment Nos.:331 and 324.

Facility Operating License Nos. DPR-77 and DPR-79:Amendments revised the License and TSs.

Date of initial notice in Federal Register: August 23, 2011 (76 FR 52703). The supplement letters dated July 27, 2011, November 14, 2011, March 23, April 26, May 15, May 24, and June 26, 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.

The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated September 26, 2012.

No significant hazards consideration comments received:No.

For The Nuclear Regulatory Commission.
Dated at Rockville, Maryland, this 5th day of October 2012. Michele G. Evans, Director,Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.