80 FR 48920 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
NUCLEAR REGULATORY COMMISSION Federal Register Volume 80, Issue 157 (August 14, 2015)
Federal Register Volume 80, Issue 157 (August 14, 2015)
| Page Range | 48920-48932 | |
| FR Document | 2015-20138 |
[Federal Register Volume 80, Number 157 (Friday, August 14, 2015)] [Notices] [Pages 48920-48932] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2015-20138] [[Page 48920]] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2015-0194] Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations AGENCY: Nuclear Regulatory Commission. ACTION: Biweekly notice. ----------------------------------------------------------------------- SUMMARY: Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular biweekly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued, and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued from July 23, 2015, to August 5, 2015. The last biweekly notice was published on August 4, 2015. DATES: Comments must be filed by September 17, 2015. A request for a hearing must be filed by October 19, 2015. ADDRESSES: You may submit comments by any of the following methods (unless this document describes a different method for submitting comments on a specific subject):Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0194. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. Mail comments to: Cindy Bladey, Office of Administration, Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. For additional direction on obtaining information and submitting comments, see ``Obtaining Information and Submitting Comments'' in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: Sandra Figueroa, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-1262, email: [email protected]. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC-2015-0194 when contacting the NRC about the availability of information for this action. You may obtain publicly-available information related to this action by any of the following methods: Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0194. NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to [email protected]. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in the SUPPLEMENTARY INFORMATION section. 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-2015-0194, facility name, unit number(s), application date, and subject in your comment submission. 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 at http://www.regulations.gov as 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. II. Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Combined Licenses and Proposed No Significant Hazards Consideration Determination 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 the Code of Federal Regulations (10 CFR), this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. The basis for this proposed determination for each amendment request is shown below. The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination. Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60- day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30- day comment period should circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example in derating or shutdown of the facility. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. Should the Commission make a final No Significant Hazards Consideration Determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently. [[Page 48921]] A. Opportunity To Request a Hearing and Petition for Leave To Intervene 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 ``Agency Rules of Practice and Procedure'' 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 electronically from 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 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 unless the Commission finds an imminent danger to the health or safety of the public, in which case it will issue an appropriate order or rule under 10 CFR part 2. B. Electronic Submissions (E-Filing) 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 [email protected], 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/getting-started.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 [[Page 48922]] should be in Portable Document Format (PDF) in accordance with NRC 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 NRC'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 public Web site at http://www.nrc.gov/site-help/e-submittals.html, by email to [email protected], or by a toll-free call at 1-866-672-7640. The NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., Eastern Time, Monday through Friday, excluding government holidays. Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) First class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to the Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff. Participants filing a document in this manner are responsible for serving the document on all other participants. Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service. A presiding officer, having granted an exemption request from using E-Filing, may require a participant or party to use E-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists. Documents submitted in adjudicatory proceedings will appear in the NRC's electronic hearing docket which is available to the public at http://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the Commission, or the presiding officer. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or home phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. However, in some instances, a request to intervene will require including information on local residence in order to demonstrate a proximity assertion of interest in the proceeding. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submission. Petitions for leave to intervene must be filed no later than 60 days from the date of publication of this notice. Requests for hearing, petitions for leave to intervene, and motions for leave to file new or amended contentions that are filed after the 60-day deadline will not be entertained absent a determination by the presiding officer that the filing demonstrates good cause by satisfying the three factors in 10 CFR 2.309(c)(1)(i)-(iii). For further details with respect to these license amendment applications, see the application for amendment which is available for public inspection in ADAMS and at the NRC's PDR. For additional direction on accessing information related to this document, see the ``Obtaining Information and Submitting Comments'' section of this document. Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287, Oconee Nuclear Station, Units 1, 2, and 3 (ONS), Oconee County, South Carolina Date of amendment request: June 23, 2015. A publicly-available version is in ADAMS under Accession No. ML15183A060. Description of amendment request: The amendment would involve upgrading the ONS, Emergency Action Levels based on NEI 99-01, Revision 6, ``Development of Emergency Action Levels for Non-Passive Reactors.'' Pursuant to 10 CFR part 50, appendix E, section IV.B, Duke Energy requested NRC approval of this proposed change to the ONS Emergency Plan prior to implementation. 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. These changes affect the ONS Emergency Plan and do not alter the requirements of the Operating License or the Technical Specifications. The proposed changes do not modify plant equipment and do not impact failure modes that could lead to an accident. Additionally, the proposed changes do not impact the consequence of an analyzed accident since the changes do not affect equipment related to accident mitigation. Based on this discussion, the proposed amendment does not increase 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. These changes affect the ONS Emergency Plan and do not alter the requirements of the Operating License or the Technical Specifications. They do not modify plant equipment and there is no impact on the capability of the existing equipment to perform their intended functions. No system setpoints are being modified and no changes are being made to the method in which plant operations are conducted. No new failure modes are introduced by the proposed changes. The proposed amendment does not introduce an accident initiator or malfunction that would cause a new or different kind of accident. Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from an accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. These changes affect the ONS Emergency Plan and do not alter the requirements of the Operating License or the Technical Specifications. The proposed changes do not affect the assumptions used in the accident analysis, nor do they affect the operability requirements for equipment important to plant safety. Therefore, the proposed changes will not result in a significant reduction in the margin [[Page 48923]] of safety as defined in the bases for technical specifications covered in this license amendment request. 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 Tryon Street--DEC45A, Charlotte, NC 28202-1802. NRC Branch Chief: Robert J. Pascarelli. Duke Energy Progress, Inc., Docket Nos. 50-325 and 50-324; Brunswick Steam Electric Plant, Unit Nos. 1 and 2, Brunswick County, North Carolina; Docket No. 50-400; Shearon Harris Nuclear Power Plant, Unit 1, Wake County, North Carolina; Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba Nuclear Station, Units 1 and 2, York County, South Carolina; Docket Nos. 50-369 and 50-370, McGuire Nuclear Station, Units 1 and 2, Mecklenburg County, North Carolina; and Docket Nos. 50- 269, 50-270, and 50-287, Oconee Nuclear Station, Units 1, 2, and 3, Oconee County, South Carolina Date of amendment request: June 24, 2015. A publicly-available version is in ADAMS under Accession No. ML15175A438. Description of amendment request: The proposed change revises or adds Surveillance Requirements to verify that the system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowances which permit performance of the verification. The changes are being made to address the concerns discussed in NRC Generic Letter 2008-01, ``Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems'' (ADAMS Accession No. ML072910759). The proposed amendment references TSTF-523, Revision 2, ``Generic Letter 2008-01, Managing Gas Accumulation'' (79 FR 2700; January 15, 2014). 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 change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change revises or adds Surveillance Requirement(s) (SRs) that require verification that the Emergency Core Cooling System (ECCS), the Decay Heat Removal (DHR)/Residual Heat Removal (RHR) System, the Containment Spray/Reactor Building Spray System, and the Reactor Core Isolation Cooling (RCIC) System are not rendered inoperable due to accumulated gas and to provide allowances which permit performance of the revised verification. Gas accumulation in the subject systems is not an initiator of any accident previously evaluated. As a result, the probability of any accident previously evaluated is not significantly increased. The proposed SRs ensure that the subject systems continue to be capable to perform their assumed safety function and are not rendered inoperable due to gas accumulation. Thus, the consequences of any accident previously evaluated are not significantly increased. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change revises or adds SRs that require verification that the ECCS, the DHR/RHR System, the Containment Spray/Reactor Building Spray System, and the RCIC System are not rendered inoperable due to accumulated gas and to provide allowances which permit performance of the revised verification. The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. In addition, the proposed change does not impose any new or different requirements that could initiate an accident. The proposed change does not alter assumptions made in the safety analysis and is consistent with the safety analysis assumptions. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed change revises or adds SRs that require verification that the ECCS, the DHR/RHR System, the Containment Spray/Reactor Building Spray System, and the RCIC System are not rendered inoperable due to accumulated gas and to provide allowances which permit performance of the revised verification. The proposed change adds new requirements to manage gas accumulation in order to ensure the subject systems are capable of performing their assumed safety functions. The proposed SRs are more comprehensive than the current SRs and will ensure that the assumptions of the safety analysis are protected. The proposed change does not adversely affect any current plant safety margins or the reliability of the equipment assumed in the safety analysis. Therefore, there are no changes being made to any safety analysis assumptions, safety limits or limiting safety system settings that would adversely affect plant safety as a result of the proposed change. 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. Attorney for licensee: Lara S. Nichols, Deputy General Counsel, Duke Energy Corporation, 550 South Tryon Street--DEC45A, Charlotte, NC 28202-1802. NRC Branch Chiefs: Robert J. Pascarelli and Shana Helton. Luminant Generation Company LLC, Docket Nos. 50-445 and 50-446, Comanche Peak Nuclear Power Plant, Units 1 and 2 (CPNPP), Somervell County, Texas Date of amendment request: June 30, 2015. A publicly-available version is in ADAMS under Accession No. ML15191A175. Description of amendment request: The amendment involves upgrading selected CPNPP Emergency Action Levels (EALs) based on Nuclear Energy Institute (NEI) 99-01, Revision 6, ``Development of Emergency Action Levels for Non-Passive Reactors,'' dated November 2012 (ADAMS Accession No. ML12326A805), using the guidance of NRC Regulatory Issue Summary 2003-18, Supplement 2, ``Use of NEI 99-01, Methodology for Development of EALs,'' dated December 12, 2005 (ADAMS Accession No. ML051450482). 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. These changes affect the CPNPP Emergency Plan and do not alter any of the requirements of the Operating License or the Technical Specifications. The proposed changes do not modify any plant equipment and do not impact any failure modes that could lead to an accident. Additionally, the proposed changes do not impact the consequence of any analyzed accident since the changes do not affect any equipment related to accident mitigation. Based on this discussion, the proposed amendment does not increase the probability or consequences of an accident previously evaluated. [[Page 48924]] 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. These changes affect the CPNPP Emergency Plan and do not alter any of the requirements of the Operating License or the Technical Specifications. They do not modify any plant equipment and there is no impact on the capability of the existing equipment to perform their intended functions. No system setpoints are being modified and no changes are being made to the method in which plant operations are conducted. No new failure modes are introduced by the proposed changes. The proposed amendment does not introduce accident initiators or malfunctions that would cause a new or different kind of accident. Therefore, the proposed amendment 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. These changes affect the CPNPP Emergency Plan and do not alter any of the requirements of the Operating License or the Technical Specifications. The proposed changes do not affect any of the assumptions used in the accident analysis, nor do they affect any operability requirements for equipment important to plant safety. Therefore, the proposed changes will not result in a significant reduction in the margin of safety as defined in the bases for technical specifications covered in this license amendment request. 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: Timothy P. Matthews, Esq., Morgan, Lewis and Bockius, 1111 Pennsylvania Avenue NW., Washington, DC 20004. NRC Branch Chief: Michael T. Markley. South Carolina Electric & Gas Company, South Carolina Public Service Authority, Docket No. 50-395, Virgil C. Summer Nuclear Station, Unit No. 1, Fairfield County, South Carolina Date of amendment request: July 22, 2015. A publicly-available version is in ADAMS Accession No. ML15205A291. Description of amendment request: The licensee proposes to revise Technical Specification Section 6.0, ``Administrative Controls'' by changing the ``Shift Supervisor'' title to ``Shift Manager.'' 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 change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed changes to the Technical Specifications (TS) regarding Shift Supervisor to Shift Manager are administrative changes. It has no impact on accident initiators or plant equipment and thus does not affect the probability or consequences of an accident. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change does not involve a change to the physical plant or operations. This is an administrative title change that does not contribute to accident initiation. Therefore, it does not produce a new accident scenario or produce a new type of equipment malfunction. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. Since the change is administrative and changes no previously evaluated accidents or creates no possibility for any new unevaluated accidents to occur, there is no reduction in the margin of safety. This change also does not affect plant equipment or operation and therefore does not affect safety limits or limiting safety systems settings. 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: J. Hagood Hamilton, Jr., South Carolina Electric & Gas Company, Post Office Box 764, Columbia, South Carolina 29218. NRC Branch Chief: Robert J. Pascarelli. STP Nuclear Operating Company, Docket Nos. 50-498 and 50-499, South Texas Project (STP), Units 1 and 2, Matagorda County, Texas Date of amendment request: April 29, 2015, as supplemented by letter dated June 29, 2015. Publicly-available versions are in ADAMS under Accession Nos. ML15128A352 and ML15198A147, respectively. Description of amendment request: The amendment would revise the Integrated Leak Rate Test performance interval from 10 years to 15 years in Technical Specification (TS) 3.8.3.j, ``Containment Leakage Rate Testing Program,'' in accordance with Nuclear Energy Institute 94- 01, Revision 2A, ``Industry Guideline for Implementing Performance- Based Option of 10 CFR part 50, appendix J,'' dated October 2008 (ADAMS Accession No. ML100620847). 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 amendment to the TS involves the extension of the STP, Units 1 and 2 Type A containment test interval to 15 years. The current Type A test interval of 120 months (10 years) would be extended on a permanent basis to no longer than 15 years from the last Type A test. Extensions of up to nine months (total maximum interval of 189 months for Type A tests) are permissible only for non-routine emergent conditions. The proposed extension does not involve either a physical change to the plant or a change in the manner in which the plant is operated or controlled. The containment is designed to provide an essentially leak tight barrier against the uncontrolled release of radioactivity to the environment for postulated accidents. As such, the containment and the testing requirements invoked to periodically demonstrate the integrity of the containment exist to ensure the plant's ability to mitigate the consequences of an accident, and do not involve the prevention or identification of any precursors of an accident. The change in dose risk for changing the Type A test frequency from once-per-ten years to once-per-fifteen-years, measured as an increase to the total integrated dose risk for all internal events accident sequences for STP, of 0.123 person [roentgen equivalent man per year (rem/yr)] for Unit 1 and Unit 2 using the [Electric Power Research Institute (EPRI)] guidance with the base case corrosion included. Therefore, this proposed extension does not involve a significant increase in the probability of an accident previously evaluated. As documented in NUREG-1493, [``Performance-Based Containment Leak-Test Program,'' dated January 1995] Type B and C tests have identified a very large percentage of containment leakage paths, and the percentage of containment leakage paths that are detected only by Type A testing is very small. The STP, Units 1 and 2 Type A test history supports this conclusion. The integrity of the containment is subject to two types of failure mechanisms that can be categorized as: (1) Activity based, and; (2) time based. Activity based failure mechanisms are defined as degradation due to system and/or component modifications or maintenance. Local leak rate test requirements and administrative controls such as configuration management and [[Page 48925]] procedural requirements for system restoration ensure that containment integrity is not degraded by plant modifications or maintenance activities. The design and construction requirements of the containment combined with the containment inspections performed in accordance with ASME Section XI, the Maintenance Rule, and TS requirements serve to provide a high degree of assurance that the containment would not degrade in a manner that is detectable only by a Type A test. Based on the above, the proposed extensions do not significantly increase the consequences of an accident previously evaluated. The proposed amendment also deletes exceptions previously granted to allow one-time extensions of the ILRT test frequency for both Units 1 and 2. These exceptions were for activities that have already taken place so their deletion is solely an administrative action that has no effect on any component and no impact on how the units are operated. Therefore, the proposed change does not result in a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed amendment to the TS involves the extension of the STP, Unit 1 and 2 Type A containment test interval to 15 years. The containment and the testing requirements to periodically demonstrate the integrity of the containment exist to ensure the plant's ability to mitigate the consequences of an accident do not involve any accident precursors or initiators. The proposed change does not involve a physical change to the plant (i.e., no new or different type of equipment will be installed) or a change to the manner in which the plant is operated or controlled. The proposed amendment also deletes exceptions previously granted to allow one-time extensions of the ILRT test frequency for both Units 1 and 2. These exceptions were for activities that would have already taken place by the time this amendment is approved; therefore, their deletion is solely an administrative action that does not result in any change in how the units are operated. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed amendment to TS 6.8.3.j involves the extension of the STP, Units 1 and 2 Type A containment test interval to 15 years. This amendment does not alter the manner in which safety limits, limiting safety system set points, or limiting conditions for operation are determined. The specific requirements and conditions of the TS Containment Leak Rate Testing Program exist to ensure that the degree of containment structural integrity and leak-tightness that is considered in the plant safety analysis is maintained. The overall containment leak rate limit specified by TS is maintained. The proposed change involves only the extension of the interval between Type A containment leak rate tests for STP, Units 1 and 2. The proposed surveillance interval extension is bounded by the 15- year ILRT Interval currently authorized within NEI 94-01, Revision 2-A. Industry experience supports the conclusion that Type B and C testing detects a large percentage of containment leakage paths and that the percentage of containment leakage paths that are detected only by Type A testing is small. The containment inspections performed in accordance with [American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,] Section Xl, TS and the Maintenance Rule serve to provide a high degree of assurance that the containment would not degrade in a manner that is detectable only by Type A testing. The combination of these factors ensures that the margin of safety in the plant safety analysis is maintained. The design, operation, testing methods and acceptance criteria for Type A, B, and C containment leakage tests specified in applicable codes and standards would continue to be met, with the acceptance of this proposed change, since these are not affected by changes to the Type A and Type C test intervals. The proposed amendment also deletes exceptions previously granted to allow one-time extensions of the ILRT test frequency for both Units 1 and 2. These exceptions were for activities that would have already taken place by the time this amendment is approved; therefore, their deletion is solely an administrative action and does not change how the units are operated and maintained. Thus, there is no reduction in any margin of safety. 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 standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the request for amendments involves no significant hazards consideration. NRC Branch Chief: Michael T. Markley. III. Previously Published Notices of Consideration of Issuance of Amendments to Facility Operating Licenses and Combined Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The following notices were previously published as separate individual notices. The notice content was the same as above. They were published as individual notices either because time did not allow the Commission to wait for this biweekly notice or because the action involved exigent circumstances. They are repeated here because the biweekly notice lists all amendments issued or proposed to be issued involving no significant hazards consideration. For details, see the individual notice in the Federal Register on the day and page cited. This notice does not extend the notice period of the original notice. Susquehanna Nuclear, LLC, Docket Nos. 50-387 and 50-388, Susquehanna Steam Electric Station (SSES), Units 1 and 2, Luzerne County, Pennsylvania Date of amendment request: August 11, 2014, as supplemented by letters dated April 6, 2015, and July 16, 2015. Publicly-available versions are in ADAMS under Accession Nos. ML14223A780, ML15097A386, and ML15197A256, respectively. Brief description of amendment request: The amendment proposes changes to SSES, Units 1 and 2, Technical Specification 3.4.10, ``RCS [Reactor Coolant System] Pressure and Temperature (P/T) Limits,'' which includes revisions to the P/T Limits curves. Date of publication of individual notice in Federal Register: July 30, 2015 (80 FR 45559). Expiration date of individual notice: August 31, 2015 (public comments); September 28, 2015 (hearing requests). IV. 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 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 [[Page 48926]] 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 can be accessed as described in the ``Obtaining Information and Submitting Comments'' section of this document. Dominion Nuclear Connecticut, Inc., Docket No. 50-336, Millstone Power Station, Unit No. 2 (MPS2), New London County, Connecticut Date of amendment request: June 30, 2014, as supplemented by letter dated January 29, 2015. Brief description of amendment: The amendment revised the Technical Specifications (TSs) by adopting approved Technical Specification Task Force (TSTF) traveler TSTF-426, Revision 5, ``Revise or Add Actions to Preclude Entry into LCO 3.0.3--RITSTF Initiatives 6b and 6c,'' and providing a short completion time to restore an inoperable system for conditions under which the previous TS required a plant shutdown. The amendment also reformats each proposed MPS2 custom TS ACTION format to a two-column tabular format. Date of issuance: July 29, 2015. Effective date: As of the date of issuance and shall be implemented within 120 days from the date of issuance. Amendment No.: 321. A publicly-available version is in ADAMS under Accession No. ML15187A326; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-65: Amendment revised the Renewed Operating License and TSs. Date of initial notice in Federal Register: December 23, 2014 (79 FR 77044). The supplemental letter dated January 29, 2015, 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 July 29, 2015. No significant hazards consideration comments received: No. Dominion Nuclear Connecticut, Inc., Docket No. 50-423, Millstone Power Station, Unit No. 3, New London County, Connecticut Date of amendment request: November 6, 2013, as supplemented on November 14, 2014, and February 9, 2015. Brief description of amendment: The amendment revised Technical Specification (TS) 3/4.5.4, ``Refueling Water Storage Tank,'' and TS 3/ 4.6.2.1, ``Depressurization and Cooling Systems, Containment Quench Spray System,'' to provide additional operational margin for control of the Refueling Water Storage Tank. The amendment also made a clarifying editorial change to the TS 3/4.5.4 action statement. Date of issuance: July 27, 2015. Effective date: As of the date of issuance and shall be implemented within 12 days from the date of issuance. Amendment No.: 262. A publicly-available version is in ADAMS under Accession No. ML15187A011; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. NPF-49: Amendment revised the Renewed Operating License and TSs. Date of initial notice in Federal Register: November 25, 2014 (79 FR 70212). The supplemental letters dated November 14, 2014, and February 9, 2015, 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 July 27, 2015. No significant hazards consideration comments received: No. Dominion Nuclear Connecticut, Inc., Docket No. 50-423, Millstone Power Station, Unit, No. 3, New London County, Connecticut Date of amendment request: August 19, 2014, as supplemented on January 26, 2015. Brief description of amendment: The amendment revised Technical Specification (TS) 3/4.7.1.2, ``Auxiliary Feedwater System,'' Surveillance Requirement 4.7.1.2.1.b. by replacing the surveillance frequency and acceptance criteria for the Auxiliary Feedwater (AFW) pumps with a reference to the Inservice Testing Program (TS 4.0.5) for the specific pump testing acceptance criteria and the surveillance frequency. The amendment also added information on suitable plant conditions for performance of the steam turbine driven AFW pump surveillance. Date of issuance: July 28, 2015. Effective date: As of the date of issuance and shall be implemented within 120 days from the date of issuance. Amendment No.: 263. A publicly-available version is in ADAMS under Accession No. ML15187A186; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. NPF-49: Amendment revised the Renewed Operating License and TSs. Date of initial notice in Federal Register: May 26, 2015 (80 FR 30099). The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 28, 2015. No significant hazards consideration comments received: No. Duke Energy Progress, Inc., Docket Nos. 50-325, 50-324, 50-400, Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick), and Shearon Harris Nuclear Power Plant, Unit 1 (Harris), Brunswick, Wake, and Chatham Counties, North Carolina Date of amendment request: December 22, 2014, as supplemented by letters dated March 4, 2015; June 1, 2015; June 10, 2015; June 24, 2015; and July 29, 2015. Brief description of amendments: By orders dated July 6, 2015, as published in the Federal Register on July 14, 2015 (80 FR 41095 and 80 FR 41097), the NRC approved direct license transfers for Brunswick and Harris. These amendments reflect the direct transfer of the licenses of the percent of ownership from North Carolina Eastern Municipal Power Agency to Duke Energy Progress, Inc., keeping Duke Energy as the sole owner and licensee. Date of issuance: July 31, 2015. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment Nos.: 267 for Brunswick, Unit 1, 295 for Unit 2, and 147 for Harris, Unit 1. Publicly-available versions of the Brunswick and Harris amendments are in ADAMS under Accession No. ML15161A121, and the orders are in ADAMS under Accession Nos. ML15159A602 and ML15159A617, respectively. Documents related to these amendments are listed in the safety evaluation (SE) enclosed with the order dated July 6, 2015. Subsequent to the issuance of the orders, the licensee submitted a letter dated July 29, 2015 [[Page 48927]] (ADAMS Accession No. ML15210A049). The letter provided additional notifications of regulatory approvals and the closing transaction date, as required by the order. Renewed Facility Operating License Nos. DPR-71, DPR-62, and NPF-63: The amendments revised the Renewed Facility Operating Licenses. Date of initial notices in Federal Register: April 21, 2015 (80 FR 22224 and 22228). The supplemental letters dated June 1, 2015; June 10, 2015; June 24, 2015; and July 29, 2015, 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 an SE dated July 6, 2015 (ADAMS No. ML15159A632). No significant hazards consideration comments received: No. Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287, Oconee Nuclear Station, Units 1, 2, and 3, Oconee County, South Carolina Date of amendment request: September 18, 2014. Brief description of amendments: The amendments revise the Technical Specifications to define a new time limit for restoring inoperable Reactor Coolant System (RCS) leakage detection instrumentation to operable status and establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable in accordance with Technical Specifications Task Force Traveler 513, Revision 3, ``Revise Pressurized-Water Reactor Operability Requirements and Actions for Reactor Coolant System Leakage Instrumentation.'' Date of issuance: July 27, 2015. Effective date: As of the date of issuance and shall be implemented within 120 days. Amendment Nos.: 394 for Unit 1, 396 for Unit 2, and 395 for Unit 3. A publicly-available version is in ADAMS under Accession No. ML15170A055; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Facility Operating License Nos. DPR-38, DPR-47, and DPR-55: The amendments revised the Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: May 26, 2015 (80 FR 30100). The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated July 27, 2015. 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: July 9, 2014, as supplemented by letters dated February 24, June 3, and July 16, 2015. Brief description of amendment: The amendment revised the RBS Technical Specifications (TSs) Surveillance Requirements (SRs) related to the steady state voltage, frequency and test load limits for the emergency diesel generators Diesel Generator (DG) 1A, DG 1B and DG 1C. Specifically, the amendment revised the SR Acceptance Criteria Tolerance Band (ACTB) for TS SRs 3.8.1.2, 3.8.1.3, 3.8.1.7, 3.8.1.10, 3.8.1.11, 3.8.1.12, 3.8.1.14, 3.8.1.15, 3.8.1.19 and 3.8.1.20. The changes will lower the upper bound of the frequency SR ACTB, lower the upper bound of the voltage SR ACTB for DG 1A and DG 1B (existing DG 1C voltage SR ACTB is retained), and raise the lower bound of the test load SR ACTB. Date of issuance: July 30, 2015. Effective date: As of the date of issuance and shall be implemented 60 days from the date of issuance. Amendment No.: 187. A publicly-available version is in ADAMS under Accession No. ML15187A127; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Operating License No. NPF-47: The amendment revised the Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: November 12, 2014 (79 FR 67201). The supplements dated February 24, June 3, and July 16, 2015, 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 July 30, 2015. No significant hazards consideration comments received: No. Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric Station, Unit 3, St. Charles Parish, Louisiana Date of amendment request: October 1, 2014, as supplemented by letter dated February 2, 2015. Brief description of amendment: The amendment relocated Technical Specification (TS) 3/4.9.6, ``Refueling Machine,'' and TS 3/4.9.7, ``Crane Travel--Fuel Handling Building,'' to the Technical Requirements Manual. Date of issuance: July 29, 2015. Effective date: As of the date of issuance and shall be implemented 60 days from the date of issuance. Amendment No.: 243. A publicly-available version is in ADAMS under Accession No. ML15174A227; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Operating License No. NPF-38: The amendment revised the Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: March 3, 2015 (80 FR 11475). The supplemental letter dated February 2, 2015, 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 the Federal Register. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated July 29, 2015. No significant hazards consideration comments received: No. [[Page 48928]] Exelon Generation Company, LLC, Docket Nos. STN 50-456, STN 50-457 and 72-73, Braidwood Station, Units 1 and 2, Will County, Illinois Exelon Generation Company, LLC, Docket Nos. STN 50-454, STN 50-455 and 72-68, Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power Station, Unit No. 1, DeWitt County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-10, 50-237, 50-249 and 72-37, Dresden Nuclear Power Station, Units 1, 2 and 3, Grundy County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-373, 50-374 and 72-70, LaSalle County Station, Units 1 and 2, LaSalle County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-352, 50-353 and 72-65, Limerick Generating Station, Unit 1 and 2, Montgomery County, Pennsylvania Exelon Generation Company, LLC, et al., Docket No. 50-219 and 72-15, Oyster Creek Nuclear Generating Station, Ocean County, New Jersey Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50- 171, 50-277, 50-278 and 72-29, Peach Bottom Atomic Power Station, Units 1, 2 and 3, York and Lancaster Counties, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-254, 50-265 and 70-53, Quad Cities Nuclear Power Station, Units 1 and 2, Rock Island County, Illinois Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island Nuclear Station, Unit 1, Dauphin County, Pennsylvania Exelon Generation Company, LLC, Docket No. 50-320, Three Mile Island Nuclear Station, Unit 2, Dauphin County, Pennsylvania Date of amendment request: May 30, 2014, as supplemented by letters dated March 2 and June 5, 2015. Brief description of amendments: The amendments revised the Emergency Plans for the affected facilities to adopt the Nuclear Energy Institute's (NEl's) revised Emergency Action Level (EAL) schemes described in NEI 99-01, Revision 6, ``Development of Emergency Action Levels for Non-Passive Reactors.'' Date of issuance: July 28, 2015. Effective date: As of the date of issuance and shall be implemented on or before April 29, 2016. Amendment Nos.: 184, 184, 190, 190, 205, 45, 245, 238, 215, 201, 217, 179, 287, 13, 300, 303, 258, 253, and 287. A publicly-available version is in ADAMS under Accession No. ML15141A058; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Facility Operating License Nos. NPF-72, NPF-77, NPF-37, NPF-66, NPF-62, DPR-2, DPR-19, DPR-25, NPF-11, NPF-18, NPF-39, NPF-85, DPR-16, DPR-12, DPR-44, DPR-56, DPR-29, DPR-30, and DPR-50: The amendments revised the Emergency Plans. Date of initial notice in Federal Register: September 16, 2014 (79 FR 55511). The supplemental letters dated March 2 and June 5, 2015, 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 July 28, 2015. No significant hazards consideration comments received: No from Pennsylvania and New Jersey, and Yes from the state of Illinois. The Safety Evaluation dated July 28, 2015, provides the discussion of the comments received from the State of Illinois. Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, Braidwood Station, Units 1 and 2, Will County, Illinois Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-455, Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power Station, Unit No. 1, DeWitt County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden Nuclear Power Station, Units 2 and 3, Grundy County, Illinois Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle County Station, Units 1 and 2, LaSalle County, Illinois Exelon Generation Company, LLC, Docket No. 50-352 and No. 50-353, Limerick Generating Station, Unit 1 and 2, Montgomery County, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine Mile Point Nuclear Station, Units 1 and 2, Oswego County, New York Exelon Generation Company, LLC, et al., Docket No. 50-219, Oyster Creek Nuclear Generating Station, Ocean County, New Jersey Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50- 277 and 50-278, Peach Bottom Atomic Power Station, Units 2 and 3,York and Lancaster Counties, Pennsylvania Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad Cities Nuclear Power Station, Units 1 and 2, Rock Island County, Illinois Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear Power Plant, Wayne County, New York Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island Nuclear Station, Unit 1, Dauphin County, Pennsylvania Date of amendment request: August 29, 2014. Brief description of amendments: The amendments approved the extension of the completion date for Milestone 8 of the Cyber Security Plan implementation schedules. Date of issuance: July 30, 2015. Effective date: As of the date of issuance and shall be implemented within 60 days from the date of issuance. [[Page 48929]] Amendment Nos.: 185, 185, 191, 191, 312, 290, 206, 246, 239, 216, 202, 218, 180, 219, 149, 288, 301, 304, 259, 254, 117, and 288. A publicly-available version is in ADAMS under Accession No. ML15153A282; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Facility Operating License Nos. NPF-72, NPF-77, NPF-37, NPF-66, DPR-53, DPR-69, NPF- 62, DPR-19, DPR-25, NPF-11, NPF-18, NPF-39, NPF- 85, DPR-63, NPF-69, DPR-16, DPR-44, DPR-56, DPR-29, DPR-30, DPR-18, DPR-50: The amendments revised the Licenses. Date of initial notice in Federal Register: May 5, 2015 (80 FR 25719). The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated July 30, 2015. No significant hazards consideration comments received: No. Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland Date of amendment request: January 13, 2014, as supplemented by letters dated November 3, 2014, March 3, 2015, and March 27, 2015. Brief description of amendments: These amendments revise the Technical Specifications (TSs) to add a new TS 3.7.18, ``Atmospheric Dump Valves (ADVs).'' The addition of these TSs addresses a degraded or non-conforming condition that was caused by not having TSs for the ADVs. Date of issuance: July 23, 2015. Effective date: As of the date of issuance and shall be implemented within 60 days of issuance. Amendment Nos.: 311 and 289. A publicly-available version is in ADAMS under Accession No. ML15133A144; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR-53 and DPR-69: Amendments revised the Renewed Facility Operating License and TSs. Date of initial notice in Federal Register: July 22, 2014 (79 FR 42548). The supplemental letters dated November 3, 2014, March 3, 2015, and March 27, 2015, 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 July 23, 2015. No significant hazards consideration comments received: No. Exelon Generation Company, LLC, Docket No. 50-317, Calvert Cliffs Nuclear Power Plant, Unit No. 1 (CCNPP1), Calvert County, Maryland Exelon Generation Company, LLC, Docket No. 50-318, Calvert Cliffs Nuclear Power Plant, Unit No. 2 (CCNPP2), Calvert County, Maryland Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear Power Plant (Ginna), Wayne County, New York Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point Nuclear Station, Unit No. 2 (NMP2), Oswego County, New York Date of amendment request: July 10, 2014, as supplemented by letter dated April 30, 2015. Brief description of amendment: The amendments revised and added several Technical Specification (TS) surveillance requirements to address concerns discussed in Generic Letter (GL) 2008-01, ``Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.'' These changes are consistent with TS Task Force Traveler (TSTF) 523, Revision 2, GL 2008-01, Managing Gas Accumulation. Date of issuance: July 30, 2015. Effective date: As of the date of issuance and shall be implemented within 120 days of issuance. Amendment No.: CCNPP1-313; CCNPP2-291; Ginna-118; NMP2-150. A publicly-available version of the amendments are in ADAMS under Accession No. ML15161A380; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Facility Operating License Nos. DPR-53 (CCNPP1), DPR-69 (CCNPP2), DPR-18 (Ginna), and NPF-69 (NMP2): The amendments revised the Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: May 12, 2015, (80 FR 27197). The supplemental letter dated April 30, 2015, 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 July 30, 2015. No significant hazards consideration comments received: No. Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50- 277 and 50-278, Peach Bottom Atomic Power Station, Units 2 and 3, York and Lancaster Counties, Pennsylvania Date of amendment request: September 3, 2014, as supplemented by letter dated February 9, 2015. Brief description of amendments: The amendments revised the Technical Specifications to eliminate the main steam line (MSL) radiation monitor from initiating: (1) A reactor protection system automatic reactor scram; and (2) a primary containment isolation system isolation, including automatic closure of the MSL isolation valves, MSL drain valves, MSL sample line valves, residual heat removal system sample line valves, and reactor recirculation loop sample line valves. Date of issuance: July 28, 2015. Effective date: As of the date of issuance, to be implemented prior to startup from the fall 2016 refueling outage for Unit 2, and prior to startup from the fall 2015 refueling outage for Unit 3. Amendments Nos.: 299 and 302. A publicly-available version is in ADAMS under Accession No. ML15167A456; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR-44 and DPR-56: The amendments revised the Facility Operating Licenses and the TSs. Date of initial notice in Federal Register: November 12, 2014 (79 FR 67201). The supplemental letter dated February 9, 2015, 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 July 28, 2015. No significant hazards consideration comments received: No. Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island Nuclear Station, Unit No. 1, (TMI-1) Dauphin County, Pennsylvania Date of application for amendments: October 30, 2014, as supplemented by letter dated June 10, 2015. [[Page 48930]] Brief description of amendment: The amendment revised the TMI-1 Technical Specification Table 3.1.6.1, ``Pressure Isolation Check Valves Between the Primary Coolant System & LPIS [Low Pressure Injection System],'' maximum allowable leakage limits. Date of issuance: July 28, 2015. Effective date: As of the date of issuance and shall be implemented within 30 days. Amendment Nos.: 286. A publicly-available version is in ADAMS under Accession No. ML15090A584; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-50: The amendment revised the Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: December 9, 2014 (79 FR 73110). The supplemental letter dated June 10, 2015, 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 July 28, 2015. No significant hazards consideration comments received: No. Florida Power & Light Company, Docket Nos. 50-250 and 50-251, Turkey Point Nuclear Generating Unit Nos. 3 and 4, Miami-Dade County, Florida Date of application for amendments: July 8, 2014, as supplemented by letter dated July 15, 2015. Brief description of amendments: The amendments revised the Technical Specifications (TSs) by modifying or adding surveillance requirements to verify that system locations susceptible to gas accumulation are sufficiently filled with water and to provide allowances that permit performance of the verification. The changes address NRC Generic Letter 2008-01, ``Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems'' (ADAMS Accession No. ML072910759), as described in Revision 2 of Technical Specification Task Force-523, ``Generic Letter 2008-01, Managing Gas Accumulation'' (ADAMS Accession No. ML13053A075). Date of issuance: July 27, 2015. Effective date: As of the date of issuance and shall be implemented within 120 days of issuance. Amendment Nos.: 264 and 259. The amendments are in ADAMS under Accession No. ML15181A179; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR-31 and DPR-41: Amendments revised the TSs. Date of initial notice in Federal Register: October 14, 2014 (79 FR 61661). The licensee's supplemental letter dated July 15, 2015, 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 July 27, 2015. No significant hazards consideration comments received: No. NextEra Energy, Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point Beach Nuclear Plant Units 1 and 2, Town of Two Creeks, Manitowoc County, Wisconsin Date of amendment request: July 3, 2014, as supplemented by letters dated December 8, 2014; March 19, 2015; and May 28, 2015. Brief description of amendments: The amendments revised the Technical Specifications (TSs) for Units 1 and 2 to relocate surveillance frequencies to licensee control as per Technical Specifications Task Force Traveler-425, Revision 3. Date of issuance: July 28, 2015. Effective date: As of the date of issuance and shall be implemented within 90 days of issuance. Amendment Nos.: 253 and 257. Publicly-available versions are in ADAMS under Accession No. ML15195A201; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR-24 and DPR-27: Amendments revised the Facility Operating Licenses and TSs. Date of initial notice in Federal Register: November 12, 2014 (79 FR 67203). The supplemental letters dated December 8, 2014; March 19, 2015; and May 28, 2015, 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 July 28, 2015. No significant hazards consideration comments received: No. PSEG Nuclear LLC, Docket Nos. 50-272 and 50-311, Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, Salem County, New Jersey Date amendment request: July 28, 2014, as supplemented by letter dated January 15, 2015. Brief description of amendments: The amendments revised the technical specification (TS) requirements regarding steam generator tube inspections and reporting as described in Technical Specifications Task Force (TSTF) Change Traveler TSTF-510, Revision 2, ``Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.'' In addition, the amendments revise the Salem, Unit No. 2 TSs 6.8.4.i, ``Steam Generator (SG) Program,'' and TS 6.9.1.10, ``Steam Generator Tube Inspection Report,'' to remove unnecessary information related to the original Salem, Unit No. 2 Westinghouse steam generators. Date of issuance: July 30, 2015. Effective date: As of the date of issuance and shall be implemented within 60 days. Amendment Nos.: 309 and 291. A publicly-available version is in ADAMS under Accession No. ML15153A230; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR-70 and DPR-75: The amendments revised the facility operating license and TSs. Date of initial notice in Federal Register: October 28, 2014 (79 FR 64227). The supplemental letter dated January 15, 2015, 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 July 30, 2015. No significant hazards consideration comments received: No. South Carolina Electric & Gas Company, Docket Nos. 52-027 and 52-028, Virgil C. Summer Nuclear Station, Units 2 and 3, Fairfield County, South Carolina Date of amendment request: September 11, 2014, and supplemented [[Page 48931]] by letters dated October 15, 2014 and December 18, 2014. Description of amendment: The amendment revises the Updated Final Safety Analysis Report by clarifying human diversity during the lifecycle development design process for the Component Interface Module and Diverse Actuation System. Date of issuance: July 17, 2015. Effective date: As of the date of issuance and shall be implemented within 90 days of issuance. Amendment No.: 28. A publicly-available version is in ADAMS under Accession No. ML15176A703; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Combined Licenses No. NPF-93 and NPF-94: Amendment revised the Facility Combined Licenses. Date of initial notice in Federal Register: December 9, 2014 (79 FR 73111). The supplemental letters dated October 15, 2014 and December 18, 2014, 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 the Safety Evaluation dated July 17, 2015. No significant hazards consideration comments received: No. South Carolina Electric and Gas Company, Docket Nos. 52-027 and 52-028, Virgil C. Summer Nuclear Station, Units 2 and 3 (VCSNS), Fairfield County, South Carolina Date of amendment request: January 27, 2015. Brief description of amendment: The amendments are to Combined License Nos. NPF-93 and NPF-94 for VCSNS Units 2 and 3. The amendments revise the VCSNS Units 2 and 3 Updated Final Safety Analysis Report (UFSAR) to clarify a human factors engineering operational sequence analysis related to the AP1000 Automatic Depressurization System and delete document WCAP-15847, ``AP1000 Quality Assurance Procedures Supporting NRC Review of AP1000 DCD Sections 18.2 and 18.8,'' that is incorporated by reference into the UFSAR. Both of the amendments constitute changes to information identified as Tier 2* information as defined in 10 CFR part 52, appendix D, section II.F. Date of issuance: June 2, 2015. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment No.: 26. A publicly-available version is in ADAMS under Accession No. ML15131A445; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Combined Licenses No. NPF-93 and NPF-94: Amendment revised the Facility Combined Licenses. Date of initial notice in Federal Register: March 17, 2015 (80 FR 13912). The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated June 2, 2015. No significant hazards consideration comments received: No. Southern Nuclear Operating Company, Inc., Docket Nos. 50-348 and 50- 364, Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, Houston County, Alabama Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50- 425, Vogtle Electric Generating Plant (VEGP), Units 1 and 2, Burke County, Georgia Southern Nuclear Operating Company, Inc., Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, City of Dalton, Georgia, Docket Nos. 50-321 and 50-366, Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2, Appling County, Georgia Date of application for amendment: December 30, 2014. Brief description of amendments: The amendments revise the date of the full implementation of the Cyber Security Plans. Date of issuance: August 3, 2015. Effective date: As of its date of issuance and shall be implemented within 30 days from the date of issuance. Amendment Nos.: Farley Unit 1-199, Farley Unit 2-195, VEGP Unit 1- 175, VEGP Unit 2-157, Hatch Unit 1-274, and Hatch Unit 2-219. A publicly-available version is in ADAMS under Accession No. ML15180A334, documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Facility Operating License Nos. NPF-2, NPF-8, NPF-68, NPF-81, DPR- 57, NPF-5: The amendments revised the Renewed Facility Operating Licenses. Date of initial notice in Federal Register: March 3, 2015 (80 FR 11492). The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated August 3, 2015. 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: August 27, 2014, as supplemented by letter dated February 16, 2015. Brief description of amendment: The license amendments approved the changes to the Technical Specification (TS) 3.4.3, ``[Reactor Coolant System] RCS Pressure and Temperature (P-T) Limits'' to address vacuum fill operations of the RCS to meet the requirements of 10 CFR part 50, appendix G. Specifically, this will revise TS figures 3.4.3-1 and 3.4.3-2, RCS Heatup and Cooldown Limitations respectively. Date of issuance: July 27, 2015. Effective date: As of the date of issuance and shall be implemented within 60 days from the date of issuance. Amendment Nos.: 275 and 257. A publicly-available version is in ADAMS under Accession No. ML15187A424; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. NPF-4 and NPF-7: Amendments revised the Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: October 14, 2014, (79 FR 61663). The supplemental letter dated February 16, 2015, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination. The Commission's related evaluation of the amendments is contained in a Safety Evaluation dated July 27, 2015. No significant hazards consideration comments received: No. Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek Generating Station, Coffey County, Kansas Date of amendment request: November 20, 2014, as supplemented by letters dated March 18 and May 4, 2015. Brief description of amendment: The amendment revised the Technical Specification (TS) requirements to address NRC Generic Letter 2008-01, ``Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,'' as described in Technical Specification Task Force (TSTF) Traveler TSTF-523, Revision 2, ``Generic Letter 2008-01, Managing Gas Accumulation.'' [[Page 48932]] Date of issuance: July 28, 2015. Effective date: As of its date of issuance and shall be implemented within 90 days of the date of issuance. Amendment No.: 212. A publicly-available version is in ADAMS under Accession No. ML15169A213; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. NPF-42. The amendment revised the Operating License and Technical Specifications. Date of initial notice in Federal Register: March 31, 2015 (80 FR 17105). The supplemental letters dated March 18 and May 4, 2015, 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 July 28, 2015. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, this 10th day of August 2015. For the Nuclear Regulatory Commission. A. Louise Lund, Acting Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2015-20138 Filed 8-13-15; 8:45 am] BILLING CODE 7590-01-P
![48920 Federal Register / Vol. 80, No. 157 / Friday, August 14, 2015 / Notices
NUCLEAR REGULATORY FOR FURTHER INFORMATION CONTACT: Your request should state that the NRC
COMMISSION Sandra Figueroa, Office of Nuclear does not routinely edit comment
Reactor Regulation, U.S. Nuclear submissions to remove such information
[NRC–2015–0194]
Regulatory Commission, Washington DC before making the comment
Biweekly Notice; Applications and 20555–0001; telephone: 301–415–1262, submissions available to the public or
Amendments to Facility Operating email: Sandra.Figueroa@nrc.gov. entering the comment submissions into
Licenses and Combined Licenses SUPPLEMENTARY INFORMATION: ADAMS.
Involving No Significant Hazards I. Obtaining Information and II. Notice of Consideration of Issuance
Considerations Submitting Comments of Amendments to Facility Operating
AGENCY: Nuclear Regulatory Licenses and Combined Licenses and
A. Obtaining Information
Commission. Proposed No Significant Hazards
Please refer to Docket ID NRC–2015– Consideration Determination
ACTION: Biweekly notice.
0194 when contacting the NRC about
SUMMARY: Pursuant to Section 189a. (2) the availability of information for this The Commission has made a
of the Atomic Energy Act of 1954, as action. You may obtain publicly- proposed determination that the
amended (the Act), the U.S. Nuclear available information related to this following amendment requests involve
Regulatory Commission (NRC) is action by any of the following methods: no significant hazards consideration.
publishing this regular biweekly notice. • Federal Rulemaking Web site: Go to Under the Commission’s regulations in
The Act requires the Commission to http://www.regulations.gov and search section 50.92 of Title 10 of the Code of
publish notice of any amendments for Docket ID NRC–2015–0194. Federal Regulations (10 CFR), this
issued, or proposed to be issued, and • NRC’s Agencywide Documents means that operation of the facility in
grants the Commission the authority to Access and Management System accordance with the proposed
issue and make immediately effective (ADAMS): You may obtain publicly- amendment would not (1) involve a
any amendment to an operating license available documents online in the significant increase in the probability or
or combined license, as applicable, ADAMS Public Documents collection at consequences of an accident previously
upon a determination by the http://www.nrc.gov/reading-rm/ evaluated, or (2) create the possibility of
Commission that such amendment adams.html. To begin the search, select a new or different kind of accident from
involves no significant hazards ‘‘ADAMS Public Documents’’ and then any accident previously evaluated; or
consideration, notwithstanding the select ‘‘Begin Web-based ADAMS (3) involve a significant reduction in a
pendency before the Commission of a Search.’’ For problems with ADAMS, margin of safety. The basis for this
request for a hearing from any person. please contact the NRC’s Public proposed determination for each
This biweekly notice includes all Document Room (PDR) reference staff at amendment request is shown below.
notices of amendments issued, or 1–800–397–4209, 301–415–4737, or by The Commission is seeking public
proposed to be issued from July 23, email to pdr.resource@nrc.gov. The comments on this proposed
2015, to August 5, 2015. The last ADAMS accession number for each determination. Any comments received
biweekly notice was published on document referenced (if it is available in within 30 days after the date of
August 4, 2015. ADAMS) is provided the first time that publication of this notice will be
it is mentioned in the SUPPLEMENTARY considered in making any final
DATES: Comments must be filed by
INFORMATION section.
September 17, 2015. A request for a determination.
• NRC’s PDR: You may examine and
hearing must be filed by October 19, Normally, the Commission will not
purchase copies of public documents at
2015. issue the amendment until the
the NRC’s PDR, Room O1–F21, One
ADDRESSES: You may submit comments White Flint North, 11555 Rockville expiration of 60 days after the date of
by any of the following methods (unless Pike, Rockville, Maryland 20852. publication of this notice. The
this document describes a different Commission may issue the license
method for submitting comments on a B. Submitting Comments amendment before expiration of the 60-
specific subject): Please include Docket ID NRC–2015– day period provided that its final
• Federal Rulemaking Web site: Go to 0194, facility name, unit number(s), determination is that the amendment
http://www.regulations.gov and search application date, and subject in your involves no significant hazards
for Docket ID NRC–2015–0194. Address comment submission. consideration. In addition, the
questions about NRC dockets to Carol The NRC cautions you not to include Commission may issue the amendment
Gallagher; telephone: 301–415–3463; identifying or contact information that prior to the expiration of the 30-day
email: Carol.Gallagher@nrc.gov. For you do not want to be publicly comment period should circumstances
technical questions, contact the disclosed in your comment submission. change during the 30-day comment
individual listed in the FOR FURTHER The NRC will post all comment period such that failure to act in a
INFORMATION CONTACT section of this submissions at http:// timely way would result, for example in
document. www.regulations.gov as well as enter the derating or shutdown of the facility.
• Mail comments to: Cindy Bladey, comment submissions into ADAMS. Should the Commission take action
Office of Administration, Mail Stop: The NRC does not routinely edit prior to the expiration of either the
OWFN–12–H08, U.S. Nuclear comment submissions to remove comment period or the notice period, it
asabaliauskas on DSK5VPTVN1PROD with NOTICES
Regulatory Commission, Washington, identifying or contact information. will publish in the Federal Register a
DC 20555–0001. If you are requesting or aggregating notice of issuance. Should the
For additional direction on obtaining comments from other persons for Commission make a final No Significant
information and submitting comments, submission to the NRC, then you should Hazards Consideration Determination,
see ‘‘Obtaining Information and inform those persons not to include any hearing will take place after
Submitting Comments’’ in the identifying or contact information that issuance. The Commission expects that
SUPPLEMENTARY INFORMATION section of they do not want to be publicly the need to take this action will occur
this document. disclosed in their comment submission. very infrequently.
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![48922 Federal Register / Vol. 80, No. 157 / Friday, August 14, 2015 / Notices
should be in Portable Document Format class mail as of the time of deposit in Description of amendment request:
(PDF) in accordance with NRC guidance the mail, or by courier, express mail, or The amendment would involve
available on the NRC’s public Web site expedited delivery service upon upgrading the ONS, Emergency Action
at http://www.nrc.gov/site-help/e- depositing the document with the Levels based on NEI 99–01, Revision 6,
submittals.html. A filing is considered provider of the service. A presiding ‘‘Development of Emergency Action
complete at the time the documents are officer, having granted an exemption Levels for Non-Passive Reactors.’’
submitted through the NRC’s E-Filing request from using E-Filing, may require Pursuant to 10 CFR part 50, appendix E,
system. To be timely, an electronic a participant or party to use E-Filing if section IV.B, Duke Energy requested
filing must be submitted to the E-Filing the presiding officer subsequently NRC approval of this proposed change
system no later than 11:59 p.m. Eastern determines that the reason for granting to the ONS Emergency Plan prior to
Time on the due date. Upon receipt of the exemption from use of E-Filing no implementation.
a transmission, the E-Filing system longer exists. Basis for proposed no significant
time-stamps the document and sends Documents submitted in adjudicatory hazards consideration determination:
the submitter an email notice proceedings will appear in the NRC’s As required by 10 CFR 50.91(a), the
confirming receipt of the document. The electronic hearing docket which is licensee has provided its analysis of the
E-Filing system also distributes an email available to the public at http:// issue of no significant hazards
notice that provides access to the ehd1.nrc.gov/ehd/, unless excluded consideration, which is presented
document to the NRC’s Office of the pursuant to an order of the Commission, below:
General Counsel and any others who or the presiding officer. Participants are
1. Does the proposed amendment involve
have advised the Office of the Secretary requested not to include personal a significant increase in the probability or
that they wish to participate in the privacy information, such as social consequences of an accident previously
proceeding, so that the filer need not security numbers, home addresses, or evaluated?
serve the documents on those home phone numbers in their filings, Response: No.
participants separately. Therefore, unless an NRC regulation or other law These changes affect the ONS Emergency
applicants and other participants (or requires submission of such Plan and do not alter the requirements of the
their counsel or representative) must information. However, in some Operating License or the Technical
instances, a request to intervene will Specifications. The proposed changes do not
apply for and receive a digital ID
modify plant equipment and do not impact
certificate before a hearing request/ require including information on local failure modes that could lead to an accident.
petition to intervene is filed so that they residence in order to demonstrate a Additionally, the proposed changes do not
can obtain access to the document via proximity assertion of interest in the impact the consequence of an analyzed
the E-Filing system. proceeding. With respect to copyrighted accident since the changes do not affect
A person filing electronically using works, except for limited excerpts that equipment related to accident mitigation.
the NRC’s adjudicatory E-Filing system serve the purpose of the adjudicatory Based on this discussion, the proposed
may seek assistance by contacting the filings and would constitute a Fair Use amendment does not increase the probability
NRC Meta System Help Desk through application, participants are requested or consequences of an accident previously
the ‘‘Contact Us’’ link located on the not to include copyrighted materials in evaluated.
2. Does the proposed amendment [create
NRC’s public Web site at http:// their submission. the possibility of a new or different kind of
www.nrc.gov/site-help/e- Petitions for leave to intervene must accident from any accident previously
submittals.html, by email to be filed no later than 60 days from the evaluated]?
MSHD.Resource@nrc.gov, or by a toll- date of publication of this notice. Response: No.
free call at 1–866–672–7640. The NRC Requests for hearing, petitions for leave These changes affect the ONS Emergency
Meta System Help Desk is available to intervene, and motions for leave to Plan and do not alter the requirements of the
between 8 a.m. and 8 p.m., Eastern file new or amended contentions that Operating License or the Technical
Time, Monday through Friday, are filed after the 60-day deadline will Specifications. They do not modify plant
excluding government holidays. not be entertained absent a equipment and there is no impact on the
capability of the existing equipment to
Participants who believe that they determination by the presiding officer perform their intended functions. No system
have a good cause for not submitting that the filing demonstrates good cause setpoints are being modified and no changes
documents electronically must file an by satisfying the three factors in 10 CFR are being made to the method in which plant
exemption request, in accordance with 2.309(c)(1)(i)–(iii). operations are conducted. No new failure
10 CFR 2.302(g), with their initial paper For further details with respect to modes are introduced by the proposed
filing requesting authorization to these license amendment applications, changes. The proposed amendment does not
continue to submit documents in paper see the application for amendment introduce an accident initiator or
format. Such filings must be submitted which is available for public inspection malfunction that would cause a new or
by: (1) First class mail addressed to the in ADAMS and at the NRC’s PDR. For different kind of accident.
Therefore, the proposed amendment does
Office of the Secretary of the additional direction on accessing not create the possibility of a new or different
Commission, U.S. Nuclear Regulatory information related to this document, kind of accident from an accident previously
Commission, Washington, DC 20555– see the ‘‘Obtaining Information and evaluated.
0001, Attention: Rulemaking and Submitting Comments’’ section of this 3. Does the proposed change involve a
Adjudications Staff; or (2) courier, document. significant reduction in a margin of safety?
express mail, or expedited delivery Response: No.
service to the Office of the Secretary, Duke Energy Carolinas, LLC, Docket These changes affect the ONS Emergency
asabaliauskas on DSK5VPTVN1PROD with NOTICES
Sixteenth Floor, One White Flint North, Nos. 50–269, 50–270, and 50–287, Plan and do not alter the requirements of the
11555 Rockville Pike, Rockville, Oconee Nuclear Station, Units 1, 2, and Operating License or the Technical
3 (ONS), Oconee County, South Specifications. The proposed changes do not
Maryland, 20852, Attention:
Carolina affect the assumptions used in the accident
Rulemaking and Adjudications Staff. analysis, nor do they affect the operability
Participants filing a document in this Date of amendment request: June 23, requirements for equipment important to
manner are responsible for serving the 2015. A publicly-available version is in plant safety.
document on all other participants. ADAMS under Accession No. Therefore, the proposed changes will not
Filing is considered complete by first- ML15183A060. result in a significant reduction in the margin
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![48924 Federal Register / Vol. 80, No. 157 / Friday, August 14, 2015 / Notices
2. Does the proposed amendment create licensee has provided its analysis of the Energy Institute 94–01, Revision 2A,
the possibility of a new or different kind of issue of no significant hazards ‘‘Industry Guideline for Implementing
accident from any accident previously consideration, which is presented Performance-Based Option of 10 CFR
evaluated? below: part 50, appendix J,’’ dated October
Response: No.
These changes affect the CPNPP 1. Does the proposed change involve a 2008 (ADAMS Accession No.
Emergency Plan and do not alter any of the significant increase in the probability or ML100620847).
requirements of the Operating License or the consequences of an accident previously Basis for proposed no significant
Technical Specifications. They do not modify evaluated? hazards consideration determination:
any plant equipment and there is no impact Response: No. As required by 10 CFR 50.91(a), the
on the capability of the existing equipment The proposed changes to the Technical licensee has provided its analysis of the
to perform their intended functions. No Specifications (TS) regarding Shift issue of no significant hazards
system setpoints are being modified and no Supervisor to Shift Manager are
administrative changes. It has no impact on
consideration, which is presented
changes are being made to the method in below:
which plant operations are conducted. No accident initiators or plant equipment and
new failure modes are introduced by the thus does not affect the probability or 1. Does the proposed amendment involve
proposed changes. The proposed amendment consequences of an accident. a significant increase in the probability or
does not introduce accident initiators or 2. Does the proposed change create the consequences of an accident previously
malfunctions that would cause a new or possibility of a new or different kind of evaluated?
different kind of accident. accident from any accident previously Response: No.
Therefore, the proposed amendment does evaluated? The proposed amendment to the TS
Response: No. involves the extension of the STP, Units 1
not create the possibility of a new or different
The proposed change does not involve a and 2 Type A containment test interval to 15
kind of accident from any accident
change to the physical plant or operations. years. The current Type A test interval of 120
previously evaluated.
This is an administrative title change that months (10 years) would be extended on a
3. Does the proposed amendment involve
does not contribute to accident initiation. permanent basis to no longer than 15 years
a significant reduction in a margin of safety?
Therefore, it does not produce a new from the last Type A test. Extensions of up
Response: No.
accident scenario or produce a new type of to nine months (total maximum interval of
These changes affect the CPNPP
equipment malfunction. 189 months for Type A tests) are permissible
Emergency Plan and do not alter any of the
3. Does the proposed change involve a only for non-routine emergent conditions.
requirements of the Operating License or the
significant reduction in a margin of safety? The proposed extension does not involve
Technical Specifications. The proposed Response: No.
changes do not affect any of the assumptions either a physical change to the plant or a
Since the change is administrative and change in the manner in which the plant is
used in the accident analysis, nor do they changes no previously evaluated accidents or
affect any operability requirements for operated or controlled. The containment is
creates no possibility for any new designed to provide an essentially leak tight
equipment important to plant safety. unevaluated accidents to occur, there is no
Therefore, the proposed changes will not barrier against the uncontrolled release of
reduction in the margin of safety. This radioactivity to the environment for
result in a significant reduction in the margin change also does not affect plant equipment
of safety as defined in the bases for technical postulated accidents. As such, the
or operation and therefore does not affect containment and the testing requirements
specifications covered in this license safety limits or limiting safety systems
amendment request. invoked to periodically demonstrate the
settings. integrity of the containment exist to ensure
The NRC staff has reviewed the The NRC staff has reviewed the the plant’s ability to mitigate the
licensee’s analysis and, based on this licensee’s analysis and, based on this consequences of an accident, and do not
review, it appears that the three review, it appears that the three involve the prevention or identification of
standards of 10 CFR 50.92(c) are standards of 10 CFR 50.92(c) are any precursors of an accident. The change in
satisfied. Therefore, the NRC staff dose risk for changing the Type A test
satisfied. Therefore, the NRC staff
proposes to determine that the frequency from once-per-ten years to once-
proposes to determine that the per-fifteen-years, measured as an increase to
amendment request involves no amendment request involves no the total integrated dose risk for all internal
significant hazards consideration. significant hazards consideration. events accident sequences for STP, of 0.123
Attorney for licensee: Timothy P. Attorney for licensee: J. Hagood person [roentgen equivalent man per year
Matthews, Esq., Morgan, Lewis and Hamilton, Jr., South Carolina Electric & (rem/yr)] for Unit 1 and Unit 2 using the
Bockius, 1111 Pennsylvania Avenue Gas Company, Post Office Box 764, [Electric Power Research Institute (EPRI)]
NW., Washington, DC 20004. Columbia, South Carolina 29218. guidance with the base case corrosion
NRC Branch Chief: Michael T. NRC Branch Chief: Robert J. included. Therefore, this proposed extension
Markley. Pascarelli. does not involve a significant increase in the
probability of an accident previously
South Carolina Electric & Gas Company, STP Nuclear Operating Company, evaluated.
South Carolina Public Service Docket Nos. 50–498 and 50–499, South As documented in NUREG–1493,
Authority, Docket No. 50–395, Virgil C. Texas Project (STP), Units 1 and 2, [‘‘Performance-Based Containment Leak-Test
Summer Nuclear Station, Unit No. 1, Matagorda County, Texas Program,’’ dated January 1995] Type B and C
Fairfield County, South Carolina tests have identified a very large percentage
Date of amendment request: April 29, of containment leakage paths, and the
Date of amendment request: July 22, 2015, as supplemented by letter dated percentage of containment leakage paths that
2015. A publicly-available version is in June 29, 2015. Publicly-available are detected only by Type A testing is very
ADAMS Accession No. ML15205A291. versions are in ADAMS under small. The STP, Units 1 and 2 Type A test
Description of amendment request: Accession Nos. ML15128A352 and history supports this conclusion.
asabaliauskas on DSK5VPTVN1PROD with NOTICES
The licensee proposes to revise ML15198A147, respectively. The integrity of the containment is subject
Technical Specification Section 6.0, Description of amendment request: to two types of failure mechanisms that can
The amendment would revise the be categorized as: (1) Activity based, and; (2)
‘‘Administrative Controls’’ by changing
time based. Activity based failure
the ‘‘Shift Supervisor’’ title to ‘‘Shift Integrated Leak Rate Test performance mechanisms are defined as degradation due
Manager.’’ interval from 10 years to 15 years in to system and/or component modifications or
Basis for proposed no significant Technical Specification (TS) 3.8.3.j, maintenance. Local leak rate test
hazards consideration determination: ‘‘Containment Leakage Rate Testing requirements and administrative controls
As required by 10 CFR 50.91(a), the Program,’’ in accordance with Nuclear such as configuration management and
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![Federal Register / Vol. 80, No. 157 / Friday, August 14, 2015 / Notices 48925
procedural requirements for system The proposed change involves only the involving no significant hazards
restoration ensure that containment integrity extension of the interval between Type A consideration.
is not degraded by plant modifications or containment leak rate tests for STP, Units 1 For details, see the individual notice
maintenance activities. The design and and 2. The proposed surveillance interval in the Federal Register on the day and
construction requirements of the extension is bounded by the 15-year ILRT
containment combined with the containment
page cited. This notice does not extend
Interval currently authorized within NEI 94–
inspections performed in accordance with 01, Revision 2–A. Industry experience the notice period of the original notice.
ASME Section XI, the Maintenance Rule, and supports the conclusion that Type B and C Susquehanna Nuclear, LLC, Docket Nos.
TS requirements serve to provide a high testing detects a large percentage of 50–387 and 50–388, Susquehanna
degree of assurance that the containment containment leakage paths and that the
would not degrade in a manner that is Steam Electric Station (SSES), Units 1
percentage of containment leakage paths that
detectable only by a Type A test. Based on are detected only by Type A testing is small. and 2, Luzerne County, Pennsylvania
the above, the proposed extensions do not The containment inspections performed in Date of amendment request: August
significantly increase the consequences of an accordance with [American Society for 11, 2014, as supplemented by letters
accident previously evaluated. Mechanical Engineers (ASME) Boiler and dated April 6, 2015, and July 16, 2015.
The proposed amendment also deletes Pressure Vessel Code,] Section Xl, TS and the
exceptions previously granted to allow one- Publicly-available versions are in
Maintenance Rule serve to provide a high
time extensions of the ILRT test frequency for ADAMS under Accession Nos.
degree of assurance that the containment
both Units 1 and 2. These exceptions were would not degrade in a manner that is ML14223A780, ML15097A386, and
for activities that have already taken place so detectable only by Type A testing. The ML15197A256, respectively.
their deletion is solely an administrative combination of these factors ensures that the Brief description of amendment
action that has no effect on any component margin of safety in the plant safety analysis request: The amendment proposes
and no impact on how the units are operated. is maintained. The design, operation, testing changes to SSES, Units 1 and 2,
Therefore, the proposed change does not methods and acceptance criteria for Type A, Technical Specification 3.4.10, ‘‘RCS
result in a significant increase in the B, and C containment leakage tests specified [Reactor Coolant System] Pressure and
probability or consequences of an accident in applicable codes and standards would
previously evaluated.
Temperature (P/T) Limits,’’ which
continue to be met, with the acceptance of includes revisions to the P/T Limits
2. Does the proposed change create the this proposed change, since these are not
possibility of a new or different kind of affected by changes to the Type A and Type
curves.
accident from any accident previously C test intervals.
Date of publication of individual
evaluated? The proposed amendment also deletes notice in Federal Register: July 30,
Response: No. exceptions previously granted to allow one- 2015 (80 FR 45559).
The proposed amendment to the TS time extensions of the ILRT test frequency for Expiration date of individual notice:
involves the extension of the STP, Unit 1 and both Units 1 and 2. These exceptions were August 31, 2015 (public comments);
2 Type A containment test interval to 15 for activities that would have already taken September 28, 2015 (hearing requests).
years. The containment and the testing place by the time this amendment is
requirements to periodically demonstrate the approved; therefore, their deletion is solely IV. Notice of Issuance of Amendments
integrity of the containment exist to ensure an administrative action and does not change to Facility Operating Licenses and
the plant’s ability to mitigate the how the units are operated and maintained. Combined Licenses
consequences of an accident do not involve Thus, there is no reduction in any margin of
any accident precursors or initiators. The During the period since publication of
safety.
proposed change does not involve a physical the last biweekly notice, the
Therefore, the proposed change does not
change to the plant (i.e., no new or different involve a significant reduction in a margin of Commission has issued the following
type of equipment will be installed) or a safety. amendments. The Commission has
change to the manner in which the plant is determined for each of these
operated or controlled. The NRC staff has reviewed the amendments that the application
The proposed amendment also deletes licensee’s analysis and, based on this complies with the standards and
exceptions previously granted to allow one- review, it appears that the standards of requirements of the Atomic Energy Act
time extensions of the ILRT test frequency for 10 CFR 50.92(c) are satisfied. Therefore, of 1954, as amended (the Act), and the
both Units 1 and 2. These exceptions were the NRC staff proposes to determine that
for activities that would have already taken Commission’s rules and regulations.
the request for amendments involves no The Commission has made appropriate
place by the time this amendment is
approved; therefore, their deletion is solely significant hazards consideration. findings as required by the Act and the
an administrative action that does not result NRC Branch Chief: Michael T. Commission’s rules and regulations in
in any change in how the units are operated. Markley. 10 CFR Chapter I, which are set forth in
Therefore, the proposed change does not the license amendment.
create the possibility of a new or different III. Previously Published Notices of
Consideration of Issuance of A notice of consideration of issuance
kind of accident from any previously of amendment to facility operating
evaluated. Amendments to Facility Operating
Licenses and Combined Licenses, license or combined license, as
3. Does the proposed change involve a
significant reduction in a margin of safety? Proposed No Significant Hazards applicable, proposed no significant
Response: No. Consideration Determination, and hazards consideration determination,
The proposed amendment to TS 6.8.3.j Opportunity for a Hearing and opportunity for a hearing in
involves the extension of the STP, Units 1 connection with these actions, was
and 2 Type A containment test interval to 15 The following notices were previously published in the Federal Register as
years. This amendment does not alter the published as separate individual indicated.
manner in which safety limits, limiting safety notices. The notice content was the Unless otherwise indicated, the
asabaliauskas on DSK5VPTVN1PROD with NOTICES
system set points, or limiting conditions for same as above. They were published as Commission has determined that these
operation are determined. The specific individual notices either because time amendments satisfy the criteria for
requirements and conditions of the TS
did not allow the Commission to wait categorical exclusion in accordance
Containment Leak Rate Testing Program exist
to ensure that the degree of containment for this biweekly notice or because the with 10 CFR 51.22. Therefore, pursuant
structural integrity and leak-tightness that is action involved exigent circumstances. to 10 CFR 51.22(b), no environmental
considered in the plant safety analysis is They are repeated here because the impact statement or environmental
maintained. The overall containment leak biweekly notice lists all amendments assessment need be prepared for these
rate limit specified by TS is maintained. issued or proposed to be issued amendments. If the Commission has
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![48930 Federal Register / Vol. 80, No. 157 / Friday, August 14, 2015 / Notices
Brief description of amendment: The Amendment Nos.: 264 and 259. The The Commission’s related evaluation
amendment revised the TMI–1 amendments are in ADAMS under of the amendments is contained in a
Technical Specification Table 3.1.6.1, Accession No. ML15181A179; Safety Evaluation dated July 28, 2015.
‘‘Pressure Isolation Check Valves documents related to these amendments No significant hazards consideration
Between the Primary Coolant System & are listed in the Safety Evaluation comments received: No.
LPIS [Low Pressure Injection System],’’ enclosed with the amendments.
PSEG Nuclear LLC, Docket Nos. 50–272
maximum allowable leakage limits. Renewed Facility Operating License
and 50–311, Salem Nuclear Generating
Date of issuance: July 28, 2015. Nos. DPR–31 and DPR–41: Amendments
Station (Salem), Unit Nos. 1 and 2,
Effective date: As of the date of revised the TSs.
Salem County, New Jersey
issuance and shall be implemented Date of initial notice in Federal
within 30 days. Register: October 14, 2014 (79 FR Date amendment request: July 28,
Amendment Nos.: 286. A publicly- 61661). The licensee’s supplemental 2014, as supplemented by letter dated
available version is in ADAMS under letter dated July 15, 2015, did not January 15, 2015.
Accession No. ML15090A584; expand the scope of the application as Brief description of amendments: The
documents related to this amendment originally noticed and did not change amendments revised the technical
are listed in the Safety Evaluation the staff’s original proposed no specification (TS) requirements
enclosed with the amendment. significant hazards consideration regarding steam generator tube
Renewed Facility Operating License determination as published in the inspections and reporting as described
No. DPR–50: The amendment revised Federal Register. in Technical Specifications Task Force
the Facility Operating License and The Commission’s related evaluation (TSTF) Change Traveler TSTF–510,
Technical Specifications. of the amendments is contained in a Revision 2, ‘‘Revision to Steam
Date of initial notice in Federal Safety Evaluation dated July 27, 2015. Generator Program Inspection
Register: December 9, 2014 (79 FR No significant hazards consideration Frequencies and Tube Sample
73110). The supplemental letter dated comments received: No. Selection.’’ In addition, the amendments
June 10, 2015, provided additional revise the Salem, Unit No. 2 TSs 6.8.4.i,
NextEra Energy, Point Beach, LLC, ‘‘Steam Generator (SG) Program,’’ and
information that clarified the
Docket Nos. 50–266 and 50–301, Point TS 6.9.1.10, ‘‘Steam Generator Tube
application, did not expand the scope of
Beach Nuclear Plant Units 1 and 2, Inspection Report,’’ to remove
the application as originally noticed,
Town of Two Creeks, Manitowoc unnecessary information related to the
and did not change the staff’s original
County, Wisconsin original Salem, Unit No. 2
proposed no significant hazards
consideration determination as Date of amendment request: July 3, Westinghouse steam generators.
published in the Federal Register. 2014, as supplemented by letters dated Date of issuance: July 30, 2015.
The Commission’s related evaluation December 8, 2014; March 19, 2015; and Effective date: As of the date of
of the amendment is contained in a May 28, 2015. issuance and shall be implemented
Safety Evaluation dated July 28, 2015. Brief description of amendments: The within 60 days.
No significant hazards consideration amendments revised the Technical Amendment Nos.: 309 and 291. A
comments received: No. Specifications (TSs) for Units 1 and 2 to publicly-available version is in ADAMS
relocate surveillance frequencies to under Accession No. ML15153A230;
Florida Power & Light Company, Docket licensee control as per Technical documents related to these amendments
Nos. 50–250 and 50–251, Turkey Point Specifications Task Force Traveler–425, are listed in the Safety Evaluation
Nuclear Generating Unit Nos. 3 and 4, Revision 3. enclosed with the amendments.
Miami-Dade County, Florida Date of issuance: July 28, 2015. Renewed Facility Operating License
Date of application for amendments: Effective date: As of the date of Nos. DPR–70 and DPR–75: The
July 8, 2014, as supplemented by letter issuance and shall be implemented amendments revised the facility
dated July 15, 2015. within 90 days of issuance. operating license and TSs.
Brief description of amendments: The Amendment Nos.: 253 and 257. Date of initial notice in Federal
amendments revised the Technical Publicly-available versions are in Register: October 28, 2014 (79 FR
Specifications (TSs) by modifying or ADAMS under Accession No. 64227). The supplemental letter dated
adding surveillance requirements to ML15195A201; documents related to January 15, 2015, provided additional
verify that system locations susceptible these amendments are listed in the information that clarified the
to gas accumulation are sufficiently Safety Evaluation enclosed with the application, did not expand the scope of
filled with water and to provide amendments. the application as originally noticed,
allowances that permit performance of Renewed Facility Operating License and did not change the staff’s original
the verification. The changes address Nos. DPR–24 and DPR–27: Amendments proposed no significant hazards
NRC Generic Letter 2008–01, ‘‘Managing revised the Facility Operating Licenses consideration determination as
Gas Accumulation in Emergency Core and TSs. published in the Federal Register.
Cooling, Decay Heat Removal, and Date of initial notice in Federal The Commission’s related evaluation
Containment Spray Systems’’ (ADAMS Register: November 12, 2014 (79 FR of the amendments is contained in a
Accession No. ML072910759), as 67203). The supplemental letters dated safety evaluation dated July 30, 2015.
described in Revision 2 of Technical December 8, 2014; March 19, 2015; and No significant hazards consideration
asabaliauskas on DSK5VPTVN1PROD with NOTICES
Specification Task Force-523, ‘‘Generic May 28, 2015, provided additional comments received: No.
Letter 2008–01, Managing Gas information that clarified the
Accumulation’’ (ADAMS Accession No. application, did not expand the scope of South Carolina Electric & Gas Company,
ML13053A075). the application as originally noticed, Docket Nos. 52–027 and 52–028, Virgil
Date of issuance: July 27, 2015. and did not change the staff’s original C. Summer Nuclear Station, Units 2 and
Effective date: As of the date of proposed no significant hazards 3, Fairfield County, South Carolina
issuance and shall be implemented consideration determination as Date of amendment request:
within 120 days of issuance. published in the Federal Register. September 11, 2014, and supplemented
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![Federal Register / Vol. 80, No. 157 / Friday, August 14, 2015 / Notices 48931
by letters dated October 15, 2014 and Effective date: As of the date of Virginia Electric and Power Company,
December 18, 2014. issuance and shall be implemented Docket Nos. 50–338 and 50–339, North
Description of amendment: The within 30 days of issuance. Anna Power Station, Units 1 and 2,
amendment revises the Updated Final Amendment No.: 26. A publicly- Louisa County, Virginia
Safety Analysis Report by clarifying available version is in ADAMS under Date of application for amendment:
human diversity during the lifecycle Accession No. ML15131A445; August 27, 2014, as supplemented by
development design process for the documents related to this amendment letter dated February 16, 2015.
Component Interface Module and are listed in the Safety Evaluation Brief description of amendment: The
Diverse Actuation System. enclosed with the amendment. license amendments approved the
Facility Combined Licenses No. NPF– changes to the Technical Specification
Date of issuance: July 17, 2015.
93 and NPF–94: Amendment revised the (TS) 3.4.3, ‘‘[Reactor Coolant System]
Effective date: As of the date of Facility Combined Licenses.
issuance and shall be implemented RCS Pressure and Temperature (P–T)
Date of initial notice in Federal
within 90 days of issuance. Limits’’ to address vacuum fill
Register: March 17, 2015 (80 FR
Amendment No.: 28. A publicly- operations of the RCS to meet the
13912).
available version is in ADAMS under requirements of 10 CFR part 50,
The Commission’s related evaluation
Accession No. ML15176A703; appendix G. Specifically, this will
of the amendment is contained in a
documents related to this amendment revise TS figures 3.4.3–1 and 3.4.3–2,
Safety Evaluation dated June 2, 2015.
are listed in the Safety Evaluation No significant hazards consideration RCS Heatup and Cooldown Limitations
enclosed with the amendment. comments received: No. respectively.
Date of issuance: July 27, 2015.
Facility Combined Licenses No. NPF– Southern Nuclear Operating Company, Effective date: As of the date of
93 and NPF–94: Amendment revised the Inc., Docket Nos. 50–348 and 50–364, issuance and shall be implemented
Facility Combined Licenses. Joseph M. Farley Nuclear Plant (Farley), within 60 days from the date of
Date of initial notice in Federal Units 1 and 2, Houston County, issuance.
Register: December 9, 2014 (79 FR Alabama Amendment Nos.: 275 and 257. A
73111). The supplemental letters dated publicly-available version is in ADAMS
October 15, 2014 and December 18, Southern Nuclear Operating Company,
under Accession No. ML15187A424;
Inc., Docket Nos. 50–424 and 50–425,
2014, provided additional information documents related to these amendments
Vogtle Electric Generating Plant (VEGP),
that clarified the application, did not are listed in the Safety Evaluation
Units 1 and 2, Burke County, Georgia
expand the scope of the application as enclosed with the amendments.
originally noticed, and did not change Southern Nuclear Operating Company, Renewed Facility Operating License
the staff’s original proposed no Inc., Georgia Power Company, Nos. NPF–4 and NPF–7: Amendments
significant hazards consideration Oglethorpe Power Corporation, revised the Facility Operating License
determination as published in the Municipal Electric Authority of Georgia, and Technical Specifications.
Federal Register. City of Dalton, Georgia, Docket Nos. 50– Date of initial notice in Federal
The Commission’s related evaluation 321 and 50–366, Edwin I. Hatch Nuclear Register: October 14, 2014, (79 FR
of the amendment is contained in the Plant, Unit Nos. 1 and 2, Appling 61663). The supplemental letter dated
Safety Evaluation dated July 17, 2015. County, Georgia February 16, 2015, provided additional
No significant hazards consideration Date of application for amendment: information that clarified the
comments received: No. December 30, 2014. application, did not expand the scope of
Brief description of amendments: The the application as originally noticed,
South Carolina Electric and Gas amendments revise the date of the full and did not change the staff’s original
Company, Docket Nos. 52–027 and 52– implementation of the Cyber Security proposed no significant hazards
028, Virgil C. Summer Nuclear Station, Plans. consideration determination.
Units 2 and 3 (VCSNS), Fairfield Date of issuance: August 3, 2015. The Commission’s related evaluation
County, South Carolina Effective date: As of its date of of the amendments is contained in a
Date of amendment request: January issuance and shall be implemented Safety Evaluation dated July 27, 2015.
within 30 days from the date of No significant hazards consideration
27, 2015.
issuance. comments received: No.
Brief description of amendment: The Amendment Nos.: Farley Unit 1–199,
amendments are to Combined License Wolf Creek Nuclear Operating
Farley Unit 2–195, VEGP Unit 1–175, Corporation, Docket No. 50–482, Wolf
Nos. NPF–93 and NPF–94 for VCSNS VEGP Unit 2–157, Hatch Unit 1–274,
Units 2 and 3. The amendments revise Creek Generating Station, Coffey
and Hatch Unit 2–219. A publicly- County, Kansas
the VCSNS Units 2 and 3 Updated Final available version is in ADAMS under
Safety Analysis Report (UFSAR) to Accession No. ML15180A334, Date of amendment request:
clarify a human factors engineering documents related to these amendments November 20, 2014, as supplemented by
operational sequence analysis related to are listed in the Safety Evaluation letters dated March 18 and May 4, 2015.
the AP1000 Automatic Depressurization enclosed with the amendments. Brief description of amendment: The
System and delete document WCAP– Facility Operating License Nos. NPF– amendment revised the Technical
15847, ‘‘AP1000 Quality Assurance 2, NPF–8, NPF–68, NPF–81, DPR–57, Specification (TS) requirements to
Procedures Supporting NRC Review of address NRC Generic Letter 2008–01,
asabaliauskas on DSK5VPTVN1PROD with NOTICES
NPF–5: The amendments revised the
AP1000 DCD Sections 18.2 and 18.8,’’ Renewed Facility Operating Licenses. ‘‘Managing Gas Accumulation in
that is incorporated by reference into Date of initial notice in Federal Emergency Core Cooling, Decay Heat
the UFSAR. Both of the amendments Register: March 3, 2015 (80 FR 11492). Removal, and Containment Spray
constitute changes to information The Commission’s related evaluation Systems,’’ as described in Technical
identified as Tier 2* information as of the amendments is contained in a Specification Task Force (TSTF)
defined in 10 CFR part 52, appendix D, Safety Evaluation dated August 3, 2015. Traveler TSTF–523, Revision 2,
section II.F. No significant hazards consideration ‘‘Generic Letter 2008–01, Managing Gas
Date of issuance: June 2, 2015. comments received: No. Accumulation.’’
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![48932 Federal Register / Vol. 80, No. 157 / Friday, August 14, 2015 / Notices
Date of issuance: July 28, 2015. by and hold discussions with the NRC NUCLEAR REGULATORY
Effective date: As of its date of staff and staff from Mitsubishi Heavy COMMISSION
issuance and shall be implemented Industries. The Subcommittee will
within 90 days of the date of issuance. gather information, analyze relevant Advisory Committee on Reactor
Amendment No.: 212. A publicly- issues and facts, and formulate Safeguards; Meeting of the ACRS
available version is in ADAMS under proposed positions and actions, as Subcommittee on Reliability and PRA;
Accession No. ML15169A213; appropriate, for deliberation by the Full Notice of Meeting
documents related to this amendment Committee.
are listed in the Safety Evaluation The ACRS Subcommittee on
enclosed with the amendment. Members of the public desiring to Reliability and PRA will hold a meeting
Renewed Facility Operating License provide oral statements and/or written on August 21, 2015, Room T–2B3,
No. NPF–42. The amendment revised comments should notify the Designated 11545 Rockville Pike, Rockville,
the Operating License and Technical Federal Official (DFO), Girija Shukla Maryland 20852.
Specifications. (Telephone: 301–415–6855 or Email: The meeting will be open to public
Date of initial notice in Federal Girija.Shukla@nrc.gov) five days prior to attendance.
Register: March 31, 2015 (80 FR the meeting, if possible, so that The agenda for the subject meeting
17105). The supplemental letters dated arrangements can be made. Thirty-five shall be as follows:
March 18 and May 4, 2015, provided hard copies of each presentation or Friday, August 21, 2015—1:00 p.m.
additional information that clarified the handout should be provided to the DFO Until 5:00 p.m.
application, did not expand the scope of thirty minutes before the meeting. In
the application as originally noticed, The Subcommittee will discuss the
addition, one electronic copy of each development of the Interim Staff
and did not change the staff’s original presentation should be Emailed to the
proposed no significant hazards Guidance on Probabilistic Risk
DFO one day before the meeting. If an Assessment requirements for the
consideration determination as electronic copy cannot be provided
published in the Federal Register. Advanced Light-Water Reactor license
The Commission’s related evaluation within this timeframe, presenters application under 10 CFR part 52. The
of the amendment is contained in a should provide the DFO with a CD Subcommittee will hear presentations
Safety Evaluation dated July 28, 2015. containing each presentation at least by and hold discussions with the NRC
No significant hazards consideration thirty minutes before the meeting. staff and other interested persons
comments received: No. Electronic recordings will be permitted regarding this matter. The
only during those portions of the Subcommittee will gather information,
Dated at Rockville, Maryland, this 10th day
meeting that are open to the public. analyze relevant issues and facts, and
of August 2015.
Detailed procedures for the conduct of formulate proposed positions and
For the Nuclear Regulatory Commission.
and participation in ACRS meetings actions, as appropriate, for deliberation
A. Louise Lund, by the Full Committee.
were published in the Federal Register
Acting Director, Division of Operating Reactor Members of the public desiring to
Licensing, Office of Nuclear Reactor on October 1, 2014 (79 FR 59307).
provide oral statements and/or written
Regulation. Detailed meeting agendas and meeting comments should notify the Designated
[FR Doc. 2015–20138 Filed 8–13–15; 8:45 am] transcripts are available on the NRC Federal Official (DFO), Hossein
BILLING CODE 7590–01–P Web site at http://www.nrc.gov/reading- Nourbakhsh (Telephone: 301–415–5622
rm/doc-collections/acrs. Information or Email: Hossein.Nourbakhsh@nrc.gov)
regarding changes to the agenda, five days prior to the meeting, if
NUCLEAR REGULATORY whether the meeting has been canceled possible, so that appropriate
COMMISSION or rescheduled, and the time allotted to arrangements can be made. Thirty-five
present oral statements can be obtained hard copies of each presentation or
Advisory Committee on Reactor
by contacting the identified DFO. handout should be provided to the DFO
Safeguards (ACRS); Meeting of the
Moreover, in view of the possibility that thirty minutes before the meeting. In
ACRS Subcommittee on US–APWR;
the schedule for ACRS meetings may be addition, one electronic copy of each
Notice of Meeting
adjusted by the Chairman as necessary presentation should be Emailed to the
The ACRS Subcommittee on US– to facilitate the conduct of the meeting, DFO one day before the meeting. If an
APWR will hold a meeting on August persons planning to attend should check electronic copy cannot be provided
20, 2015, Room T–2B3, 11545 Rockville with the DFO if such rescheduling within this timeframe, presenters
Pike, Rockville, Maryland 20852. would result in a major inconvenience. should provide the DFO with a CD
The meeting will be open to public containing each presentation at least
If attending this meeting, please enter thirty minutes before the meeting.
attendance with the exception of
through the One White Flint North Detailed procedures for the conduct of
portions that may be closed to protect
information that is proprietary pursuant building, 11555 Rockville Pike, and participation in ACRS meetings
to 5 U.S.C. 552b(c)(4). The agenda for Rockville, Maryland 20852. After were published in the Federal Register
the subject meeting shall be as follows: registering with Security, please contact on October 1, 2014 (79 FR 59307).
Mr. Theron Brown (Telephone: 240– Detailed meeting agendas and
Thursday, August 20, 2015—8:30 a.m. 888–9835) to be escorted to the meeting transcripts are available on the NRC
asabaliauskas on DSK5VPTVN1PROD with NOTICES
Until 5:00 p.m. room. Web site at http://www.nrc.gov/reading-
The Subcommittee will review Dated: August 6, 2015. rm/doc-collections/acrs. Information
Chapter 18, ‘‘Human Factors regarding topics to be discussed,
Mark L. Banks,
Engineering’’ of the Safety Evaluation changes to the agenda, whether the
Report and related Topical Report Chief, Technical Support Branch, Advisory meeting has been canceled or
MUAP–07007–P associated with the Committee on Reactor Safeguards. rescheduled, and the time allotted to
US–APWR design certification. The [FR Doc. 2015–20133 Filed 8–13–15; 8:45 am] present oral statements may be obtained
Subcommittee will hear presentations BILLING CODE 7590–01–P from the Web site cited above or by
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Document Created: 2018-02-23 10:59:08
Document Modified: 2018-02-23 10:59:08
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Biweekly notice. | |
| Dates | Comments must be filed by September 17, 2015. A request for a hearing must be filed by October 19, 2015. | |
| Contact | Sandra Figueroa, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-1262, email: [email protected] | |
| FR Citation | 80 FR 48920 |
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