Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 48463-48470 [2018-20333]

Download as PDF Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices daltland on DSKBBV9HB2PROD with NOTICES responded on August 29, 2018, stating that the WY SHPO would not be commenting, considering its understanding that Section 106 consultation was completed during the original licensing for the project (ADAMS Accession No. ML18242A349). On August 9, 2018, the NRC staff made sections of the draft EA concerning historic and cultural resources available on the NRC public web page for the Smith Ranch Project for public comment at https:// www.nrc.gov/materials/uraniumrecovery/license-apps/smith-ranch/ section106-smith-ranch.html. On the same date, the NRC staff also made these same sections of the draft EA available to the Tribal Historic Preservation Officers (THPOs) from 27 Native American Tribes for their review and comment. No comments were received from members of the public. In response to comments received from the THPO for the Northern Arapaho Tribe (ADAMS Accession No. ML18247A228), the NRC staff hosted two conference calls, on August 28 and 30, 2018, to discuss the staff’s approach concerning protection of historic and cultural resources (ADAMS Accession No. ML18243A262); no THPOs attended these calls. The NRC staff also held a conference call with the Northern Cheyenne THPO on August 31, 2018 (ADAMS Accession No. ML18260A046). No written comments were received from the Northern Cheyenne THPO. However, the NRC staff addressed the Northern Arapaho THPO’s comments provided on August 31, 2018, conference call in the final EA. Additional Information The NRC staff conducted its environmental review in accordance with 10 CFR part 51, which implements the requirements of the National Environmental Policy Act of 1969, as amended (NEPA) and following the NRC staff guidance in NUREG–1748, ‘‘Environmental Review Guidance for Licensing Actions Associated with NMSS Programs’’ (ADAMS Accession No. ML032450279). In May 2009, the NRC staff issued NUREG–1910, ‘‘Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities’’ (herein referred to as the GEIS) (ADAMS Accession No. ML15093A368 and ML15093A486). In the GEIS, the NRC staff assessed the potential environmental impacts from construction, operation, aquifer restoration, and decommissioning of an in-situ leach uranium milling facility (also known as an ISR facility) located VerDate Sep<11>2014 17:40 Sep 24, 2018 Jkt 244001 in four specific geographic regions of the western United States. Smith Ranch Project properties are located in two of these four regions. Where applicable, this EA incorporates by reference relevant portions from the GEIS, and uses sitespecific information from Cameco’s license renewal application and responses to NRC staff requests for additional information, and from independent sources to fulfill the requirements in 10 CFR 51.20(b)(8). License SUA–1548 authorizes Cameco to conduct ISR operations at four properties under the Smith Ranch Project located in Wyoming: The contiguous Smith Ranch, Highland, and Reynolds Ranch properties in Converse County; the North Butte remote satellite site in Campbell County; the Ruth remote satellite site in Johnson County; and the Gas Hills remote satellite site in Fremont and Natrona Counties. In the EA, the NRC staff assessed the potential environmental impacts from the continued construction, operation, aquifer restoration, and decommissioning of the sites under the Smith Ranch Project. The NRC staff assessed the impacts of the proposed action on land use; historical and cultural resources; visual and scenic resources; climatology, meteorology and air quality; geology, minerals, and soils; water resources; ecological resources; socioeconomics; noise; traffic and transportation; public and occupational health and safety; and waste management. In addition to the action proposed by the licensee, the NRC staff addressed the No-Action Alternative that serves as a baseline for comparison of the potential environmental impacts of the proposed action. Under the No-Action Alternative, the NRC staff would deny renewal of License SUA–1548. After weighing the impacts of the proposed license renewal and comparing to the No-Action Alternative, the NRC staff, in accordance with 10 CFR 51.91(d), sets forth its NEPA recommendation regarding the proposed action (granting the NRC license renewal request for the Smith Ranch Project). Unless safety issues mandate otherwise, the NRC staff recommendation related to the environmental aspects of the proposed action is that a renewed NRC license be issued. The EA for the proposed renewal of License SUA–1548 may be accessed at ADAMS Accession No. ML18257A071. III. Finding of No Significant Impact Based on its review of the proposed action, and in accordance with the PO 00000 Frm 00055 Fmt 4703 Sfmt 4703 48463 requirements in 10 CFR part 51, the NRC staff has determined that renewal of source materials license SUA–1548 for the Smith Ranch Project would not significantly affect the quality of the human environment. In its license renewal request, Cameco proposed increased ground water flowrates at certain of the project properties with previously approved uranium recovery to commence at the Reynolds Ranch satellite and at the Gas Hills remote satellite site. No other significant changes in Cameco’s authorized operations for the Smith Ranch Project were requested. Approval of the proposed action would not result in an increased radiological risk to public health or the environment. The NRC staff has determined that pursuant to 10 CFR 51.31, preparation of an EIS is not required for the proposed action and that, pursuant to 10 CFR 51.32, a FONSI is appropriate. Dated at Rockville, Maryland, this 20th day of September 2018. For the Nuclear Regulatory Commission. Craig G. Erlanger, Director, Division of Fuel Cycle Safety, Safeguards, and Environmental Review, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2018–20793 Filed 9–24–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2018–0208] Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations Nuclear Regulatory Commission. ACTION: Biweekly notice. AGENCY: 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. SUMMARY: E:\FR\FM\25SEN1.SGM 25SEN1 48464 Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices This biweekly notice includes all notices of amendments issued, or proposed to be issued, from August 28, 2018 to September 10, 2018. The last biweekly notice was published on September 11, 2018. DATES: Comments must be filed by October 25, 2018. A request for a hearing must be filed by November 26, 2018. 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 Website: Go to https://www.regulations.gov and search for Docket ID NRC–2018–0208. Address questions about Docket IDs in Regulations.gov to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individual(s) listed in the FOR FURTHER INFORMATION CONTACT section of this document. • Mail comments to: May Ma, Office of Administration, Mail Stop: TWFN–7– A60M, 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: Kay Goldstein, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone: 301–415–1506, email: Kay.Goldstein@nrc.gov. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments daltland on DSKBBV9HB2PROD with NOTICES A. Obtaining Information Please refer to Docket ID NRC–2018– 0208 facility name, unit number(s), plant docket number, application date, and subject when contacting the NRC about the availability of information for this action. You may obtain publiclyavailable information related to this action by any of the following methods: • Federal Rulemaking website: Go to https://www.regulations.gov and search for Docket ID NRC–2018–0208. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact VerDate Sep<11>2014 17:40 Sep 24, 2018 Jkt 244001 the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301– 415–4737, or by email to pdr.resource@ nrc.gov. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. • 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–2018– 0208, facility name, unit number(s), plant docket number, 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 https:// 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 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 § 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. PO 00000 Frm 00056 Fmt 4703 Sfmt 4703 The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination. Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30-day comment period if 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. If the Commission takes 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. If the Commission makes 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. A. Opportunity To Request a Hearing and Petition for Leave To Intervene Within 60 days after the date of publication of this notice, any persons (petitioner) whose interest may be affected by this action may file a request for a hearing and petition for leave to intervene (petition) with respect to the action. Petitions shall be filed in accordance with the Commission’s ‘‘Agency Rules of Practice and Procedure’’ in 10 CFR part 2. Interested persons should consult a current copy of 10 CFR 2.309. The NRC’s regulations are accessible electronically from the NRC Library on the NRC’s website at https://www.nrc.gov/reading-rm/doccollections/cfr/. Alternatively, a copy of the regulations is available at the NRC’s Public Document Room, located at One White Flint North, Room O1–F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. If a petition is filed, the Commission or a presiding officer will rule on the petition and, if appropriate, a notice of a hearing will be issued. As required by 10 CFR 2.309(d) the petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements for standing: (1) The name, address, and E:\FR\FM\25SEN1.SGM 25SEN1 daltland on DSKBBV9HB2PROD with NOTICES Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices telephone number of the petitioner; (2) the nature of the petitioner’s right under the Act to be made a party to the proceeding; (3) the nature and extent of the 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 petitioner’s interest. In accordance with 10 CFR 2.309(f), the petition must also set forth the specific contentions which the petitioner seeks to have litigated in 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 petitioner must 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 petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide references to the specific sources and documents on which the petitioner intends to rely to support its position on the issue. The petition must include sufficient information to show that a genuine dispute exists with the applicant or licensee on a material issue of law or fact. Contentions must be limited to matters within the scope of the proceeding. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to satisfy the requirements at 10 CFR 2.309(f) 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. Parties have the opportunity to participate fully in the conduct of the hearing with respect to resolution of that party’s admitted contentions, including the opportunity to present evidence, consistent with the NRC’s regulations, policies, and procedures. Petitions must be filed no later than 60 days from the date of publication of this notice. Petitions and motions for leave to file new or amended contentions that are filed after the 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) through (iii). The petition must be filed in accordance with the filing instructions in the ‘‘Electronic Submissions (E-Filing)’’ section of this document. If a hearing is requested, and the Commission has not made a final determination on the issue of no significant hazards consideration, the Commission will make a final VerDate Sep<11>2014 17:40 Sep 24, 2018 Jkt 244001 determination on the issue of no significant hazards consideration. The final determination will serve to establish 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 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 the 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. A State, local governmental body, Federally-recognized Indian Tribe, or agency thereof, may submit a petition to the Commission to participate as a party under 10 CFR 2.309(h)(1). The petition should state the nature and extent of the petitioner’s interest in the proceeding. The petition should be submitted to the Commission no later than 60 days from the date of publication of this notice. The petition must be filed in accordance with the filing instructions in the ‘‘Electronic Submissions (E-Filing)’’ section of this document, and should meet the requirements for petitions set forth in this section, except that under 10 CFR 2.309(h)(2) a State, local governmental body, or Federallyrecognized Indian Tribe, or agency thereof does not need to address the standing requirements in 10 CFR 2.309(d) if the facility is located within its boundaries. Alternatively, a State, local governmental body, Federallyrecognized Indian Tribe, or agency thereof may participate as a non-party under 10 CFR 2.315(c). If a hearing is granted, any person who is not a party to the proceeding and is not affiliated with or represented by a party may, at the discretion of the presiding officer, be permitted to make a limited appearance pursuant to the provisions of 10 CFR 2.315(a). A person making a limited appearance may make an oral or written statement of his or her position on the issues but may not otherwise participate in the proceeding. A limited appearance may be made at any session of the hearing or at any prehearing conference, subject to the limits and conditions as may be imposed by the presiding officer. Details regarding the opportunity to make a limited appearance will be provided by the presiding officer if such sessions are scheduled. PO 00000 Frm 00057 Fmt 4703 Sfmt 4703 48465 B. Electronic Submissions (E-Filing) All documents filed in NRC adjudicatory proceedings, including a request for hearing and petition for leave to intervene (petition), 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 that request to participate under 10 CFR 2.315(c), must be filed in accordance with the NRC’s E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR 46562; August 3, 2012). The EFiling process requires participants to submit and serve all adjudicatory documents over the internet, or in some cases to mail copies on electronic storage media. Detailed guidance on making electronic submissions may be found in the Guidance for Electronic Submissions to the NRC and on the NRC website at https://www.nrc.gov/site-help/ e-submittals.html. Participants may not submit paper copies of their filings unless they seek an exemption in accordance with the procedures described below. To comply with the procedural requirements of E-Filing, at least 10 days prior to the filing deadline, the participant should contact the Office of the Secretary by email at hearing.docket@nrc.gov, or by telephone at 301–415–1677, to (1) request a digital identification (ID) certificate, which allows the participant (or its counsel or representative) to digitally sign submissions and access the E-Filing system for any proceeding in which it is participating; and (2) advise the Secretary that the participant will be submitting a petition or other adjudicatory document (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 website at https:// www.nrc.gov/site-help/e-submittals/ getting-started.html. Once a participant has obtained a digital ID certificate and a docket has been created, the participant can then submit adjudicatory documents. Submissions must be in Portable Document Format (PDF). Additional guidance on PDF submissions is available on the NRC’s public website at https://www.nrc.gov/ site-help/electronic-sub-ref-mat.html. A filing is considered complete at the time E:\FR\FM\25SEN1.SGM 25SEN1 daltland on DSKBBV9HB2PROD with NOTICES 48466 Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices the document is 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 EFiling 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 document on those participants separately. Therefore, applicants and other participants (or their counsel or representative) must apply for and receive a digital ID certificate before adjudicatory documents are filed so that they can obtain access to the documents via the E-Filing system. A person filing electronically using the NRC’s adjudicatory E-Filing system may seek assistance by contacting the NRC’s Electronic Filing Help Desk through the ‘‘Contact Us’’ link located on the NRC’s public website at https:// www.nrc.gov/site-help/esubmittals.html, by email to MSHD.Resource@nrc.gov, or by a tollfree call at 1–866–672–7640. The NRC Electronic Filing Help Desk is available between 9 a.m. and 6 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 stating why there is good cause for not filing electronically and 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, 11555 Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and Adjudications Staff. Participants filing adjudicatory documents 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 VerDate Sep<11>2014 17:40 Sep 24, 2018 Jkt 244001 granted an exemption request from using E-Filing, may require a participant or party to use E-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists. Documents submitted in adjudicatory proceedings will appear in the NRC’s electronic hearing docket which is available to the public at https:// adams.nrc.gov/ehd, unless excluded pursuant to an order of the Commission or the presiding officer. If you do not have an NRC-issued digital ID certificate as described above, click cancel when the link requests certificates and you will be automatically directed to the NRC’s electronic hearing dockets where you will be able to access any publicly available documents in a particular hearing docket. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or personal phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. For example, in some instances, individuals provide home addresses in order to demonstrate proximity to a facility or site. 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. 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. Southern Nuclear Operating Company, Inc., Docket Nos. 50–348 and 50–364, Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County, Alabama Date of amendment request: July 27, 2018. A publicly-available version is in ADAMS under Accession No. ML18208A619. Description of amendment request: The proposed amendment would modify Technical Specification requirements to permit use of Risk Informed Completion Times in accordance with NEI 06–09, Revision 0– A, ‘‘Risk-Informed Technical Specifications Initiative 4b, RiskManaged Technical Specifications (RMTS) Guidelines.’’ Basis for proposed no significant hazards consideration determination: PO 00000 Frm 00058 Fmt 4703 Sfmt 4703 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 [change] involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change permits the extension of completion times provided risk is assessed and managed within the Risk Informed Completion Time Program. The proposed change does not involve a significant increase in the probability of an accident previously evaluated because the changes involve no change to the plant or its mode of operation. The proposed change does not increase the consequences of an accident because the design-basis mitigation function of the affected systems is not changed and the consequences of an accident during the extended completion time are no different from those during the existing COMPLETION TIME. 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 TS revision does not change the design, configuration, or method of plant operation. The proposed change does not involve a physical alteration of the plant in that no new or different kind of equipment will be installed. 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 permits the extension of completion times provided risk is assessed and managed within the Risk Informed Completion Time Program. The proposed change implements a risk-informed configuration management program to assure that adequate safety margins are maintained. Application of these new specifications and the configuration management program considers cumulative effects of multiple systems or components being out of service and does so more effectively than the current TS. 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: Millicent Ronnlund, Vice President and General E:\FR\FM\25SEN1.SGM 25SEN1 Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices Counsel, Southern Nuclear Operating Company, Inc., P.O. Box 1295, Birmingham, AL 35201–1295. Southern Nuclear Operating Company, Docket Nos. 52–025 and 52–026, Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia daltland on DSKBBV9HB2PROD with NOTICES Date of amendment request: July 19, 2018. A publicly-available version is in ADAMS under Accession No. ML18200A415. Description of amendment request: The amendment request proposes changes to combined license Appendix C (and plant-specific design control document Tier 1) to revise Inspections, Tests, Analysis, and Acceptance Criteria (ITAAC) related to flow testing of low pressure makeup from the cask loading pit to the reactor coolant system via the normal residual heat removal system (RNS) and RNs pump testing at reduced inventory. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed changes to the RNS ITAAC revise the acceptance criteria for flow testing of low pressure makeup from the CLP [cask loading pit] to the RCS [reactor coolant system] (via RNS) and clarify the acceptance criteria for RNS pump flow testing at reduced inventory. The proposed changes do not have any adverse effects on the design functions of the RNS. The probabilities of accidents evaluated in the UFSAR [Updated Safety Analysis Report] are not affected. The changes do not adversely impact the support, design, or operation of mechanical and fluid systems. The changes do not impact the support, design, or operation of any safety-related structures. There is no change to the plant systems or response of systems to postulated accident conditions. There is no change to the predicted radioactive releases due to normal operation or postulated accident conditions. The plant response to previously evaluated accidents or external events is not adversely affected, nor do the proposed changes create any new accident precursors. Therefore, the requested amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed changes to the RNS ITAAC revise the acceptance criteria for flow testing VerDate Sep<11>2014 17:40 Sep 24, 2018 Jkt 244001 of low pressure makeup from the CLP to the RCS (via RNS) and clarify the acceptance criteria for RNS pump flow testing at reduced inventory. The proposed changes do not have any adverse effects on the design function of the RNS, the structures and systems in which the RNS is used, or any other SSC [structure system or component] design functions or methods of operation that result in a new failure mode, malfunction, or sequence of events that affect safety-related or non-safety related equipment. This activity does not allow for a new fission product release path, result in a new fission product barrier failure mode, or create a new sequence of events that result in significant fuel cladding failures. Therefore, the requested 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. The proposed changes to the RNS ITAAC revise the acceptance criteria for flow testing of low pressure makeup from the CLP to the RCS (via RNS) and clarify the acceptance criteria for RNS pump flow testing at reduced inventory. Because no safety analysis or design basis acceptance limit/criterion is challenged or exceeded by these changes, no significant margin of safety is reduced. Therefore, the proposed changes do 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: M. Stanford Blanton, Balch & Bingham LLP, 1710 Sixth Avenue North, Birmingham, AL 35203–2015. NRC Branch Chief: Jennifer DixonHerrity. Southern Nuclear Operating Company, Docket Nos. 52–025 and 52–026, Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia Date of amendment request: August 10, 2018. A publicly-available version is in ADAMS under Accession No. ML18222A254. Description of amendment request: The requested amendment proposes changes to Combined License Appendix A, Technical Specifications, to change Technical Specifications Limiting Condition for Operation (LCO) 3.1.8, ‘‘Physics Tests Exception—Mode 2,’’ related to Functions of LCO 3.3.1, ‘‘Reactor Trip System (RTS) Instrumentation,’’ for which the required number of channels may be reduced from 4 channels to 3 channels, to include Function 4. Additionally, for LCO 3.8.3, ‘‘Inverters—Operating,’’ the PO 00000 Frm 00059 Fmt 4703 Sfmt 4703 48467 request proposes to make an editorial nomenclature change from ‘‘constant voltage source transformer’’ to ‘‘voltage regulating transformer.’’ Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed changes do not involve changes to current plant design or safety analysis assumptions. These changes provide Technical Specifications consistency with the approved plant design and safety analysis assumptions. The changes do not affect the operation of any systems or equipment that initiate an analyzed accident or alter any structures, systems, and components (SSCs) accident initiator or initiating sequence of events. The proposed changes do not adversely impact the ability of any SSCs provided for, or credited in, mitigating any analyzed accident. Therefore, the requested amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed changes do not involve changes to current plant design or safety analysis assumptions. These changes provide Technical Specifications consistency with the approved plant design and safety analysis assumptions. The proposed changes do not adversely affect plant protection instrumentation systems, and do not affect the design function, support, design, or operation of mechanical and fluid systems. The proposed changes do not result in a new failure mechanism or introduce any new accident precursors. No design function described in the Updated Final Safety Analysis Report (UFSAR) is affected by the proposed changes. Therefore, the requested 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. The proposed changes do not involve changes to current plant design or safety analysis assumptions. These changes provide Technical Specifications consistency with the approved plant design and safety analysis assumptions. No safety analysis or design basis acceptance limit/criterion is involved. Therefore, the proposed amendment does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee’s analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are E:\FR\FM\25SEN1.SGM 25SEN1 48468 Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: M. Stanford Blanton, Balch & Bingham LLP, 1710 Sixth Avenue North, Birmingham, AL 35203–2015. NRC Branch Chief: Jennifer DixonHerrity. daltland on DSKBBV9HB2PROD with NOTICES Southern Nuclear Operating Company, Inc., Docket Nos.: 52–025 and 52–026, Vogtle Electric Generating Plant (VEGP) Units 3 and 4, Burke County, Georgia Date of amendment request: August 3, 2018. A publicly-available version is in ADAMS under Accession No. ML18215A382. Description of amendment request: The requested amendment requires changes to the Updated Final Safety Analysis Report (UFSAR) in the form of departures from the incorporated plantspecific Design Control Document (DCD) Tier 2* and Tier 2 information and related changes to the VEGP Units 3 and 4 Combined License (COL) and COL Appendix C (and corresponding plant-specific DCD Tier 1) information. Specifically, the requested amendment includes changes to credit previously completed first plant only and first three plant only testing as described in the licensing basis documents, including COL Condition 2.D.(2)(a) and plantspecific Tier 1 Section 2.1.3. In particular, the proposed changes would revise the COL to delete conditions requiring the following tests: InContainment Refueling Water Storage Tank (IRWST) Heatup Test, Reactor Vessel Internals Vibration Testing, and Core Makeup Tank (CMT) Heated Recirculation Tests. The documentation to establish a valid prototype reactor internals in accordance with Regulatory Guide 1.20 is also included. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change does not affect the operation of any systems or equipment that initiates an analyzed accident or alter any structures, systems, or components (SSC) accident initiator or initiating sequence of events. The proposed changes remove first plant and first three plant only tests including the IRWST heatup test, reactor vessel internals vibration testing, and CMT recirculation tests based on the successful VerDate Sep<11>2014 17:40 Sep 24, 2018 Jkt 244001 completion of the tests at the lead AP1000 units. The change does not adversely affect any methodology which would increase the probability or consequences of a previously evaluated accident. The change does not impact the support, design, or operation of mechanical or fluid systems. There is no change to plant systems or the response of systems to postulated accident conditions. There is no change to predicted radioactive releases due to normal operation or postulated accident conditions. The plant response to previously evaluated accidents or external events is not adversely affected, nor does the proposed change create any new accident precursors. Therefore, the proposed amendment does not involve a significant increase in the probability or consequences of a previously evaluated accident. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change does not affect the operation of any systems or equipment that may initiate a new or different kind of accident, or alter any SSC such that a new accident initiator or initiating sequence of events is created. The proposed change credits previously completed first plant and first three plant only tests including the IRWST heatup test, reactor vessel internals vibration testing, and CMT recirculation tests based on the successful completion of the tests at the lead AP1000 units. The proposed changes do not adversely affect any design function of any SSC design functions or methods of operation in a manner that results in a new failure mode, malfunction, or sequence of events that affect safety-related or non-safetyrelated equipment. This activity does not allow for a new fission product release path, result in a new fission product barrier failure mode, or create a new sequence of events that result in significant fuel cladding failures. 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. The proposed change maintains existing safety margin and provides adequate protection through continued application of the existing requirement in the UFSAR. The proposed change satisfies the same design functions in accordance with the same codes and standards as stated in the UFSAR. This change does not adversely affect any design code, function, design analysis, safety analysis input or result, or design/safety margin. No safety analysis or design basis acceptance limit/criterion is challenged or exceeded by the proposed change. Since no safety analysis or design basis acceptance limit/criterion is challenged or exceeded by this change, no significant margin of safety is reduced. Therefore, the proposed change does not involve a significant reduction in a margin of safety. PO 00000 Frm 00060 Fmt 4703 Sfmt 4703 The NRC staff has reviewed the licensee’s analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Mr. M. Stanford Blanton, Balch & Bingham LLP, 1710 Sixth Avenue North Birmingham, AL 35203–2015. NRC Branch Chief: Jennifer DixonHerrity. III. 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 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. E:\FR\FM\25SEN1.SGM 25SEN1 Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices Energy Northwest, Docket No. 50–397, Columbia Generating Station, Benton County, Washington Date of amendment request: December 12, 2017. Brief description of amendment: The amendment revised Technical Specification (TS) 3.6.4.1, ‘‘Secondary Containment.’’ The changes are based on Technical Specifications Task Force (TSTF) Traveler TSTF–551, Revision 3, ‘‘Revise Secondary Containment Surveillance Requirements.’’ Date of issuance: September 6, 2018. Effective date: As of its date of issuance and shall be implemented within 60 days from the date of issuance. Amendment No.: 250. A publiclyavailable version is in ADAMS under Accession No. ML18221A107; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. NPF–21: The amendment revised the Renewed Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: March 13, 2018 (83 FR 10915). The Commission’s related evaluation of the amendment is contained in a Safety Evaluation dated September 6, 2018. No significant hazards consideration comments received: No. daltland on DSKBBV9HB2PROD with NOTICES Exelon Generation Company, LLC, Docket No. 50–244, R. E. Ginna Nuclear Power Plant, Wayne County, New York Date of amendment request: October 31, 2017. Brief description of amendment: The amendment revised Technical Specification (TS) Surveillance Requirement 3.8.4.3, ‘‘DC [Direct Current] Sources—MODES 1, 2, 3, and 4,’’ to allow for a modified performance discharge test. Date of issuance: August 31, 2018. Effective date: As of the date of issuance and shall be implemented within 60 days of issuance. Amendment No.: 130. A publiclyavailable version is in ADAMS under Accession No. ML18214A176; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR–18: Amendment revised the Renewed Facility Operating License and TS. Date of initial notice in Federal Register: January 2, 2018 (83 FR 168). The Commission’s related evaluation of the amendment is contained in a VerDate Sep<11>2014 17:40 Sep 24, 2018 Jkt 244001 Safety Evaluation dated August 31, 2018. No significant hazards consideration comments received: No. Nebraska Public Power District, Docket No. 50–298, Cooper Nuclear Station (CNS), Nemaha County, Nebraska Date of amendment request: May 10, 2018. Brief description of amendment: The amendment modified CNS Technical Specification 2.1.1.2 by revising the values of the safety limit minimum critical power ratio for two recirculation loop operation and for single recirculation loop operation to reflect the results of a cycle-specific calculation. Date of issuance: September 6, 2018. Effective date: As of the date of issuance and shall be implemented prior to startup from Refuel Outage 30. Amendment No.: 261. A publiclyavailable version is in ADAMS under Accession No. ML18218A483; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR–46: The amendment revised the Renewed Facility Operating License and Technical Specifications. Date of initial notice in Federal Register: July 2, 2018 (83 FR 30984). The Commission’s related evaluation of the amendment is contained in a Safety Evaluation dated September 6, 2018. No significant hazards consideration comments received: No. 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 amendment request: July 10, 2017. A publicly-available version is in ADAMS under Accession No. ML17191B163. Brief description of amendments: The amendments revise the Technical Specifications (TSs) by: (1) Adding a Note to the Surveillance Requirements (SRs) of TS 3.7.7 to clarify that the SRs are not required to be met when the Limiting Condition for Operation (LCO) does not require the Main Turbine Bypass System to be operable; (2) clarifying that LCO 3.2.3, ‘‘LINEAR HEAT GENERATION RATE,’’ also has limits for an inoperable Main Turbine Bypass System that are made applicable as specified in the Core Operating PO 00000 Frm 00061 Fmt 4703 Sfmt 4703 48469 Limits Report; and (3) deleting an outdated footnote for LCO 3.2.3. Date of issuance: August 29, 2018. Effective date: As of the date of issuance and shall be implemented within 90 days from the date of issuance. Amendment Nos.: Unit 1—292, Unit 2—237. A publicly-available version is in ADAMS under Accession No. ML18222A296; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR–57 and NPF–5: Amendments revised the Renewed Facility Operating Licenses and Technical Specifications. Date of initial notice in Federal Register: November 21, 2017 (82 FR 55412). The Commission’s related evaluation of the amendments is contained in a Safety Evaluation dated August 29, 2018. No significant hazards consideration comments received: No. Southern Nuclear Operating Company, Docket Nos. 52–025 and 52–026, Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County, Georgia Date of amendment request: January 31, 2018, as supplemented by letters dated April 25, and June 21, 2018. Description of amendment: The amendments make changes to the VEGP Units 3 and 4 Combined Operating License (COL) in the form of departure from the approved COL Appendix A, Technical Specifications. The amendments make changes to COL Appendix A, Surveillance Requirement 3.8.7.6 to align the test frequency with the expected life of the AP1000 Class 1E batteries. Date of issuance: The amendments were issued on July 26, 2018. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment Nos.: 135 (Unit 3) and 134 (Unit 4). A publicly-available version is in ADAMS under Accession No. ML18173A301; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Combined Licenses Nos. NPF– 91 and NPF–92: Amendment revised the Facility Combined License. Date of initial notice in Federal Register: April 24, 2018 (83 FR 17858). The supplements dated April 25, 2018 and June 21, 2018, 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 E:\FR\FM\25SEN1.SGM 25SEN1 48470 Federal Register / Vol. 83, No. 186 / Tuesday, September 25, 2018 / Notices original proposed no significant hazards consideration determination. The Commission’s related evaluation of the amendment is contained in the Safety Evaluation dated July 26, 2018. No significant hazards consideration comments received: No. daltland on DSKBBV9HB2PROD with NOTICES Southern Nuclear Operating Company, Docket Nos. 52–025 and 52–026, Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County, Georgia Date of amendment request: June 15, 2018 and supplemented on June 25, 2018 and July 10, 2018. Description of amendment: The amendment revises commitments related to the construction fitness-forduty (FFD) program described in the VEGP Units 3 and 4 Updated Final Safety Analysis Report. Specifically, the change involves the creation of a new type of FFD Authorization that allows construction workers temporary access to the construction site pending completion of all pre-access FFD requirements. The individuals will not be given assignments to work on safety or security-related structures, systems, and components prior to the completion of the FFD requirements. Date of issuance: August 29, 2018. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment Nos.: 141 (Unit 3) and 140 (Unit 4). A publicly-available version is in ADAMS under Accession No. ML18214A659; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Combined Licenses No. NPF– 91 and NPF–92: Amendment revised the Facility Combined Licenses. Date of initial notice in Federal Register: June 27, 2018 (83 FR 30199). The supplements dated June 25, 2018, and July 10, 2018, 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 the Safety Evaluation dated August 29, 2018. No significant hazards consideration comments received: No. VerDate Sep<11>2014 17:40 Sep 24, 2018 Jkt 244001 Tennessee Valley Authority (TVA) Docket Nos. 50–327 and 50–328, Sequoyah Nuclear Plant (SQN), Units 1 and 2, Hamilton County, Tennessee TVA Docket Nos. 50–390 and 50–391, Watts Bar Nuclear Plant (WBN), Units 1 and 2, Rhea County, Tennessee Date of amendment request: August 7, 2017. Brief description of amendments: The amendments revised technical specifications (TSs) limiting conditions for operation and surveillance requirements related to the reactor trip system instrumentation for all four units. Date of issuance: August 30, 2018. Effective date: As of the date of issuance and shall be implemented in 30 days. Amendment Nos.: SQN, 343 (Unit 1) and 336 (Unit 2); and WBN, 122 (Unit 1) and 21 (Unit 2). A publicly-available version is in ADAMS under Accession No. ML18197A307; documents related to these amendments are listed in the Safety Evaluation (SE) enclosed with the amendments. Renewed Facility Operating License Nos. DPR–77, DPR–79 and Facility Operating License Nos, NPF–90 and NPF–96: Amendments revised the Facility Operating Licenses and TSs. Date of initial notice in Federal Register: November 21, 2017 (82 FR 55416). The Commission’s related evaluation of the amendments is contained in SE dated August 30, 2018. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, on September 14, 2018. For the Nuclear Regulatory Commission. Kathryn M. Brock, Acting Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2018–20333 Filed 9–24–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2018–0001] Sunshine Act Meetings Weeks of September 24, October 1, 8, 15, 22, 29, 2018. PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and closed. MATTERS TO BE CONSIDERED: TIME AND DATE: PO 00000 Frm 00062 Fmt 4703 Sfmt 4703 Week of September 24, 2018 Thursday, September 27, 2018 10:00 a.m. Strategic Programmatic Overview of the Operating Reactors Business Line (Public) (Contact: Trent Wertz: 301–415–1568). This meeting will be webcast live at the Web address—https://www.nrc.gov/. Week of October 1, 2018—Tentative There are no meetings scheduled for the week of October 1, 2018. Week of October 8, 2018—Tentative Thursday, October 11, 2018 9:00 a.m. Strategic Programmatic Overview of the Decommissioning and Low-Level Waste and Spent Fuel Storage and Transportation Business Lines (Public) (Contact: Matthew Meyer: 301–415–6198). This meeting will be webcast live at the Web address—https://www.nrc.gov/. Week of October 15, 2018—Tentative There are no meetings scheduled for the week of October 15, 2018. Week of October 22, 2018—Tentative Thursday, October 25, 2018 9:00 a.m. Briefing on Digital Instrumentation and Control (Public) (Contact: Jason Paige: 301– 415–1474). This meeting will be webcast live at the Web address—https://www.nrc.gov/. Week of October 29, 2018—Tentative There are no meetings scheduled for the week of October 29, 2018. CONTACT PERSON FOR MORE INFORMATION: For more information or to verify the status of meetings, contact Denise McGovern at 301–415–0681 or via email at Denise.McGovern@nrc.gov. The schedule for Commission meetings is subject to change on short notice. The NRC Commission Meeting Schedule can be found on the internet at: https://www.nrc.gov/public-involve/ public-meetings/schedule.html. The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a reasonable accommodation to participate in these public meetings, or need this meeting notice or the transcript or other information from the public meetings in another format (e.g., braille, large print), please notify Kimberly Meyer-Chambers, NRC Disability Program Manager, at 301– 287–0739, by videophone at 240–428– 3217, or by email at Kimberly.MeyerChambers@nrc.gov. Determinations on requests for reasonable accommodation will be made on a case-by-case basis. E:\FR\FM\25SEN1.SGM 25SEN1

Agencies

NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 83, Number 186 (Tuesday, September 25, 2018)]
[Notices]
[Pages 48463-48470]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-20333]


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NUCLEAR REGULATORY COMMISSION

[NRC-2018-0208]


Biweekly Notice; Applications and Amendments to Facility 
Operating Licenses and Combined Licenses Involving No Significant 
Hazards Considerations

AGENCY: Nuclear Regulatory Commission.

ACTION: Biweekly notice.

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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.

[[Page 48464]]

    This biweekly notice includes all notices of amendments issued, or 
proposed to be issued, from August 28, 2018 to September 10, 2018. The 
last biweekly notice was published on September 11, 2018.

DATES: Comments must be filed by October 25, 2018. A request for a 
hearing must be filed by November 26, 2018.

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 Website: Go to https://www.regulations.gov and search for Docket ID NRC-2018-0208. Address 
questions about Docket IDs in Regulations.gov to Jennifer Borges; 
telephone: 301-287-9127; email: [email protected]. For technical 
questions, contact the individual(s) listed in the FOR FURTHER 
INFORMATION CONTACT section of this document.
     Mail comments to: May Ma, Office of Administration, Mail 
Stop: TWFN-7-A60M, 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: Kay Goldstein, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-1506, email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2018-0208 facility name, unit 
number(s), plant docket number, application date, and subject 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 website: Go to https://www.regulations.gov and search for Docket ID NRC-2018-0208.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, 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 this document.
     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-2018-0208, facility name, unit 
number(s), plant docket number, 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 https://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 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 Sec.  50.92 of title 10 of the Code of 
Federal Regulations (10 CFR), this means that operation of the facility 
in accordance with the proposed amendment would not (1) involve a 
significant increase in the probability or consequences of an accident 
previously evaluated, or (2) create the possibility of a new or 
different kind of accident from any accident previously evaluated; or 
(3) involve a significant reduction in a margin of safety. The basis 
for this proposed determination for each amendment request is shown 
below.
    The Commission is seeking public comments on this proposed 
determination. Any comments received within 30 days after the date of 
publication of this notice will be considered in making any final 
determination.
    Normally, the Commission will not issue the amendment until the 
expiration of 60 days after the date of publication of this notice. The 
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment 
involves no significant hazards consideration. In addition, the 
Commission may issue the amendment prior to the expiration of the 30-
day comment period if 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. If the Commission 
takes 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. If the Commission makes 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.

A. Opportunity To Request a Hearing and Petition for Leave To Intervene

    Within 60 days after the date of publication of this notice, any 
persons (petitioner) whose interest may be affected by this action may 
file a request for a hearing and petition for leave to intervene 
(petition) with respect to the action. Petitions shall be filed in 
accordance with the Commission's ``Agency Rules of Practice and 
Procedure'' in 10 CFR part 2. Interested persons should consult a 
current copy of 10 CFR 2.309. The NRC's regulations are accessible 
electronically from the NRC Library on the NRC's website at https://www.nrc.gov/reading-rm/doc-collections/cfr/. Alternatively, a copy of 
the regulations is available at the NRC's Public Document Room, located 
at One White Flint North, Room O1-F21, 11555 Rockville Pike (first 
floor), Rockville, Maryland 20852. If a petition is filed, the 
Commission or a presiding officer will rule on the petition and, if 
appropriate, a notice of a hearing will be issued.
    As required by 10 CFR 2.309(d) the petition should specifically 
explain the reasons why intervention should be permitted with 
particular reference to the following general requirements for 
standing: (1) The name, address, and

[[Page 48465]]

telephone number of the petitioner; (2) the nature of the petitioner's 
right under the Act to be made a party to the proceeding; (3) the 
nature and extent of the 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 petitioner's 
interest.
    In accordance with 10 CFR 2.309(f), the petition must also set 
forth the specific contentions which the petitioner seeks to have 
litigated in 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 petitioner must 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 petitioner 
intends to rely in proving the contention at the hearing. The 
petitioner must also provide references to the specific sources and 
documents on which the petitioner intends to rely to support its 
position on the issue. The petition must include sufficient information 
to show that a genuine dispute exists with the applicant or licensee on 
a material issue of law or fact. Contentions must be limited to matters 
within the scope of the proceeding. The contention must be one which, 
if proven, would entitle the petitioner to relief. A petitioner who 
fails to satisfy the requirements at 10 CFR 2.309(f) 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. 
Parties have the opportunity to participate fully in the conduct of the 
hearing with respect to resolution of that party's admitted 
contentions, including the opportunity to present evidence, consistent 
with the NRC's regulations, policies, and procedures.
    Petitions must be filed no later than 60 days from the date of 
publication of this notice. Petitions and motions for leave to file new 
or amended contentions that are filed after the 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) through (iii). The petition must be filed in 
accordance with the filing instructions in the ``Electronic Submissions 
(E-Filing)'' section of this document.
    If a hearing is requested, and the Commission has not made a final 
determination on the issue of no significant hazards consideration, the 
Commission will make a final determination on the issue of no 
significant hazards consideration. The final determination will serve 
to establish 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 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 the 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.
    A State, local governmental body, Federally-recognized Indian 
Tribe, or agency thereof, may submit a petition to the Commission to 
participate as a party under 10 CFR 2.309(h)(1). The petition should 
state the nature and extent of the petitioner's interest in the 
proceeding. The petition should be submitted to the Commission no later 
than 60 days from the date of publication of this notice. The petition 
must be filed in accordance with the filing instructions in the 
``Electronic Submissions (E-Filing)'' section of this document, and 
should meet the requirements for petitions set forth in this section, 
except that under 10 CFR 2.309(h)(2) a State, local governmental body, 
or Federally-recognized Indian Tribe, or agency thereof does not need 
to address the standing requirements in 10 CFR 2.309(d) if the facility 
is located within its boundaries. Alternatively, a State, local 
governmental body, Federally-recognized Indian Tribe, or agency thereof 
may participate as a non-party under 10 CFR 2.315(c).
    If a hearing is granted, any person who is not a party to the 
proceeding and is not affiliated with or represented by a party may, at 
the discretion of the presiding officer, be permitted to make a limited 
appearance pursuant to the provisions of 10 CFR 2.315(a). A person 
making a limited appearance may make an oral or written statement of 
his or her position on the issues but may not otherwise participate in 
the proceeding. A limited appearance may be made at any session of the 
hearing or at any prehearing conference, subject to the limits and 
conditions as may be imposed by the presiding officer. Details 
regarding the opportunity to make a limited appearance will be provided 
by the presiding officer if such sessions are scheduled.

B. Electronic Submissions (E-Filing)

    All documents filed in NRC adjudicatory proceedings, including a 
request for hearing and petition for leave to intervene (petition), 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 that request to 
participate under 10 CFR 2.315(c), must be filed in accordance with the 
NRC's E-Filing rule (72 FR 49139; August 28, 2007, as amended at 77 FR 
46562; August 3, 2012). 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. Detailed 
guidance on making electronic submissions may be found in the Guidance 
for Electronic Submissions to the NRC and on the NRC website at https://www.nrc.gov/site-help/e-submittals.html. 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 (1) request a digital identification (ID) 
certificate, which allows the participant (or its counsel or 
representative) to digitally sign submissions and access the E-Filing 
system for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a petition or 
other adjudicatory document (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 website at https://www.nrc.gov/site-help/e-submittals/getting-started.html. Once a participant has obtained a 
digital ID certificate and a docket has been created, the participant 
can then submit adjudicatory documents. Submissions must be in Portable 
Document Format (PDF). Additional guidance on PDF submissions is 
available on the NRC's public website at https://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the 
time

[[Page 48466]]

the document is 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 
document on those participants separately. Therefore, applicants and 
other participants (or their counsel or representative) must apply for 
and receive a digital ID certificate before adjudicatory documents are 
filed so that they can obtain access to the documents via the E-Filing 
system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC's Electronic 
Filing Help Desk through the ``Contact Us'' link located on the NRC's 
public website at https://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 Electronic Filing Help Desk is available between 9 a.m. 
and 6 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 
stating why there is good cause for not filing electronically and 
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, 11555 
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and 
Adjudications Staff. Participants filing adjudicatory documents in this 
manner are responsible for serving the document on all other 
participants. Filing is considered complete by first-class mail as of 
the time of deposit in the mail, or by courier, express mail, or 
expedited delivery service upon depositing the document with the 
provider of the service. A presiding officer, having granted an 
exemption request from using E-Filing, may require a participant or 
party to use E-Filing if the presiding officer subsequently determines 
that the reason for granting the exemption from use of E-Filing no 
longer exists.
    Documents submitted in adjudicatory proceedings will appear in the 
NRC's electronic hearing docket which is available to the public at 
https://adams.nrc.gov/ehd, unless excluded pursuant to an order of the 
Commission or the presiding officer. If you do not have an NRC-issued 
digital ID certificate as described above, click cancel when the link 
requests certificates and you will be automatically directed to the 
NRC's electronic hearing dockets where you will be able to access any 
publicly available documents in a particular hearing docket. 
Participants are requested not to include personal privacy information, 
such as social security numbers, home addresses, or personal phone 
numbers in their filings, unless an NRC regulation or other law 
requires submission of such information. For example, in some 
instances, individuals provide home addresses in order to demonstrate 
proximity to a facility or site. 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.
    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.

Southern Nuclear Operating Company, Inc., Docket Nos. 50-348 and 50-
364, Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County, 
Alabama

    Date of amendment request: July 27, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18208A619.
    Description of amendment request: The proposed amendment would 
modify Technical Specification requirements to permit use of Risk 
Informed Completion Times in accordance with NEI 06-09, Revision 0-A, 
``Risk-Informed Technical Specifications Initiative 4b, Risk-Managed 
Technical Specifications (RMTS) Guidelines.''
    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 [change] involve a significant 
increase in the probability or consequences of an accident 
previously evaluated?
    Response: No.
    The proposed change permits the extension of completion times 
provided risk is assessed and managed within the Risk Informed 
Completion Time Program. The proposed change does not involve a 
significant increase in the probability of an accident previously 
evaluated because the changes involve no change to the plant or its 
mode of operation. The proposed change does not increase the 
consequences of an accident because the design-basis mitigation 
function of the affected systems is not changed and the consequences 
of an accident during the extended completion time are no different 
from those during the existing COMPLETION TIME.
    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 TS revision does not change the design, 
configuration, or method of plant operation. The proposed change 
does not involve a physical alteration of the plant in that no new 
or different kind of equipment will be installed.
    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 permits the extension of completion times 
provided risk is assessed and managed within the Risk Informed 
Completion Time Program. The proposed change implements a risk-
informed configuration management program to assure that adequate 
safety margins are maintained. Application of these new 
specifications and the configuration management program considers 
cumulative effects of multiple systems or components being out of 
service and does so more effectively than the current TS.
    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: Millicent Ronnlund, Vice President and 
General

[[Page 48467]]

Counsel, Southern Nuclear Operating Company, Inc., P.O. Box 1295, 
Birmingham, AL 35201-1295.

Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia

    Date of amendment request: July 19, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18200A415.
    Description of amendment request: The amendment request proposes 
changes to combined license Appendix C (and plant-specific design 
control document Tier 1) to revise Inspections, Tests, Analysis, and 
Acceptance Criteria (ITAAC) related to flow testing of low pressure 
makeup from the cask loading pit to the reactor coolant system via the 
normal residual heat removal system (RNS) and RNs pump testing at 
reduced inventory.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed changes to the RNS ITAAC revise the acceptance 
criteria for flow testing of low pressure makeup from the CLP [cask 
loading pit] to the RCS [reactor coolant system] (via RNS) and 
clarify the acceptance criteria for RNS pump flow testing at reduced 
inventory. The proposed changes do not have any adverse effects on 
the design functions of the RNS. The probabilities of accidents 
evaluated in the UFSAR [Updated Safety Analysis Report] are not 
affected.
    The changes do not adversely impact the support, design, or 
operation of mechanical and fluid systems. The changes do not impact 
the support, design, or operation of any safety-related structures. 
There is no change to the plant systems or response of systems to 
postulated accident conditions. There is no change to the predicted 
radioactive releases due to normal operation or postulated accident 
conditions. The plant response to previously evaluated accidents or 
external events is not adversely affected, nor do the proposed 
changes create any new accident precursors.
    Therefore, the requested amendment does not involve a 
significant increase in the probability or consequences of an 
accident previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed changes to the RNS ITAAC revise the acceptance 
criteria for flow testing of low pressure makeup from the CLP to the 
RCS (via RNS) and clarify the acceptance criteria for RNS pump flow 
testing at reduced inventory. The proposed changes do not have any 
adverse effects on the design function of the RNS, the structures 
and systems in which the RNS is used, or any other SSC [structure 
system or component] design functions or methods of operation that 
result in a new failure mode, malfunction, or sequence of events 
that affect safety-related or non-safety related equipment. This 
activity does not allow for a new fission product release path, 
result in a new fission product barrier failure mode, or create a 
new sequence of events that result in significant fuel cladding 
failures.
    Therefore, the requested 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.
    The proposed changes to the RNS ITAAC revise the acceptance 
criteria for flow testing of low pressure makeup from the CLP to the 
RCS (via RNS) and clarify the acceptance criteria for RNS pump flow 
testing at reduced inventory.
    Because no safety analysis or design basis acceptance limit/
criterion is challenged or exceeded by these changes, no significant 
margin of safety is reduced. Therefore, the proposed changes do 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: M. Stanford Blanton, Balch & Bingham LLP, 
1710 Sixth Avenue North, Birmingham, AL 35203-2015.
    NRC Branch Chief: Jennifer Dixon-Herrity.

Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia

    Date of amendment request: August 10, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18222A254.
    Description of amendment request: The requested amendment proposes 
changes to Combined License Appendix A, Technical Specifications, to 
change Technical Specifications Limiting Condition for Operation (LCO) 
3.1.8, ``Physics Tests Exception--Mode 2,'' related to Functions of LCO 
3.3.1, ``Reactor Trip System (RTS) Instrumentation,'' for which the 
required number of channels may be reduced from 4 channels to 3 
channels, to include Function 4. Additionally, for LCO 3.8.3, 
``Inverters--Operating,'' the request proposes to make an editorial 
nomenclature change from ``constant voltage source transformer'' to 
``voltage regulating transformer.''
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed changes do not involve changes to current plant 
design or safety analysis assumptions. These changes provide 
Technical Specifications consistency with the approved plant design 
and safety analysis assumptions. The changes do not affect the 
operation of any systems or equipment that initiate an analyzed 
accident or alter any structures, systems, and components (SSCs) 
accident initiator or initiating sequence of events. The proposed 
changes do not adversely impact the ability of any SSCs provided 
for, or credited in, mitigating any analyzed accident. Therefore, 
the requested amendment does not involve a significant increase in 
the probability or consequences of an accident previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed changes do not involve changes to current plant 
design or safety analysis assumptions. These changes provide 
Technical Specifications consistency with the approved plant design 
and safety analysis assumptions. The proposed changes do not 
adversely affect plant protection instrumentation systems, and do 
not affect the design function, support, design, or operation of 
mechanical and fluid systems. The proposed changes do not result in 
a new failure mechanism or introduce any new accident precursors. No 
design function described in the Updated Final Safety Analysis 
Report (UFSAR) is affected by the proposed changes. Therefore, the 
requested 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.
    The proposed changes do not involve changes to current plant 
design or safety analysis assumptions. These changes provide 
Technical Specifications consistency with the approved plant design 
and safety analysis assumptions. No safety analysis or design basis 
acceptance limit/criterion is involved. Therefore, the proposed 
amendment does not involve a significant reduction in a margin of 
safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are

[[Page 48468]]

satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: M. Stanford Blanton, Balch & Bingham LLP, 
1710 Sixth Avenue North, Birmingham, AL 35203-2015.
    NRC Branch Chief: Jennifer Dixon-Herrity.

Southern Nuclear Operating Company, Inc., Docket Nos.: 52-025 and 52-
026, Vogtle Electric Generating Plant (VEGP) Units 3 and 4, Burke 
County, Georgia

    Date of amendment request: August 3, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18215A382.
    Description of amendment request: The requested amendment requires 
changes to the Updated Final Safety Analysis Report (UFSAR) in the form 
of departures from the incorporated plant-specific Design Control 
Document (DCD) Tier 2* and Tier 2 information and related changes to 
the VEGP Units 3 and 4 Combined License (COL) and COL Appendix C (and 
corresponding plant-specific DCD Tier 1) information. Specifically, the 
requested amendment includes changes to credit previously completed 
first plant only and first three plant only testing as described in the 
licensing basis documents, including COL Condition 2.D.(2)(a) and 
plant-specific Tier 1 Section 2.1.3. In particular, the proposed 
changes would revise the COL to delete conditions requiring the 
following tests: In-Containment Refueling Water Storage Tank (IRWST) 
Heatup Test, Reactor Vessel Internals Vibration Testing, and Core 
Makeup Tank (CMT) Heated Recirculation Tests. The documentation to 
establish a valid prototype reactor internals in accordance with 
Regulatory Guide 1.20 is also included.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change does not affect the operation of any systems 
or equipment that initiates an analyzed accident or alter any 
structures, systems, or components (SSC) accident initiator or 
initiating sequence of events. The proposed changes remove first 
plant and first three plant only tests including the IRWST heatup 
test, reactor vessel internals vibration testing, and CMT 
recirculation tests based on the successful completion of the tests 
at the lead AP1000 units. The change does not adversely affect any 
methodology which would increase the probability or consequences of 
a previously evaluated accident.
    The change does not impact the support, design, or operation of 
mechanical or fluid systems. There is no change to plant systems or 
the response of systems to postulated accident conditions. There is 
no change to predicted radioactive releases due to normal operation 
or postulated accident conditions. The plant response to previously 
evaluated accidents or external events is not adversely affected, 
nor does the proposed change create any new accident precursors.
    Therefore, the proposed amendment does not involve a significant 
increase in the probability or consequences of a previously 
evaluated accident.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed change does not affect the operation of any systems 
or equipment that may initiate a new or different kind of accident, 
or alter any SSC such that a new accident initiator or initiating 
sequence of events is created.
    The proposed change credits previously completed first plant and 
first three plant only tests including the IRWST heatup test, 
reactor vessel internals vibration testing, and CMT recirculation 
tests based on the successful completion of the tests at the lead 
AP1000 units. The proposed changes do not adversely affect any 
design function of any SSC design functions or methods of operation 
in a manner that results in a new failure mode, malfunction, or 
sequence of events that affect safety-related or non-safety-related 
equipment. This activity does not allow for a new fission product 
release path, result in a new fission product barrier failure mode, 
or create a new sequence of events that result in significant fuel 
cladding failures.
    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.
    The proposed change maintains existing safety margin and 
provides adequate protection through continued application of the 
existing requirement in the UFSAR. The proposed change satisfies the 
same design functions in accordance with the same codes and 
standards as stated in the UFSAR. This change does not adversely 
affect any design code, function, design analysis, safety analysis 
input or result, or design/safety margin. No safety analysis or 
design basis acceptance limit/criterion is challenged or exceeded by 
the proposed change.
    Since no safety analysis or design basis acceptance limit/
criterion is challenged or exceeded by this change, no significant 
margin of safety is reduced.
    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: Mr. M. Stanford Blanton, Balch & Bingham 
LLP, 1710 Sixth Avenue North Birmingham, AL 35203-2015.
    NRC Branch Chief: Jennifer Dixon-Herrity.

III. 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 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.

[[Page 48469]]

Energy Northwest, Docket No. 50-397, Columbia Generating Station, 
Benton County, Washington

    Date of amendment request: December 12, 2017.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) 3.6.4.1, ``Secondary Containment.'' The changes are 
based on Technical Specifications Task Force (TSTF) Traveler TSTF-551, 
Revision 3, ``Revise Secondary Containment Surveillance Requirements.''
    Date of issuance: September 6, 2018.
    Effective date: As of its date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment No.: 250. A publicly-available version is in ADAMS under 
Accession No. ML18221A107; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-21: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: March 13, 2018 (83 FR 
10915).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated September 6, 2018.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket No. 50-244, R. E. Ginna Nuclear 
Power Plant, Wayne County, New York

    Date of amendment request: October 31, 2017.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) Surveillance Requirement 3.8.4.3, ``DC [Direct 
Current] Sources--MODES 1, 2, 3, and 4,'' to allow for a modified 
performance discharge test.
    Date of issuance: August 31, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment No.: 130. A publicly-available version is in ADAMS under 
Accession No. ML18214A176; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-18: Amendment revised 
the Renewed Facility Operating License and TS.
    Date of initial notice in Federal Register: January 2, 2018 (83 FR 
168).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated August 31, 2018.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: May 10, 2018.
    Brief description of amendment: The amendment modified CNS 
Technical Specification 2.1.1.2 by revising the values of the safety 
limit minimum critical power ratio for two recirculation loop operation 
and for single recirculation loop operation to reflect the results of a 
cycle-specific calculation.
    Date of issuance: September 6, 2018.
    Effective date: As of the date of issuance and shall be implemented 
prior to startup from Refuel Outage 30.
    Amendment No.: 261. A publicly-available version is in ADAMS under 
Accession No. ML18218A483; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-46: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: July 2, 2018 (83 FR 
30984).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated September 6, 2018.
    No significant hazards consideration comments received: No.

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 amendment request: July 10, 2017. A publicly-available 
version is in ADAMS under Accession No. ML17191B163.
    Brief description of amendments: The amendments revise the 
Technical Specifications (TSs) by: (1) Adding a Note to the 
Surveillance Requirements (SRs) of TS 3.7.7 to clarify that the SRs are 
not required to be met when the Limiting Condition for Operation (LCO) 
does not require the Main Turbine Bypass System to be operable; (2) 
clarifying that LCO 3.2.3, ``LINEAR HEAT GENERATION RATE,'' also has 
limits for an inoperable Main Turbine Bypass System that are made 
applicable as specified in the Core Operating Limits Report; and (3) 
deleting an outdated footnote for LCO 3.2.3.
    Date of issuance: August 29, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment Nos.: Unit 1--292, Unit 2--237. A publicly-available 
version is in ADAMS under Accession No. ML18222A296; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-57 and NPF-5: 
Amendments revised the Renewed Facility Operating Licenses and 
Technical Specifications.
    Date of initial notice in Federal Register: November 21, 2017 (82 
FR 55412).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated August 29, 2018.
    No significant hazards consideration comments received: No.

Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County, 
Georgia

    Date of amendment request: January 31, 2018, as supplemented by 
letters dated April 25, and June 21, 2018.
    Description of amendment: The amendments make changes to the VEGP 
Units 3 and 4 Combined Operating License (COL) in the form of departure 
from the approved COL Appendix A, Technical Specifications. The 
amendments make changes to COL Appendix A, Surveillance Requirement 
3.8.7.6 to align the test frequency with the expected life of the 
AP1000 Class 1E batteries.
    Date of issuance: The amendments were issued on July 26, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 135 (Unit 3) and 134 (Unit 4). A publicly-available 
version is in ADAMS under Accession No. ML18173A301; documents related 
to this amendment are listed in the Safety Evaluation enclosed with the 
amendment.
    Facility Combined Licenses Nos. NPF-91 and NPF-92: Amendment 
revised the Facility Combined License.
    Date of initial notice in Federal Register: April 24, 2018 (83 FR 
17858). The supplements dated April 25, 2018 and June 21, 2018, 
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

[[Page 48470]]

original proposed no significant hazards consideration determination.
    The Commission's related evaluation of the amendment is contained 
in the Safety Evaluation dated July 26, 2018.
    No significant hazards consideration comments received: No.

Southern Nuclear Operating Company, Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant (VEGP), Units 3 and 4, Burke County, 
Georgia

    Date of amendment request: June 15, 2018 and supplemented on June 
25, 2018 and July 10, 2018.
    Description of amendment: The amendment revises commitments related 
to the construction fitness-for-duty (FFD) program described in the 
VEGP Units 3 and 4 Updated Final Safety Analysis Report. Specifically, 
the change involves the creation of a new type of FFD Authorization 
that allows construction workers temporary access to the construction 
site pending completion of all pre-access FFD requirements. The 
individuals will not be given assignments to work on safety or 
security-related structures, systems, and components prior to the 
completion of the FFD requirements.
    Date of issuance: August 29, 2018.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 141 (Unit 3) and 140 (Unit 4). A publicly-available 
version is in ADAMS under Accession No. ML18214A659; documents related 
to this amendment are listed in the Safety Evaluation enclosed with the 
amendment.
    Facility Combined Licenses No. NPF-91 and NPF-92: Amendment revised 
the Facility Combined Licenses.
    Date of initial notice in Federal Register: June 27, 2018 (83 FR 
30199). The supplements dated June 25, 2018, and July 10, 2018, 
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 the Safety Evaluation dated August 29, 2018.
    No significant hazards consideration comments received: No.

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

TVA Docket Nos. 50-390 and 50-391, Watts Bar Nuclear Plant (WBN), Units 
1 and 2, Rhea County, Tennessee

    Date of amendment request: August 7, 2017.
    Brief description of amendments: The amendments revised technical 
specifications (TSs) limiting conditions for operation and surveillance 
requirements related to the reactor trip system instrumentation for all 
four units.
    Date of issuance: August 30, 2018.
    Effective date: As of the date of issuance and shall be implemented 
in 30 days.
    Amendment Nos.: SQN, 343 (Unit 1) and 336 (Unit 2); and WBN, 122 
(Unit 1) and 21 (Unit 2). A publicly-available version is in ADAMS 
under Accession No. ML18197A307; documents related to these amendments 
are listed in the Safety Evaluation (SE) enclosed with the amendments.
    Renewed Facility Operating License Nos. DPR-77, DPR-79 and Facility 
Operating License Nos, NPF-90 and NPF-96: Amendments revised the 
Facility Operating Licenses and TSs.
    Date of initial notice in Federal Register: November 21, 2017 (82 
FR 55416).
    The Commission's related evaluation of the amendments is contained 
in SE dated August 30, 2018.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, on September 14, 2018.

    For the Nuclear Regulatory Commission.
Kathryn M. Brock,
Acting Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2018-20333 Filed 9-24-18; 8:45 am]
 BILLING CODE 7590-01-P

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