Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information, 26112-26119 [2018-10982]

Download as PDF 26112 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices of components evaluated by a cumulative usage factor calculation in accordance with the fatigue design provisions in Section III, ‘‘Rules for Construction of Nuclear Power Plant Components,’’ of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code to account for the effects of LWR water environments. The NRC is issuing Revision 1 of RG 1.207 concurrently with Revision 1 of NUREG/CR–6909 under a separate notice associated with Docket ID NRC– 2014–0244. The NRC notes that Revision 1 of RG 1.207 was issued in draft form as a draft RG (DG–1309). The NRC published a notice of the availability of DG–1309 in the Federal Register on November 24, 2014 (79 FR 69884), under Docket ID NRC–2014–0244, with a public comment period that closed on January 24, 2015. Public comments on DG–1309 and the NRC staff’s responses are available in ADAMS under Accession No. ML16315A127. Dated at Rockville, Maryland, this 30th day of May 2018. For the Nuclear Regulatory Commission. Thomas Boyce, Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2018–11996 Filed 6–4–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Planning and Procedures; Notice of Meeting amozie on DSK3GDR082PROD with NOTICES1 The ACRS Subcommittee on Planning and Procedures will hold a meeting on June 6, 2018, 11545 Rockville Pike, Room T–2B3, Rockville, Maryland 20852. The meeting will be open to public attendance. The agenda for the subject meeting shall be as follows: Wednesday, June 6, 2018—12:00 p.m. Until 1:00 p.m. The Subcommittee will discuss proposed ACRS activities and related matters. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the Full Committee. Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official (DFO), Quynh Nguyen (Telephone 301–415–5844 or Email: VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 Quynh.Nguyen@nrc.gov) five days prior to the meeting, if possible, so that arrangements can be made. Thirty-five hard copies of each presentation or handout should be provided to the DFO thirty minutes before the meeting. In addition, one electronic copy of each presentation should be emailed to the DFO one day before the meeting. If an electronic copy cannot be provided within this timeframe, presenters should provide the DFO with a CD containing each presentation at least thirty minutes before the meeting. Electronic recordings will be permitted only during those portions of the meeting that are open to the public. Detailed procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on October 4, 2017 (82 FR 46312). The bridgeline number for this meeting is 888–790–7128, passcode 7802533#. Information regarding changes to the agenda, whether the meeting has been canceled or rescheduled, and the time allotted to present oral statements can be obtained by contacting the identified DFO. Moreover, in view of the possibility that the schedule for ACRS meetings may be adjusted by the Chairman as necessary to facilitate the conduct of the meeting, persons planning to attend should check with the DFO if such rescheduling would result in a major inconvenience. If attending this meeting, please enter through the One White Flint North building, 11555 Rockville Pike, Rockville, Maryland 20852. After registering with Security, please contact Mr. Theron Brown at 301–415–6702 to be escorted to the meeting room. Dated: May 23, 2018. Mark L. Banks, Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards. [FR Doc. 2018–12023 Filed 6–4–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2018–0102] Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information Nuclear Regulatory Commission. AGENCY: PO 00000 Frm 00118 Fmt 4703 Sfmt 4703 License amendment request; notice of opportunity to comment, request a hearing, and petition for leave to intervene; order imposing procedures. ACTION: The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of three amendment requests. The amendment requests are for River Bend Station, Unit 1; Grand Gulf Nuclear Station, Unit 1; and Browns Ferry Nuclear Plant, Units 1, 2, and 3. For each amendment request, the NRC proposes to determine that they involve no significant hazards consideration. Because each amendment request contains sensitive unclassified non-safeguards information (SUNSI) an order imposes procedures to obtain access to SUNSI for contention preparation. SUMMARY: Comments must be filed by July 5, 2018. A request for a hearing must be filed by August 6, 2018. Any potential party as defined in § 2.4 of title 10 of the Code of Federal Regulations (10 CFR) who believes access to SUNSI is necessary to respond to this notice must request document access by June 15, 2018. DATES: You may submit comments by any of the following methods: • Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC–2018–0102. Address questions about NRC dockets to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individual 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: Beverly Clayton, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415– 3475; email: Beverly.Clayton@nrc.gov. SUPPLEMENTARY INFORMATION: ADDRESSES: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC–2018– 0102, facility name, unit number(s), E:\FR\FM\05JNN1.SGM 05JNN1 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices amozie on DSK3GDR082PROD with NOTICES1 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 http://www.regulations.gov and search for Docket ID NRC–2018–0102. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and then select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301–415–4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced 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– 0102, 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 http:// www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment into ADAMS. II. Background Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the NRC is publishing this notice. The Act requires the VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 Commission to publish notice of any amendments issued, or proposed to be issued and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This notice includes notices of amendments containing SUNSI. III. Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Combined Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The Commission has made a proposed determination that the following amendment requests involve no significant hazards consideration. Under the Commission’s regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, 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 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 a notice of issuance in the Federal Register. If the Commission makes a final no significant hazards PO 00000 Frm 00119 Fmt 4703 Sfmt 4703 26113 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 http://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 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 E:\FR\FM\05JNN1.SGM 05JNN1 amozie on DSK3GDR082PROD with NOTICES1 26114 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices 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 VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 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. 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 http://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. PO 00000 Frm 00120 Fmt 4703 Sfmt 4703 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 http:// 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 http://www.nrc.gov/ site-help/electronic-sub-ref-mat.html. A filing is considered complete at the time 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 E:\FR\FM\05JNN1.SGM 05JNN1 amozie on DSK3GDR082PROD with NOTICES1 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices on the NRC’s public website at http:// 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 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 VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 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. Entergy Louisiana, LLC, and Entergy Operations, Inc., Docket No. 50–458, River Bend Station, Unit 1 (River Bend), West Feliciana Parish, Louisiana Date of amendment request: April 2, 2018. A publicly-available version is in ADAMS under Accession No. ML18092B187. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendment would replace Technical Specification (TS) Figure 3.4.11–1, ‘‘Minimum Temperature Required vs. RCS [Reactor Coolant System] Pressure,’’ curves, also known as the pressure and temperature limit curves. The current TS figure is calculated for 34 Effective Full Power Years (EFPY), and the proposed TS figure would provide for 54 EFPY. The proposed TS figure includes new fluence values and material chemistry information, and uses the new methodologies described in Licensing Topical Report NEDO– 33882, Revision 1, ‘‘Pressure and Temperature Limits Report (PTLR) Up to 54 Effective Full Power Years.’’ 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, with NRC staff edits in square brackets: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. Basis: The proposed change to the River Bend reactor coolant system (RCS) pressure/ temperature (P/T) limits does not modify the boundary, operating pressure, materials or seismic loading of the reactor coolant system. The proposed change does adjust the P/T limits for neutron irradiation effects to ensure that the Reactor Pressure Vessel (RPV) fracture toughness is consistent with analysis assumptions and NRC regulations. Changing the applicability of the limits to 54 effective full power years (EFPY) will continue to maintain appropriate limits for River Bend during the renewed license term. The proposed limits are more bounding than the current limits. Therefore, it is concluded that this change does not significantly increase the probability or consequences of an accident previously evaluated. PO 00000 Frm 00121 Fmt 4703 Sfmt 4703 26115 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. Basis: The proposed change to the reactor pressure vessel pressure-temperature limits does not involve any physical changes (installing new equipment or modifying existing equipment). The change does not affect the assumed accident performance of any structure, system or component previously evaluated. These revised limits are in compliance with the brittle fracture requirements of [10 CFR part 50] Appendix G. The proposed change does not introduce any new modes of system operation or failure mechanisms. 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. Basis: The proposed change, which corrects a non-conservative TS, does not exceed or alter a setpoint, design basis or safety limit. Therefore, it is concluded that this 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: Anna Vinson Jones, Senior Counsel/Legal Department, Entergy Services, Inc., 101 Constitution Avenue NW, Suite 200 East, Washington, DC 20001. NRC Branch Chief: Robert J. Pascarelli. Entergy Operations, Inc. (Entergy); System Energy Resources, Inc.; Cooperative Energy, A Mississippi Electric Cooperative; and Entergy Mississippi, Inc., Docket No. 50–416, Grand Gulf Nuclear Station, Unit No. 1, Claiborne County, Mississippi Date of amendment request: March 26, 2018. A publicly-available version is in ADAMS under Accession No. ML18085A579. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendment would revise the Updated Final Safety Analysis Report (UFSAR) descriptions for the replacement of the Turbine First Stage Pressure (TFSP) output signals with Power Range Neutron Monitoring System (PRNMS) output signals. During June 2014, Entergy implemented Engineering Change (EC) 49880 in accordance with E:\FR\FM\05JNN1.SGM 05JNN1 amozie on DSK3GDR082PROD with NOTICES1 26116 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices 10 CFR 50.59, ‘‘Changes, tests, and experiments,’’ that replaced the use of the TFSP instruments with the PRNMS to measure reactor power. On December 9, 2016, the NRC issued NRC Inspection Report 05000416/2016007. In this inspection report, the NRC issued noncited violation 050000416/2016007–02, which identified that Entergy failed to obtain a license amendment prior to implementing the proposed change. Specifically, modification EC 40880 eliminated the TFSP instrument signals to the Reactor Protection System and replaced the signals with average power range monitor signals. The NRC concluded that the change reduced the diversity and resulted in a more than minimal increase in the likelihood of occurrence of a malfunction of a structure, system, or component (SSC) important to safety. Entergy has determined that the proposed change requires NRC approval per 10 CFR 50.59(c)(2). Entergy concluded that the plant modification is potentially a reduction in diversity based on the Grand Gulf Nuclear Station, Unit 1, licensing basis. As such, the potential reduction in diversity is considered to be a change that results in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. The proposed amendment would eliminate the potential for a transient caused by the mechanical failure of the TFSP sensing lines and instruments. It would also eliminate process delays in the steam lines, as the PRNMS voltage output signals are based on average power range monitoring signals, a direct and immediate measurement of neutron flux. The PRNMS signals are divisionally separated, safety-related, and provide reliability, quality, and defense-in-depth that the TFSP sensing lines and instruments could not provide. The replacement of the TFSP output signals with the PRNMS output signals enhances plant safety and improves reliability. 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 modification does not result in a change to the safety related functions including Low Power Setpoint (LPSP) and VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 High Power Setpoint (HPSP), Turbine Stop Valve (TSV) closure and Turbine Control Valve (TCV) fast closure scram enable/ bypass, and End of Cycle Recirculation Pump Trip (EOC–RPT) enable/bypass. The accidents potentially affected by the TFSP instrumentation are the turbine trip event (UFSAR Section 15.2.3), generator load rejection event (UFSAR Section 15.2.2), control rod drop accident (UFSAR Section 15.4.9) and rod withdrawal error (UFSAR Section 15.4.1). The proposed use of PRNMS signal outputs as inputs to the trip units will maintain the safety related functions credited in the evaluated events. Furthermore, the proposed modification makes no changes to the existing PRNM system inputs, system software or hardware architecture. Overall protection system performance will remain within the bounds of the previously performed accident analyses since the proposed modification does not change the Reactor Protection System (RPS) or the Rod Control and Information System (RCIS). The same RPS and RCIS instrumentation will continue to be used. The protection systems will continue to function in a manner consistent with the plant design basis. The proposed modifications will not adversely affect accident initiators or precursors nor adversely alter the design assumptions and conditions of the facility or the manner in which the plant is operated and maintained with respect to such initiators or precursors. The proposed modification will not prevent the capability of structures, systems, and components (SSCs) to perform their intended functions for mitigating the consequences of an accident and meeting applicable acceptance limits. Therefore, operation of the facility in accordance with the proposed amendment would 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 use of PRNMS for determining reactor power will ensure that the protective functions EOC–RPT, TSV closure and TCV fast closure direct scram functions, and the rod pattern controller (RPC) and Rod Withdrawal Limiter functions credited in the safety analyses are maintained. With these automatic functions maintained, the proposed modification does not create the possibility of a new or different kind of accident from any accident previously evaluated in the UFSAR. No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures will be introduced as a result of the proposed modification. No new or different accidents result from the proposed modification. The proposed modification will not alter the performance of the RPS, RCIS and PRNMS. Thus, 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? PO 00000 Frm 00122 Fmt 4703 Sfmt 4703 Response: No. The proposed modification does not alter the manner in which safety limits, safety setpoints, or limiting conditions for operation are determined. The PRNMS hardware and software are not changed by this modification. The modified system responds to a loss of power, and a restoration of power, in the same way as the TFSP system would have responded. The proposed modification makes no changes to the PRNMS, RPS or RCIS human-system interfaces. The equipment credited to perform a safety function has been designed and installed to the applicable quality standards and maintained the required redundancy. The proposed modification is expected to provide an improvement in accuracy for the determination of the low power setpoint and high power setpoint in terms of reactor power. The replacement of the TFSP output signals with the PRNMS output signals does not reduce the diversity of the RPS trip functions by use of a more direct measurement of power given the additional diverse capabilities available. The proposed modification maintains conservative margins between Analytical Limits, Allowable Values and the Nominal Trip Setpoints. The proposed change does not impact accident offsite dose, containment pressure or temperature, Emergency Core Cooling System settings, Reactor Core Isolation Cooling System settings or RPS settings, or other parameter that could affect a margin of safety. Therefore, the proposed amendment does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee’s analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. Attorney for licensee: Anna Vinson Jones, Senior Counsel/Legal Department, Entergy Services, Inc., 101 Constitution Avenue NW, Suite 200 East, Washington, DC 20001. NRC Branch Chief: Robert J. Pascarelli. Tennessee Valley Authority, Docket Nos. 50–259, 50–260, and 50–296, Browns Ferry Nuclear Plant, Units 1, 2, and 3 (BFN), Limestone County, Alabama Date of amendment request: February 23, 2018, as supplemented by letter dated March 7, 2018. Publicly-available versions are in ADAMS under Accession Nos. ML18079B140 and ML18067A495, respectively. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The proposed amendments would allow operation of BFN in the expanded Maximum E:\FR\FM\05JNN1.SGM 05JNN1 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices amozie on DSK3GDR082PROD with NOTICES1 Extended Load Line Limit Analysis Plus (MELLLA+) operating domain. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed operation in the MELLLA+ operating domain does not significantly increase the probability or consequences of an accident previously evaluated. The probability (frequency of occurrence) of Design Basis Accidents (DBAs) occurring is not affected by the MELLLA+ operating domain because BFN continues to comply with the regulatory and design basis criteria established for plant equipment. There is no change in consequences of postulated accidents when operating in the MELLLA+ operating domain compared to the operating domain previously evaluated. The results of accident evaluations remain within the NRC approved acceptance limits. The spectrum of postulated transients has been investigated and is shown to meet the plant’s currently licensed regulatory criteria. Continued compliance with the Safety Limit Minimum Critical Power Ratio (SLMCPR) will be confirmed on a cycle-specific basis consistent with the criteria accepted by the NRC. Challenges to the reactor coolant pressure boundary were evaluated for the MELLLA+ operating domain conditions (pressure, temperature, flow, and radiation) and were found to meet their acceptance criteria for allowable stresses and overpressure margin. Challenges to the containment were evaluated and the containment and its associated cooling systems continue to meet the current licensing basis. The calculated post-Loss-of-Coolant Accident (LOCA) suppression pool temperature remains acceptable. 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 operation in the MELLLA+ operating domain does not create the possibility of a new or different kind of accident from any previously evaluated. Equipment that could be affected by the MELLLA+ operating domain has been evaluated. No new operating mode, safetyrelated equipment lineup, accident scenario, or equipment failure mode was identified. The full spectrum of accident considerations has been evaluated and no new or different kind of accident has been identified. The MELLLA+ operating domain uses developed technology, and applies it within the capabilities of existing plant safety-related VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 equipment in accordance with the regulatory criteria (including NRC-approved codes, standards and methods). No new accident or event precursor has been identified. 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 operation in the MELLLA+ operating domain does not involve a significant reduction in the margin of safety. The MELLLA+ operating domain affects only design and operational margins. Challenges to the fuel, reactor coolant pressure boundary, and containment were evaluated for the MELLLA+ operating domain conditions. Fuel integrity is maintained by meeting existing design and regulatory limits. The calculated loads on affected structures, systems, and components, including the reactor coolant pressure boundary, will remain within their design allowables for design basis event categories. No NRC acceptance criterion is exceeded. The BFN configuration and responses to transients and postulated accidents do not result in exceeding the presently approved NRC acceptance limits. 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: General Counsel, Tennessee Valley Authority, 400 West Summit Hill Dr., WT 6A–K, Knoxville, Tennessee 37902. NRC Acting Branch Chief: Brian W. Tindell. Order Imposing Procedures for Access to Sensitive Unclassified NonSafeguards Information for Contention Preparation Entergy Louisiana, LLC, and Entergy Operations, Inc., Docket No. 50–458, River Bend Station, Unit 1, West Feliciana Parish, Louisiana Entergy Operations, Inc.; System Energy Resources, Inc.; Cooperative Energy, A Mississippi Electric Cooperative; and Entergy Mississippi, Inc., Docket No. 50– 416, Grand Gulf Nuclear Station, Unit 1, Claiborne County, Mississippi Tennessee Valley Authority, Docket Nos. 50–259, 50–260, and 50–296, Browns Ferry Nuclear Plant, Unit Nos. 1, 2, and 3, Limestone County, Alabama A. This Order contains instructions regarding how potential parties to this proceeding may request access to PO 00000 Frm 00123 Fmt 4703 Sfmt 4703 26117 documents containing Sensitive Unclassified Non-Safeguards Information (SUNSI). B. Within 10 days after publication of this notice of hearing and opportunity to petition for leave to intervene, any potential party who believes access to SUNSI is necessary to respond to this notice may request access to SUNSI. A ‘‘potential party’’ is any person who intends to participate as a party by demonstrating standing and filing an admissible contention under 10 CFR 2.309. Requests for access to SUNSI submitted later than 10 days after publication of this notice will not be considered absent a showing of good cause for the late filing, addressing why the request could not have been filed earlier. C. The requester shall submit a letter requesting permission to access SUNSI to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, Attention: Rulemakings and Adjudications Staff, and provide a copy to the Associate General Counsel for Hearings, Enforcement and Administration, Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. The expedited delivery or courier mail address for both offices is: U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, Maryland 20852. The email address for the Office of the Secretary and the Office of the General Counsel are Hearing.Docket@nrc.gov and OGCmailcenter@nrc.gov, respectively.1 The request must include the following information: (1) A description of the licensing action with a citation to this Federal Register notice; (2) The name and address of the potential party and a description of the potential party’s particularized interest that could be harmed by the action identified in C.(1); and (3) The identity of the individual or entity requesting access to SUNSI and the requester’s basis for the need for the information in order to meaningfully participate in this adjudicatory proceeding. In particular, the request must explain why publicly available versions of the information requested would not be sufficient to provide the basis and specificity for a proffered contention. D. Based on an evaluation of the information submitted under paragraph 1 While a request for hearing or petition to intervene in this proceeding must comply with the filing requirements of the NRC’s ‘‘E-Filing Rule,’’ the initial request to access SUNSI under these procedures should be submitted as described in this paragraph. E:\FR\FM\05JNN1.SGM 05JNN1 26118 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices C.(3) the NRC staff will determine within 10 days of receipt of the request whether: (1) There is a reasonable basis to believe the petitioner is likely to establish standing to participate in this NRC proceeding; and (2) The requestor has established a legitimate need for access to SUNSI. E. If the NRC staff determines that the requestor satisfies both D.(1) and D.(2) above, the NRC staff will notify the requestor in writing that access to SUNSI has been granted. The written notification will contain instructions on how the requestor may obtain copies of the requested documents, and any other conditions that may apply to access to those documents. These conditions may include, but are not limited to, the signing of a Non-Disclosure Agreement or Affidavit, or Protective Order 2 setting forth terms and conditions to prevent the unauthorized or inadvertent disclosure of SUNSI by each individual who will be granted access to SUNSI. F. Filing of Contentions. Any contentions in these proceedings that are based upon the information received as a result of the request made for SUNSI must be filed by the requestor no later than 25 days after receipt of (or access to) that information. However, if more than 25 days remain between the petitioner’s receipt of (or access to) the information and the deadline for filing all other contentions (as established in the notice of hearing or opportunity for hearing), the petitioner may file its SUNSI contentions by that later deadline. G. Review of Denials of Access. (1) If the request for access to SUNSI is denied by the NRC staff after a determination on standing and requisite need, the NRC staff shall immediately notify the requestor in writing, briefly stating the reason or reasons for the denial. (2) The requester may challenge the NRC staff’s adverse determination by filing a challenge within 5 days of receipt of that determination with: (a) The presiding officer designated in this proceeding; (b) if no presiding officer has been appointed, the Chief Administrative Judge, or if he or she is unavailable, another administrative judge, or an Administrative Law Judge with jurisdiction pursuant to 10 CFR 2.318(a); or (c) if another officer has been designated to rule on information access issues, with that officer. (3) Further appeals of decisions under this paragraph must be made pursuant to 10 CFR 2.311. H. Review of Grants of Access. A party other than the requester may challenge an NRC staff determination granting access to SUNSI whose release would harm that party’s interest independent of the proceeding. Such a challenge must be filed within 5 days of the notification by the NRC staff of its grant of access and must be filed with: (a) The presiding officer designated in this proceeding; (b) if no presiding officer has been appointed, the Chief Administrative Judge, or if he or she is unavailable, another administrative judge, or an Administrative Law Judge with jurisdiction pursuant to 10 CFR 2.318(a); or (c) if another officer has been designated to rule on information access issues, with that officer. If challenges to the NRC staff determinations are filed, these procedures give way to the normal process for litigating disputes concerning access to information. The availability of interlocutory review by the Commission of orders ruling on such NRC staff determinations (whether granting or denying access) is governed by 10 CFR 2.311.3 I. The Commission expects that the NRC staff and presiding officers (and any other reviewing officers) will consider and resolve requests for access to SUNSI, and motions for protective orders, in a timely fashion in order to minimize any unnecessary delays in identifying those petitioners who have standing and who have propounded contentions meeting the specificity and basis requirements in 10 CFR part 2. The attachment to this Order summarizes the general target schedule for processing and resolving requests under these procedures. It is so ordered. Dated at Rockville, Maryland, this 17th day of May, 2018. For the Nuclear Regulatory Commission. Annette L. Vietti-Cook, Secretary of the Commission. ATTACHMENT 1—GENERAL TARGET SCHEDULE FOR PROCESSING AND RESOLVING REQUESTS FOR ACCESS TO SENSITIVE UNCLASSIFIED NON-SAFEGUARDS INFORMATION IN THIS PROCEEDING Day Event/activity 0 .................... Publication of Federal Register notice of hearing and opportunity to petition for leave to intervene, including order with instructions for access requests. Deadline for submitting requests for access to Sensitive Unclassified Non-Safeguards Information (SUNSI) with information: supporting the standing of a potential party identified by name and address; and describing the need for the information in order for the potential party to participate meaningfully in an adjudicatory proceeding. Deadline for submitting petition for intervention containing: (i) Demonstration of standing; and (ii) all contentions whose formulation does not require access to SUNSI (+25 Answers to petition for intervention; +7 petitioner/requestor reply). U.S. Nuclear Regulatory Commission (NRC) staff informs the requester of the staff’s determination whether the request for access provides a reasonable basis to believe standing can be established and shows need for SUNSI. (NRC staff also informs any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information.) If NRC staff makes the finding of need for SUNSI and likelihood of standing, NRC staff begins document processing (preparation of redactions or review of redacted documents). If NRC staff finds no ‘‘need’’ or no likelihood of standing, the deadline for petitioner/requester to file a motion seeking a ruling to reverse the NRC staff’s denial of access; NRC staff files copy of access determination with the presiding officer (or Chief Administrative Judge or other designated officer, as appropriate). If NRC staff finds ‘‘need’’ for SUNSI, the deadline for any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information to file a motion seeking a ruling to reverse the NRC staff’s grant of access. Deadline for NRC staff reply to motions to reverse NRC staff determination(s). 10 .................. 60 .................. 20 .................. amozie on DSK3GDR082PROD with NOTICES1 25 .................. 30 .................. 2 Any motion for Protective Order or draft NonDisclosure Affidavit or Agreement for SUNSI must be filed with the presiding officer or the Chief Administrative Judge if the presiding officer has not VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 yet been designated, within 30 days of the deadline for the receipt of the written access request. 3 Requesters should note that the filing requirements of the NRC’s E-Filing Rule (72 FR 49139; August 28, 2007, as amended at 77 FR PO 00000 Frm 00124 Fmt 4703 Sfmt 4703 46562; August 3, 2012), apply to appeals of NRC staff determinations (because they must be served on a presiding officer or the Commission, as applicable), but not to the initial SUNSI request submitted to the NRC staff under these procedures. E:\FR\FM\05JNN1.SGM 05JNN1 Federal Register / Vol. 83, No. 108 / Tuesday, June 5, 2018 / Notices 26119 ATTACHMENT 1—GENERAL TARGET SCHEDULE FOR PROCESSING AND RESOLVING REQUESTS FOR ACCESS TO SENSITIVE UNCLASSIFIED NON-SAFEGUARDS INFORMATION IN THIS PROCEEDING—Continued Day Event/activity 40 .................. (Receipt +30) If NRC staff finds standing and need for SUNSI, deadline for NRC staff to complete information processing and file motion for Protective Order and draft Non-Disclosure Affidavit. Deadline for applicant/licensee to file Non-Disclosure Agreement for SUNSI. If access granted: issuance of presiding officer or other designated officer decision on motion for protective order for access to sensitive information (including schedule for providing access and submission of contentions) or decision reversing a final adverse determination by the NRC staff. Deadline for filing executed Non-Disclosure Affidavits. Access provided to SUNSI consistent with decision issuing the protective order. Deadline for submission of contentions whose development depends upon access to SUNSI. However, if more than 25 days remain between the petitioner’s receipt of (or access to) the information and the deadline for filing all other contentions (as established in the notice of opportunity to request a hearing and petition for leave to intervene), the petitioner may file its SUNSI contentions by that later deadline. (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI. (Answer receipt +7) Petitioner/Intervenor reply to answers. Decision on contention admission. A .................... A + 3 ............. A + 28 ........... A + 53 ........... A + 60 ........... >A + 60 ......... BILLING CODE 7590–01–P PENSION BENEFIT GUARANTY CORPORATION Pendency for Request for Approval of Special Withdrawal Liability Rules: Alaska Electrical Pension Plan of the Alaska Electrical Pension Fund Pension Benefit Guaranty Corporation. AGENCY: ACTION: Notice of pendency of request. This notice advises interested persons that the Pension Benefit Guaranty Corporation (PBGC) has received a request from the Alaska Electrical Pension Plan of the Alaska Electrical Pension Fund for approval of a plan amendment providing for special withdrawal liability rules. Under PBGC’s regulation on Extension of Special Withdrawal Liability Rules, a multiemployer pension plan may, with PBGC approval, be amended to provide for special withdrawal liability rules similar to those that apply to the construction and entertainment industries. Such approval is granted only if PBGC determines that the rules apply to an industry with characteristics that make use of the special rules appropriate and that the rules will not pose a significant risk to the pension insurance system. Before granting an approval, PBGC’s regulations require PBGC to give interested persons an opportunity to comment on the request. The purpose of this notice is to advise interested persons of the request and to solicit their views on it. amozie on DSK3GDR082PROD with NOTICES1 SUMMARY: Comments must be submitted on or before July 20, 2018. DATES: VerDate Sep<11>2014 20:19 Jun 04, 2018 Jkt 241001 Comments may be submitted by any of the following methods: • Federal eRulemaking Portal: http:// www.regulations.gov. Follow the instructions for submitting comments. • Email: reg.comments@pbgc.gov. Refer to the Alaska Plan in the subject line. • Mail or Hand Delivery: Regulatory Affairs Division, Office of the General Counsel, Pension Benefit Guaranty Corporation, 1200 K Street NW, Washington, DC 20005–4026. All submissions received must include the agency’s name (Pension Benefit Guaranty Corporation, or PBGC) and refer to the Alaska Plan. All comments received will be posted without change to PBGC’s website, http://www.pbgc.gov, including any personal information provided. Copies of comments may also be obtained by writing to Disclosure Division, Office of the General Counsel, Pension Benefit Guaranty Corporation, 1200 K Street NW, Washington, DC 20005–4026 or calling 202–326–4040 during normal business hours. (TTY users may call the Federal relay service toll-free at 1–800– 877–8339 and ask to be connected to 202–326–4040.) FOR FURTHER INFORMATION CONTACT: Jon Chatalian, ext. 6757, Acting Assistant General Counsel (Chatalian.Jon@ PBGC.gov), 202–326–4020, ext. 6757, Office of the Chief Counsel, Suite 340, 1200 K Street NW, Washington, DC 20005–4026. (TTY users may call the Federal relay service toll-free at 1–800– 877–8339 and ask to be connected to 202–326–4020.) SUPPLEMENTARY INFORMATION: ADDRESSES: [FR Doc. 2018–10982 Filed 6–4–18; 8:45 am] Background Section 4203(a) of the Employee Retirement Income Security Act of 1974, as amended by the Multiemployer PO 00000 Frm 00125 Fmt 4703 Sfmt 4703 Pension Plan Amendments Act of 1980 (ERISA), provides that a complete withdrawal from a multiemployer plan generally occurs when an employer permanently ceases to have an obligation to contribute under the plan or permanently ceases all covered operations under the plan. Under section 4205 of ERISA, a partial withdrawal generally occurs when an employer: (1) Reduces its contribution base units by seventy percent in each of three consecutive years; or (2) permanently ceases to have an obligation under one or more but fewer than all collective bargaining agreements under which the employer has been obligated to contribute under the plan, while continuing to perform work in the jurisdiction of the collective bargaining agreement of the type for which contributions were previously required or transfers such work to another location or to an entity or entities owned or controlled by the employer; or (3) permanently ceases to have an obligation to contribute under the plan for work performed at one or more but fewer than all of its facilities, while continuing to perform work at the facility of the type for which the obligation to contribute ceased. Although the general rules on complete and partial withdrawal identify events that normally result in a diminution of the plan’s contribution base, Congress recognized that, in certain industries and under certain circumstances, a complete or partial cessation of the obligation to contribute normally does not weaken the plan’s contribution base. For that reason, Congress established special withdrawal rules for the construction and entertainment industries. For construction industry plans and employers, section 4203(b)(2) of ERISA provides that a complete withdrawal E:\FR\FM\05JNN1.SGM 05JNN1

Agencies

[Federal Register Volume 83, Number 108 (Tuesday, June 5, 2018)]
[Notices]
[Pages 26112-26119]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-10982]


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NUCLEAR REGULATORY COMMISSION

[NRC-2018-0102]


Applications and Amendments to Facility Operating Licenses and 
Combined Licenses Involving Proposed No Significant Hazards 
Considerations and Containing Sensitive Unclassified Non-Safeguards 
Information and Order Imposing Procedures for Access to Sensitive 
Unclassified Non-Safeguards Information

AGENCY: Nuclear Regulatory Commission.

ACTION: License amendment request; notice of opportunity to comment, 
request a hearing, and petition for leave to intervene; order imposing 
procedures.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) received and is 
considering approval of three amendment requests. The amendment 
requests are for River Bend Station, Unit 1; Grand Gulf Nuclear 
Station, Unit 1; and Browns Ferry Nuclear Plant, Units 1, 2, and 3. For 
each amendment request, the NRC proposes to determine that they involve 
no significant hazards consideration. Because each amendment request 
contains sensitive unclassified non-safeguards information (SUNSI) an 
order imposes procedures to obtain access to SUNSI for contention 
preparation.

DATES: Comments must be filed by July 5, 2018. A request for a hearing 
must be filed by August 6, 2018. Any potential party as defined in 
Sec.  2.4 of title 10 of the Code of Federal Regulations (10 CFR) who 
believes access to SUNSI is necessary to respond to this notice must 
request document access by June 15, 2018.

ADDRESSES: You may submit comments by any of the following methods:
     Federal Rulemaking website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0102. Address 
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: [email protected]. For technical questions, contact 
the individual 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: Beverly Clayton, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-3475; email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2018-0102, facility name, unit 
number(s),

[[Page 26113]]

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 http://www.regulations.gov and search for Docket ID NRC-2018-0102.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to [email protected]. The 
ADAMS accession number for each document referenced 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-2018-0102, 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 http://www.regulations.gov as well as enter the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS.

II. Background

    Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as 
amended (the Act), the NRC is publishing this notice. The Act requires 
the Commission to publish notice of any amendments issued, or proposed 
to be issued and grants the Commission the authority to issue and make 
immediately effective any amendment to an operating license or combined 
license, as applicable, upon a determination by the Commission that 
such amendment involves no significant hazards consideration, 
notwithstanding the pendency before the Commission of a request for a 
hearing from any person.
    This notice includes notices of amendments containing SUNSI.

III. Notice of Consideration of Issuance of Amendments to Facility 
Operating Licenses and Combined Licenses, Proposed No Significant 
Hazards Consideration Determination, and Opportunity for a Hearing

    The Commission has made a proposed determination that the following 
amendment requests involve no significant hazards consideration. Under 
the Commission's regulations in 10 CFR 50.92, this means that operation 
of the facility in accordance with the proposed amendment would not (1) 
involve a significant increase in the probability or consequences of an 
accident previously evaluated, 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 a notice of issuance in the Federal 
Register. 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 http://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 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

[[Page 26114]]

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 http://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 http://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 http://www.nrc.gov/site-help/electronic-sub-ref-mat.html. A filing is considered complete at the 
time 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

[[Page 26115]]

on the NRC's public website at http://www.nrc.gov/site-help/e-submittals.html, by email to [email protected], or by a toll-free 
call at 1-866-672-7640. The NRC 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.

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

    Date of amendment request: April 2, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18092B187.
    Description of amendment request: This amendment request contains 
sensitive unclassified non-safeguards information (SUNSI). The proposed 
amendment would replace Technical Specification (TS) Figure 3.4.11-1, 
``Minimum Temperature Required vs. RCS [Reactor Coolant System] 
Pressure,'' curves, also known as the pressure and temperature limit 
curves. The current TS figure is calculated for 34 Effective Full Power 
Years (EFPY), and the proposed TS figure would provide for 54 EFPY. The 
proposed TS figure includes new fluence values and material chemistry 
information, and uses the new methodologies described in Licensing 
Topical Report NEDO-33882, Revision 1, ``Pressure and Temperature 
Limits Report (PTLR) Up to 54 Effective Full Power Years.''
    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, with NRC staff edits in square 
brackets:

    1. Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    Basis: The proposed change to the River Bend reactor coolant 
system (RCS) pressure/temperature (P/T) limits does not modify the 
boundary, operating pressure, materials or seismic loading of the 
reactor coolant system. The proposed change does adjust the P/T 
limits for neutron irradiation effects to ensure that the Reactor 
Pressure Vessel (RPV) fracture toughness is consistent with analysis 
assumptions and NRC regulations. Changing the applicability of the 
limits to 54 effective full power years (EFPY) will continue to 
maintain appropriate limits for River Bend during the renewed 
license term. The proposed limits are more bounding than the current 
limits.
    Therefore, it is concluded that this change does not 
significantly increase 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.
    Basis: The proposed change to the reactor pressure vessel 
pressure-temperature limits does not involve any physical changes 
(installing new equipment or modifying existing equipment). The 
change does not affect the assumed accident performance of any 
structure, system or component previously evaluated. These revised 
limits are in compliance with the brittle fracture requirements of 
[10 CFR part 50] Appendix G. The proposed change does not introduce 
any new modes of system operation or failure mechanisms.
    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.
    Basis: The proposed change, which corrects a non-conservative 
TS, does not exceed or alter a setpoint, design basis or safety 
limit. Therefore, it is concluded that this 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: Anna Vinson Jones, Senior Counsel/Legal 
Department, Entergy Services, Inc., 101 Constitution Avenue NW, Suite 
200 East, Washington, DC 20001.
    NRC Branch Chief: Robert J. Pascarelli.

Entergy Operations, Inc. (Entergy); System Energy Resources, Inc.; 
Cooperative Energy, A Mississippi Electric Cooperative; and Entergy 
Mississippi, Inc., Docket No. 50-416, Grand Gulf Nuclear Station, Unit 
No. 1, Claiborne County, Mississippi

    Date of amendment request: March 26, 2018. A publicly-available 
version is in ADAMS under Accession No. ML18085A579.
    Description of amendment request: This amendment request contains 
sensitive unclassified non-safeguards information (SUNSI). The proposed 
amendment would revise the Updated Final Safety Analysis Report (UFSAR) 
descriptions for the replacement of the Turbine First Stage Pressure 
(TFSP) output signals with Power Range Neutron Monitoring System 
(PRNMS) output signals. During June 2014, Entergy implemented 
Engineering Change (EC) 49880 in accordance with

[[Page 26116]]

10 CFR 50.59, ``Changes, tests, and experiments,'' that replaced the 
use of the TFSP instruments with the PRNMS to measure reactor power. On 
December 9, 2016, the NRC issued NRC Inspection Report 05000416/
2016007. In this inspection report, the NRC issued non-cited violation 
050000416/2016007-02, which identified that Entergy failed to obtain a 
license amendment prior to implementing the proposed change. 
Specifically, modification EC 40880 eliminated the TFSP instrument 
signals to the Reactor Protection System and replaced the signals with 
average power range monitor signals. The NRC concluded that the change 
reduced the diversity and resulted in a more than minimal increase in 
the likelihood of occurrence of a malfunction of a structure, system, 
or component (SSC) important to safety.
    Entergy has determined that the proposed change requires NRC 
approval per 10 CFR 50.59(c)(2). Entergy concluded that the plant 
modification is potentially a reduction in diversity based on the Grand 
Gulf Nuclear Station, Unit 1, licensing basis. As such, the potential 
reduction in diversity is considered to be a change that results in 
more than a minimal increase in the likelihood of occurrence of a 
malfunction of an SSC important to safety previously evaluated in the 
UFSAR.
    The proposed amendment would eliminate the potential for a 
transient caused by the mechanical failure of the TFSP sensing lines 
and instruments. It would also eliminate process delays in the steam 
lines, as the PRNMS voltage output signals are based on average power 
range monitoring signals, a direct and immediate measurement of neutron 
flux. The PRNMS signals are divisionally separated, safety-related, and 
provide reliability, quality, and defense-in-depth that the TFSP 
sensing lines and instruments could not provide. The replacement of the 
TFSP output signals with the PRNMS output signals enhances plant safety 
and improves reliability.
    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 modification does not result in a change to the 
safety related functions including Low Power Setpoint (LPSP) and 
High Power Setpoint (HPSP), Turbine Stop Valve (TSV) closure and 
Turbine Control Valve (TCV) fast closure scram enable/bypass, and 
End of Cycle Recirculation Pump Trip (EOC-RPT) enable/bypass. The 
accidents potentially affected by the TFSP instrumentation are the 
turbine trip event (UFSAR Section 15.2.3), generator load rejection 
event (UFSAR Section 15.2.2), control rod drop accident (UFSAR 
Section 15.4.9) and rod withdrawal error (UFSAR Section 15.4.1). The 
proposed use of PRNMS signal outputs as inputs to the trip units 
will maintain the safety related functions credited in the evaluated 
events. Furthermore, the proposed modification makes no changes to 
the existing PRNM system inputs, system software or hardware 
architecture.
    Overall protection system performance will remain within the 
bounds of the previously performed accident analyses since the 
proposed modification does not change the Reactor Protection System 
(RPS) or the Rod Control and Information System (RCIS). The same RPS 
and RCIS instrumentation will continue to be used. The protection 
systems will continue to function in a manner consistent with the 
plant design basis. The proposed modifications will not adversely 
affect accident initiators or precursors nor adversely alter the 
design assumptions and conditions of the facility or the manner in 
which the plant is operated and maintained with respect to such 
initiators or precursors.
    The proposed modification will not prevent the capability of 
structures, systems, and components (SSCs) to perform their intended 
functions for mitigating the consequences of an accident and meeting 
applicable acceptance limits.
    Therefore, operation of the facility in accordance with the 
proposed amendment would 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 use of PRNMS for determining reactor power will ensure that 
the protective functions EOC-RPT, TSV closure and TCV fast closure 
direct scram functions, and the rod pattern controller (RPC) and Rod 
Withdrawal Limiter functions credited in the safety analyses are 
maintained. With these automatic functions maintained, the proposed 
modification does not create the possibility of a new or different 
kind of accident from any accident previously evaluated in the 
UFSAR.
    No new accident scenarios, transient precursors, failure 
mechanisms, or limiting single failures will be introduced as a 
result of the proposed modification. No new or different accidents 
result from the proposed modification. The proposed modification 
will not alter the performance of the RPS, RCIS and PRNMS.
    Thus, 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 modification does not alter the manner in which 
safety limits, safety setpoints, or limiting conditions for 
operation are determined. The PRNMS hardware and software are not 
changed by this modification. The modified system responds to a loss 
of power, and a restoration of power, in the same way as the TFSP 
system would have responded. The proposed modification makes no 
changes to the PRNMS, RPS or RCIS human-system interfaces. The 
equipment credited to perform a safety function has been designed 
and installed to the applicable quality standards and maintained the 
required redundancy. The proposed modification is expected to 
provide an improvement in accuracy for the determination of the low 
power setpoint and high power setpoint in terms of reactor power. 
The replacement of the TFSP output signals with the PRNMS output 
signals does not reduce the diversity of the RPS trip functions by 
use of a more direct measurement of power given the additional 
diverse capabilities available. The proposed modification maintains 
conservative margins between Analytical Limits, Allowable Values and 
the Nominal Trip Setpoints.
    The proposed change does not impact accident offsite dose, 
containment pressure or temperature, Emergency Core Cooling System 
settings, Reactor Core Isolation Cooling System settings or RPS 
settings, or other parameter that could affect a margin of safety.
    Therefore, the proposed amendment does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Anna Vinson Jones, Senior Counsel/Legal 
Department, Entergy Services, Inc., 101 Constitution Avenue NW, Suite 
200 East, Washington, DC 20001.
    NRC Branch Chief: Robert J. Pascarelli.

Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296, 
Browns Ferry Nuclear Plant, Units 1, 2, and 3 (BFN), Limestone County, 
Alabama

    Date of amendment request: February 23, 2018, as supplemented by 
letter dated March 7, 2018. Publicly-available versions are in ADAMS 
under Accession Nos. ML18079B140 and ML18067A495, respectively.
    Description of amendment request: This amendment request contains 
sensitive unclassified non-safeguards information (SUNSI). The proposed 
amendments would allow operation of BFN in the expanded Maximum

[[Page 26117]]

Extended Load Line Limit Analysis Plus (MELLLA+) operating domain.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed operation in the MELLLA+ operating domain does not 
significantly increase the probability or consequences of an 
accident previously evaluated.
    The probability (frequency of occurrence) of Design Basis 
Accidents (DBAs) occurring is not affected by the MELLLA+ operating 
domain because BFN continues to comply with the regulatory and 
design basis criteria established for plant equipment. There is no 
change in consequences of postulated accidents when operating in the 
MELLLA+ operating domain compared to the operating domain previously 
evaluated. The results of accident evaluations remain within the NRC 
approved acceptance limits.
    The spectrum of postulated transients has been investigated and 
is shown to meet the plant's currently licensed regulatory criteria. 
Continued compliance with the Safety Limit Minimum Critical Power 
Ratio (SLMCPR) will be confirmed on a cycle-specific basis 
consistent with the criteria accepted by the NRC.
    Challenges to the reactor coolant pressure boundary were 
evaluated for the MELLLA+ operating domain conditions (pressure, 
temperature, flow, and radiation) and were found to meet their 
acceptance criteria for allowable stresses and overpressure margin.
    Challenges to the containment were evaluated and the containment 
and its associated cooling systems continue to meet the current 
licensing basis. The calculated post-Loss-of-Coolant Accident (LOCA) 
suppression pool temperature remains acceptable.
    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 operation in the MELLLA+ operating domain does not 
create the possibility of a new or different kind of accident from 
any previously evaluated.
    Equipment that could be affected by the MELLLA+ operating domain 
has been evaluated. No new operating mode, safety-related equipment 
lineup, accident scenario, or equipment failure mode was identified. 
The full spectrum of accident considerations has been evaluated and 
no new or different kind of accident has been identified. The 
MELLLA+ operating domain uses developed technology, and applies it 
within the capabilities of existing plant safety-related equipment 
in accordance with the regulatory criteria (including NRC-approved 
codes, standards and methods). No new accident or event precursor 
has been identified.
    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 operation in the MELLLA+ operating domain does not 
involve a significant reduction in the margin of safety.
    The MELLLA+ operating domain affects only design and operational 
margins. Challenges to the fuel, reactor coolant pressure boundary, 
and containment were evaluated for the MELLLA+ operating domain 
conditions. Fuel integrity is maintained by meeting existing design 
and regulatory limits. The calculated loads on affected structures, 
systems, and components, including the reactor coolant pressure 
boundary, will remain within their design allowables for design 
basis event categories. No NRC acceptance criterion is exceeded. The 
BFN configuration and responses to transients and postulated 
accidents do not result in exceeding the presently approved NRC 
acceptance limits.
    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: General Counsel, Tennessee Valley Authority, 
400 West Summit Hill Dr., WT 6A-K, Knoxville, Tennessee 37902.
    NRC Acting Branch Chief: Brian W. Tindell.

Order Imposing Procedures for Access to Sensitive Unclassified Non-
Safeguards Information for Contention Preparation

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

Entergy Operations, Inc.; System Energy Resources, Inc.; Cooperative 
Energy, A Mississippi Electric Cooperative; and Entergy Mississippi, 
Inc., Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1, Claiborne 
County, Mississippi

Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296, 
Browns Ferry Nuclear Plant, Unit Nos. 1, 2, and 3, Limestone County, 
Alabama

    A. This Order contains instructions regarding how potential parties 
to this proceeding may request access to documents containing Sensitive 
Unclassified Non-Safeguards Information (SUNSI).
    B. Within 10 days after publication of this notice of hearing and 
opportunity to petition for leave to intervene, any potential party who 
believes access to SUNSI is necessary to respond to this notice may 
request access to SUNSI. A ``potential party'' is any person who 
intends to participate as a party by demonstrating standing and filing 
an admissible contention under 10 CFR 2.309. Requests for access to 
SUNSI submitted later than 10 days after publication of this notice 
will not be considered absent a showing of good cause for the late 
filing, addressing why the request could not have been filed earlier.
    C. The requester shall submit a letter requesting permission to 
access SUNSI to the Office of the Secretary, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, Attention: Rulemakings and 
Adjudications Staff, and provide a copy to the Associate General 
Counsel for Hearings, Enforcement and Administration, Office of the 
General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001. The expedited delivery or courier mail address for both 
offices is: U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, 
Rockville, Maryland 20852. The email address for the Office of the 
Secretary and the Office of the General Counsel are 
[email protected] and [email protected], respectively.\1\ The 
request must include the following information:
---------------------------------------------------------------------------

    \1\ While a request for hearing or petition to intervene in this 
proceeding must comply with the filing requirements of the NRC's 
``E-Filing Rule,'' the initial request to access SUNSI under these 
procedures should be submitted as described in this paragraph.
---------------------------------------------------------------------------

    (1) A description of the licensing action with a citation to this 
Federal Register notice;
    (2) The name and address of the potential party and a description 
of the potential party's particularized interest that could be harmed 
by the action identified in C.(1); and
    (3) The identity of the individual or entity requesting access to 
SUNSI and the requester's basis for the need for the information in 
order to meaningfully participate in this adjudicatory proceeding. In 
particular, the request must explain why publicly available versions of 
the information requested would not be sufficient to provide the basis 
and specificity for a proffered contention.
    D. Based on an evaluation of the information submitted under 
paragraph

[[Page 26118]]

C.(3) the NRC staff will determine within 10 days of receipt of the 
request whether:
    (1) There is a reasonable basis to believe the petitioner is likely 
to establish standing to participate in this NRC proceeding; and
    (2) The requestor has established a legitimate need for access to 
SUNSI.
    E. If the NRC staff determines that the requestor satisfies both 
D.(1) and D.(2) above, the NRC staff will notify the requestor in 
writing that access to SUNSI has been granted. The written notification 
will contain instructions on how the requestor may obtain copies of the 
requested documents, and any other conditions that may apply to access 
to those documents. These conditions may include, but are not limited 
to, the signing of a Non-Disclosure Agreement or Affidavit, or 
Protective Order \2\ setting forth terms and conditions to prevent the 
unauthorized or inadvertent disclosure of SUNSI by each individual who 
will be granted access to SUNSI.
---------------------------------------------------------------------------

    \2\ Any motion for Protective Order or draft Non-Disclosure 
Affidavit or Agreement for SUNSI must be filed with the presiding 
officer or the Chief Administrative Judge if the presiding officer 
has not yet been designated, within 30 days of the deadline for the 
receipt of the written access request.
---------------------------------------------------------------------------

    F. Filing of Contentions. Any contentions in these proceedings that 
are based upon the information received as a result of the request made 
for SUNSI must be filed by the requestor no later than 25 days after 
receipt of (or access to) that information. However, if more than 25 
days remain between the petitioner's receipt of (or access to) the 
information and the deadline for filing all other contentions (as 
established in the notice of hearing or opportunity for hearing), the 
petitioner may file its SUNSI contentions by that later deadline.
    G. Review of Denials of Access.
    (1) If the request for access to SUNSI is denied by the NRC staff 
after a determination on standing and requisite need, the NRC staff 
shall immediately notify the requestor in writing, briefly stating the 
reason or reasons for the denial.
    (2) The requester may challenge the NRC staff's adverse 
determination by filing a challenge within 5 days of receipt of that 
determination with: (a) The presiding officer designated in this 
proceeding; (b) if no presiding officer has been appointed, the Chief 
Administrative Judge, or if he or she is unavailable, another 
administrative judge, or an Administrative Law Judge with jurisdiction 
pursuant to 10 CFR 2.318(a); or (c) if another officer has been 
designated to rule on information access issues, with that officer.
    (3) Further appeals of decisions under this paragraph must be made 
pursuant to 10 CFR 2.311.
    H. Review of Grants of Access. A party other than the requester may 
challenge an NRC staff determination granting access to SUNSI whose 
release would harm that party's interest independent of the proceeding. 
Such a challenge must be filed within 5 days of the notification by the 
NRC staff of its grant of access and must be filed with: (a) The 
presiding officer designated in this proceeding; (b) if no presiding 
officer has been appointed, the Chief Administrative Judge, or if he or 
she is unavailable, another administrative judge, or an Administrative 
Law Judge with jurisdiction pursuant to 10 CFR 2.318(a); or (c) if 
another officer has been designated to rule on information access 
issues, with that officer.
    If challenges to the NRC staff determinations are filed, these 
procedures give way to the normal process for litigating disputes 
concerning access to information. The availability of interlocutory 
review by the Commission of orders ruling on such NRC staff 
determinations (whether granting or denying access) is governed by 10 
CFR 2.311.\3\
---------------------------------------------------------------------------

    \3\ Requesters should note that the filing requirements of the 
NRC's E-Filing Rule (72 FR 49139; August 28, 2007, as amended at 77 
FR 46562; August 3, 2012), apply to appeals of NRC staff 
determinations (because they must be served on a presiding officer 
or the Commission, as applicable), but not to the initial SUNSI 
request submitted to the NRC staff under these procedures.
---------------------------------------------------------------------------

    I. The Commission expects that the NRC staff and presiding officers 
(and any other reviewing officers) will consider and resolve requests 
for access to SUNSI, and motions for protective orders, in a timely 
fashion in order to minimize any unnecessary delays in identifying 
those petitioners who have standing and who have propounded contentions 
meeting the specificity and basis requirements in 10 CFR part 2. The 
attachment to this Order summarizes the general target schedule for 
processing and resolving requests under these procedures.
    It is so ordered.

    Dated at Rockville, Maryland, this 17th day of May, 2018.

    For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.

   Attachment 1--General Target Schedule for Processing and Resolving
Requests for Access to Sensitive Unclassified Non-Safeguards Information
                           in This Proceeding
------------------------------------------------------------------------
          Day                             Event/activity
------------------------------------------------------------------------
0......................  Publication of Federal Register notice of
                          hearing and opportunity to petition for leave
                          to intervene, including order with
                          instructions for access requests.
10.....................  Deadline for submitting requests for access to
                          Sensitive Unclassified Non[dash]Safeguards
                          Information (SUNSI) with information:
                          supporting the standing of a potential party
                          identified by name and address; and describing
                          the need for the information in order for the
                          potential party to participate meaningfully in
                          an adjudicatory proceeding.
60.....................  Deadline for submitting petition for
                          intervention containing: (i) Demonstration of
                          standing; and (ii) all contentions whose
                          formulation does not require access to SUNSI
                          (+25 Answers to petition for intervention; +7
                          petitioner/requestor reply).
20.....................  U.S. Nuclear Regulatory Commission (NRC) staff
                          informs the requester of the staff's
                          determination whether the request for access
                          provides a reasonable basis to believe
                          standing can be established and shows need for
                          SUNSI. (NRC staff also informs any party to
                          the proceeding whose interest independent of
                          the proceeding would be harmed by the release
                          of the information.) If NRC staff makes the
                          finding of need for SUNSI and likelihood of
                          standing, NRC staff begins document processing
                          (preparation of redactions or review of
                          redacted documents).
25.....................  If NRC staff finds no ``need'' or no likelihood
                          of standing, the deadline for petitioner/
                          requester to file a motion seeking a ruling to
                          reverse the NRC staff's denial of access; NRC
                          staff files copy of access determination with
                          the presiding officer (or Chief Administrative
                          Judge or other designated officer, as
                          appropriate). If NRC staff finds ``need'' for
                          SUNSI, the deadline for any party to the
                          proceeding whose interest independent of the
                          proceeding would be harmed by the release of
                          the information to file a motion seeking a
                          ruling to reverse the NRC staff's grant of
                          access.
30.....................  Deadline for NRC staff reply to motions to
                          reverse NRC staff determination(s).

[[Page 26119]]

 
40.....................  (Receipt +30) If NRC staff finds standing and
                          need for SUNSI, deadline for NRC staff to
                          complete information processing and file
                          motion for Protective Order and draft Non-
                          Disclosure Affidavit. Deadline for applicant/
                          licensee to file Non-Disclosure Agreement for
                          SUNSI.
A......................  If access granted: issuance of presiding
                          officer or other designated officer decision
                          on motion for protective order for access to
                          sensitive information (including schedule for
                          providing access and submission of
                          contentions) or decision reversing a final
                          adverse determination by the NRC staff.
A + 3..................  Deadline for filing executed Non-Disclosure
                          Affidavits. Access provided to SUNSI
                          consistent with decision issuing the
                          protective order.
A + 28.................  Deadline for submission of contentions whose
                          development depends upon access to SUNSI.
                          However, if more than 25 days remain between
                          the petitioner's receipt of (or access to) the
                          information and the deadline for filing all
                          other contentions (as established in the
                          notice of opportunity to request a hearing and
                          petition for leave to intervene), the
                          petitioner may file its SUNSI contentions by
                          that later deadline.
A + 53.................  (Contention receipt +25) Answers to contentions
                          whose development depends upon access to
                          SUNSI.
A + 60.................  (Answer receipt +7) Petitioner/Intervenor reply
                          to answers.
>A + 60................  Decision on contention admission.
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[FR Doc. 2018-10982 Filed 6-4-18; 8:45 am]
 BILLING CODE 7590-01-P