2018-10982. 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 ...  

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    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 § 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: 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.

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    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.

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    SUPPLEMENTARY INFORMATION:

    I. Obtaining Information and Submitting Comments

    A. Obtaining Information

    Please refer to Docket ID NRC-2018-0102, facility name, unit number(s), Start Printed Page 26113plant 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 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 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 Start Printed Page 26114applicant 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 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 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 Start Printed Page 26115on the NRC's public website at http://www.nrc.gov/​site-help/​e-submittals.html,, by email to MSHD.Resource@nrc.gov, 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 Start Printed Page 2611610 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 Start Printed Page 26117Extended 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 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 Start Printed Page 26118C.(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.

    Start Signature

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

    For the Nuclear Regulatory Commission.

    Annette L. Vietti-Cook,

    Secretary of the Commission.

    End Signature

    Attachment 1—General Target Schedule for Processing and Resolving Requests for Access to Sensitive Unclassified Non-Safeguards Information in This Proceeding

    DayEvent/activity
    0Publication of Federal Register notice of hearing and opportunity to petition for leave to intervene, including order with instructions for access requests.
    10Deadline 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.
    60Deadline 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).
    20U.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).
    25If 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.
    30Deadline for NRC staff reply to motions to reverse NRC staff determination(s).
    Start Printed 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.
    AIf 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 + 3Deadline for filing executed Non-Disclosure Affidavits. Access provided to SUNSI consistent with decision issuing the protective order.
    A + 28Deadline 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 + 60Decision on contention admission.
    End Supplemental Information

    Footnotes

    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.

    Back to Citation

    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.

    Back to Citation

    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.

    Back to Citation

    [FR Doc. 2018-10982 Filed 6-4-18; 8:45 am]

    BILLING CODE 7590-01-P

Document Information

Published:
06/05/2018
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Action:
License amendment request; notice of opportunity to comment, request a hearing, and petition for leave to intervene; order imposing procedures.
Document Number:
2018-10982
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.
Pages:
26112-26119 (8 pages)
Docket Numbers:
NRC-2018-0102
PDF File:
2018-10982.Pdf