Source: https://regulations.justia.com/regulations/fedreg/2018/06/28/2018-13874.html
Timestamp: 2020-01-19 11:29:03
Document Index: 552613072

Matched Legal Cases: ['art 52', 'art 52', 'art 2', 'art 2', 'art 50', 'art 50', 'art 52']

Tennessee Valley Authority, Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Independent Spent Fuel Storage Installation; Sequoyah Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation; Watts Bar Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation, 30465-30469 [2018-13874] :: Nuclear Regulatory Commission :: Agencies And Commissions :: Regulation Tracker :: Justia
Justia Regulation Tracker Agencies And Commissions Nuclear Regulatory Commission Tennessee Valley Authority, Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Independent Spent Fuel Storage Installation; Sequoyah Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation; Watts Bar Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation, 30465-30469 [2018-13874]
Tennessee Valley Authority, Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Independent Spent Fuel Storage Installation; Sequoyah Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation; Watts Bar Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation, 30465-30469 [2018-13874]
Download as PDF Federal Register / Vol. 83, No. 125 / Thursday, June 28, 2018 / Notices amozie on DSK3GDR082PROD with NOTICES1 NRC granted the exemption and issued the amendment concurrently, rather than in sequence. This included issuing a combined safety evaluation containing the NRC staff’s review of both the exemption request and the license amendment. The exemption met all applicable regulatory criteria set forth in 10 CFR 50.12, 10 CFR 52.7, and section VIII.A.4 of appendix D to 10 CFR part 52. The license amendment was found to be acceptable as well. The combined safety evaluation is available in ADAMS under Accession No. ML18100A079. Identical exemption documents (except for referenced unit numbers and license numbers) were issued to the licensee for VEGP Units 3 and 4 (COLs NPF–91 and NPF–92). The exemption documents for VEGP Units 3 and 4 can be found in ADAMS under Accession Nos. ML18100A071 and ML18100A073, respectively. The exemption is reproduced (with the exception of abbreviated titles and additional citations) in Section II of this document. The amendment documents for COLs NPF–91 and NPF–92 are available in ADAMS under Accession Nos. ML18100A074 and ML18100A077, respectively. A summary of the amendment documents is provided in Section III of this document. II. Exemption Reproduced below is the exemption document issued to VEGP Units 3 and 4. It makes reference to the combined safety evaluation that provides the reasoning for the findings made by the NRC (and listed under Item 1) in order to grant the exemption: 1. In an application dated July 14, 2017, the licensee requested from the NRC or Commission an exemption to allow departures from Tier 1 information in the certified Design Control Document (DCD) incorporated by reference in 10 CFR part 52, appendix D, ‘‘Design Certification Rule for the AP1000 Design,’’ as part of license amendment request (LAR) 17– 021, ‘‘Changes to Containment Coolant and Spent Fuel Makeup Strategies.’’ For the reasons set forth in Section 3.1 of the NRC staff’s Safety Evaluation, which can be found in ADAMS under Accession No. ML18100A079, the Commission finds that: A. The exemption is authorized by law; B. the exemption presents no undue risk to public health and safety; C. the exemption is consistent with the common defense and security; D. special circumstances are present in that the application of the rule in this circumstance is not necessary to serve the underlying purpose of the rule; VerDate Sep<11>2014 17:08 Jun 27, 2018 Jkt 244001 E. the special circumstances outweigh any decrease in safety that may result from the reduction in standardization caused by the exemption; and F. the exemption will not result in a significant decrease in the level of safety otherwise provided by the design. 2. Accordingly, the licensee is granted an exemption from the certified DCD Tier 1 information, as described in the licensee’s request dated July 14, 2017. This exemption is related to, and necessary for, the granting of License Amendment Nos. 126 (Unit 3) and 125 (Unit 4), which is being issued concurrently with this exemption. 3. As explained in Section 5.0 of the NRC staff’s Safety Evaluation (ADAMS Accession No. ML18100A079), this exemption meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the exemption. This exemption is effective as of the date of its issuance. III. License Amendment Request By letter dated July 14, 2017 (ADAMS Accession No. ML17198A596), the licensee requested that the NRC amend the COLs for VEGP Units 3 and 4, COLs NPF–91 and NPF–92. The proposed amendments are described in Section I of this document. The Commission has determined for these amendments that the application complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission’s rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission’s rules and regulations in 10 CFR chapter I, which are set forth in the license amendment. A notice of consideration of issuance of amendment to facility operating license or COL, as applicable, proposed no significant hazards consideration determination, and opportunity for a hearing in connection with these actions, was published in the Federal Register on November 22, 2017 (82 FR 55654). No comments were received during the 30-day comment period. The Commission has determined that these amendments satisfy the criteria for categorical exclusion in accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for these amendments. PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 30465 IV. Conclusion Using the reasons set forth in the combined safety evaluation, the staff granted the exemption and issued the amendment that the licensee requested on July 14, 2017. The exemption and amendment were issued on June 7, 2018, as part of a combined package to the licensee (ADAMS Accession No. ML18100A069). Dated at Rockville, Maryland, this 22nd day of June, 2018. For the Nuclear Regulatory Commission. Paul B. Kallan, Acting Branch Chief, Licensing Branch 4, Division of Licensing, Siting, and Environmental Analysis, Office of New Reactors. [FR Doc. 2018–13860 Filed 6–27–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2018–0127; Docket Nos. 50–259, 50– 260, 50–296, and 72–052; Docket Nos. 50– 327, 50–328, and 72–034; Docket Nos. 50– 390, 50–391, and 72–1048] Tennessee Valley Authority, Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Independent Spent Fuel Storage Installation; Sequoyah Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation; Watts Bar Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage Installation Nuclear Regulatory Commission. ACTION: License amendment request; opportunity to comment, request a hearing, and petition for leave to intervene. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of amendments to Renewed Facility Operating License Nos. DPR–33, DPR–52, and DPR–68 for the Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3, respectively; Renewed Facility Operating License Nos. DPR–77 and DPR–79 for the Sequoyah Nuclear Plant (Sequoyah), Units 1 and 2, respectively; and Facility Operating License Nos. NPF–90 and NPF–96 for the Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2, respectively. The proposed amendments would revise the implementation date for the NRCapproved license amendments to upgrade the Emergency Action Level (EAL) schemes for Browns Ferry, Units 1, 2, and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2. SUMMARY: E:\FR\FM\28JNN1.SGM 28JNN1 30466 Federal Register / Vol. 83, No. 125 / Thursday, June 28, 2018 / Notices Comments must be filed by July 30, 2018. Requests for a hearing or petitions for leave to intervene must be filed by August 27, 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–2018–0127. 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: Andrew Hon, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone: 301–415–8480; email: Andrew.Hon@nrc.gov. SUPPLEMENTARY INFORMATION: DATES: I. Obtaining Information and Submitting Comments amozie on DSK3GDR082PROD with NOTICES1 A. Obtaining Information Please refer to Docket ID NRC–2018– 0127 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–2018–0127. • 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 (if it is available in ADAMS) is provided the first time that it is mentioned in this document. • NRC’s PDR: You may examine and purchase copies of public documents at the NRC’s PDR, Room O1–F21, One VerDate Sep<11>2014 17:08 Jun 27, 2018 Jkt 244001 White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. B. Submitting Comments Please include Docket ID NRC–2018– 0127 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. I. Introduction The NRC is considering issuance of an amendment to Renewed Facility Operating License Nos. DPR–33, DPR– 52, and DPR–68 for Browns Ferry, Units 1, 2, and 3, respectively, located in Limestone County, Alabama; Renewed Facility Operating License Nos. DPR–77 and DPR–79 for Sequoyah, Units 1 and 2, respectively, located in Hamilton County, Tennessee; and Facility Operating License Nos. NPF–90 and NPF–96 for Watts Bar, Units 1 and 2, respectively, located in Rhea County, Tennessee. The proposed amendments would revise the implementation date for the NRC-approved license amendments to upgrade the EAL schemes for Browns Ferry, Units 1, 2, and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2. Before any issuance of the proposed license amendment, the NRC will need to make the findings required by the Atomic Energy Act of 1954, as amended (the Act), and NRC’s regulations. The NRC has made a proposed determination that the license amendment request involves no significant hazards consideration. Under the NRC’s regulations in section 50.92 of title 10 of the Code of Federal Regulations (10 CFR), this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) PO 00000 Frm 00070 Fmt 4703 Sfmt 4703 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. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change to the implementation date for the TVA [Tennessee Valley Authority] EAL schemes to adopt the NRC-endorsed guidance in NEI [Nuclear Energy Institute] 99–01, Revision 6, ‘‘Development of Emergency Action Levels for Non-Passive Reactors,’’ does not reduce the capability to meet the emergency planning requirements established in 10 CFR 50.47 and 10 CFR 50, Appendix E. The proposed change does not reduce the functionality, performance, or capability of the TVA ERO [Emergency Response Organization] to respond in mitigating the consequences of any design basis accident. The proposed change does not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, and configuration of the facilities or the manner in which the plants are operated and maintained. The proposed change does not adversely affect the ability of structures, systems, and components (SSC) to perform their intended safety function to mitigate the consequences of an initiating event within the assumed acceptable limits. The proposed changes do not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of any accident previously evaluated. Further, the proposed changes do not increase the types and amounts of radioactive effluent that may be released offsite, nor significantly increase individual or cumulative occupational/ public radiation exposure. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change to the implementation date for the TVA EAL schemes to adopt the NRC-endorsed guidance in NEI 99–01, Revision 6, does not involve any physical changes to plant systems or equipment. The proposed change does not involve the addition of any new plant equipment. The proposed change will not alter the design configuration, or method of operation of plant equipment beyond its normal functional capabilities. All TVA ERO functions will continue to be performed as required. The proposed change does not create any new credible failure mechanisms, malfunctions, or accident initiators. E:\FR\FM\28JNN1.SGM 28JNN1 Federal Register / Vol. 83, No. 125 / Thursday, June 28, 2018 / Notices amozie on DSK3GDR082PROD with NOTICES1 Therefore, the proposed change does not create the possibility of a new or different kind of accident from those that have been previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed change to the implementation date for the TVA EAL schemes to adopt the NRC-endorsed guidance in NEI 99–01, Revision 6, does not alter or exceed a design basis or safety limit. There is no change being made to safety analysis assumptions, safety limits, or limiting safety system settings that would adversely affect plant safety as a result of the proposed changes. There are no changes to setpoints or environmental conditions of any structure, system, or component (SSC) or the manner in which any SSC is operated. Margins of safety are unaffected by the proposed change to the NEI 99–01, Revision 6, EAL scheme guidance implementation date. The applicable requirements of 10 CFR 50.47 and 10 CFR 50, Appendix E will continue to be met. Therefore, the proposed changes do not involve any 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 license amendment request involves no significant hazards consideration. The NRC is seeking public comments on this proposed determination that the license amendment request involves no significant hazards consideration. 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 notice period if the Commission concludes the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30-day comment period if circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility. If the Commission takes action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. If the Commission makes a final no significant hazards consideration determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently. VerDate Sep<11>2014 17:08 Jun 27, 2018 Jkt 244001 II. 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 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 PO 00000 Frm 00071 Fmt 4703 Sfmt 4703 30467 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)’’ E:\FR\FM\28JNN1.SGM 28JNN1 30468 Federal Register / Vol. 83, No. 125 / Thursday, June 28, 2018 / Notices amozie on DSK3GDR082PROD with NOTICES1 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. III. 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. 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 VerDate Sep<11>2014 17:08 Jun 27, 2018 Jkt 244001 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 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 PO 00000 Frm 00072 Fmt 4703 Sfmt 4703 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, E:\FR\FM\28JNN1.SGM 28JNN1 Federal Register / Vol. 83, No. 125 / Thursday, June 28, 2018 / Notices participants are requested not to include copyrighted materials in their submission. For further details with respect to this action, see the application for license amendment dated June 15, 2018 (ADAMS Accession No. ML18169A222). Attorney for licensee: General Counsel, Tennessee Valley Authority, 400 West Summit Hill Drive, 6A West Tower, Knoxville, TN 37902. NRC Acting Branch Chief: Booma Venkataraman. Dated at Rockville, Maryland, this 22nd day of June 2018. For the Nuclear Regulatory Commission. Andrew Hon, Project Manager, Plant Licensing Branch II–2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2018–13874 Filed 6–27–18; 8:45 am] BILLING CODE 7590–01–P [NRC–2018–0131] Monitoring the Effectiveness of Maintenance at Nuclear Power Plants Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG–1336, ‘‘Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.’’ This proposed guide, Revision 4, has been revised to addresses new issues identified since Revision 3 of RG 1.160 was issued and endorses with clarification NUMARC 93–01, ‘‘Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,’’ Revision 4F. The proposed revision describes methods that are acceptable to the NRC staff for compliance with the requirements for monitoring the effectiveness of maintenance at nuclear power plants. DATES: Submit comments by July 30, 2018. Comments received after this date will be considered if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before this date. Although a time limit is given, comments and suggestions in connection with items for inclusion in guides currently being developed or improvements in all published guides are encouraged at any time. ADDRESSES: You may submit comments by any of the following methods: amozie on DSK3GDR082PROD with NOTICES1 SUMMARY: 17:08 Jun 27, 2018 Ami Agrawal, Office of Nuclear Reactor Regulation, telephone: 301–415–8310, email: Ami.Agrawal@nrc.gov; and Stephen Burton, Office of Nuclear Regulatory Research, telephone: 301– 415–7000, email: Stephen.Burton@ nrc.gov. Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. FOR FURTHER INFORMATION CONTACT: NUCLEAR REGULATORY COMMISSION VerDate Sep<11>2014 • Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC–2018–0131. Address questions about NRC dockets to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individuals listed in the FOR FURTHER INFORMATION CONTACT section of this document. • Mail comments to: May Ma, Office of Administration, Mail Stop: TWFN– 7A60, 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. Jkt 244001 SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC–2018– 0131 when contacting the NRC about the availability of information regarding this action. You may obtain publicallyavailable 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–2018–0131. • 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 DG– 1336 is available in ADAMS under Accession No. ML18129A080. • 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. PO 00000 Frm 00073 Fmt 4703 Sfmt 4703 30469 B. Submitting Comments Please include Docket ID NRC–2018– 0131 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 posts all comment submissions at http:// www.regulations.gov as well as enters the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment submissions into ADAMS. II. Additional Information The NRC is issuing for public comment a DG in the NRC’s ‘‘Regulatory Guide’’ series. This series was developed to describe and make available to the public information regarding methods that are acceptable to the NRC staff for implementing specific parts of the NRC’s regulations, techniques that the staff uses in evaluating specific issues or postulated events, and data that the staff needs in its review of applications for permits and licenses. The Maintenance Rule (Part 50.65 of title 10 of the Code of Federal Regulations (10 CFR)) requires each holder of an operating license for a nuclear power plant under 10 CFR part 50 and each holder of a combined license under 10 CFR part 52 (after the Commission makes certain findings) to monitor the performance or condition of structures, systems, or components, against licensee-established goals, in a manner sufficient to provide reasonable assurance that in-scope structures, systems, and components intended functions. The Maintenance Rule also applies to nuclear power plant for which the licensee has submitted the certifications that it has ceased operating permanently, but limited to structures, systems, or components associated with the storage, control, and maintenance of spent fuel in a safe condition, in a manner sufficient to provide reasonable assurance that these structures, systems, and components are E:\FR\FM\28JNN1.SGM 28JNN1
[Pages 30465-30469]
[FR Doc No: 2018-13874]
[NRC-2018-0127; Docket Nos. 50-259, 50-260, 50-296, and 72-052; Docket
Nos. 50-327, 50-328, and 72-034; Docket Nos. 50-390, 50-391, and 72-
Tennessee Valley Authority, Browns Ferry Nuclear Plant, Units 1,
2, and 3, and Independent Spent Fuel Storage Installation; Sequoyah
Nuclear Plant, Units 1 and 2, and Independent Spent Fuel Storage
Installation; Watts Bar Nuclear Plant, Units 1 and 2, and Independent
hearing, and petition for leave to intervene.
33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant (Browns
Ferry), Units 1, 2, and 3, respectively; Renewed Facility Operating
License Nos. DPR-77 and DPR-79 for the Sequoyah Nuclear Plant
(Sequoyah), Units 1 and 2, respectively; and Facility Operating License
Nos. NPF-90 and NPF-96 for the Watts Bar Nuclear Plant (Watts Bar),
Units 1 and 2, respectively. The proposed amendments would revise the
implementation date for the NRC-approved license amendments to upgrade
the Emergency Action Level (EAL) schemes for Browns Ferry, Units 1, 2,
and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2.
[[Page 30466]]
DATES: Comments must be filed by July 30, 2018. Requests for a hearing
or petitions for leave to intervene must be filed by August 27, 2018.
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0127. Address
FOR FURTHER INFORMATION CONTACT: Andrew Hon, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001; telephone: 301-415-8480; email:
Please refer to Docket ID NRC-2018-0127 when contacting the NRC
Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0127.
Please include Docket ID NRC-2018-0127 in your comment submission.
Operating License Nos. DPR-33, DPR-52, and DPR-68 for Browns Ferry,
Units 1, 2, and 3, respectively, located in Limestone County, Alabama;
Renewed Facility Operating License Nos. DPR-77 and DPR-79 for Sequoyah,
Units 1 and 2, respectively, located in Hamilton County, Tennessee; and
Facility Operating License Nos. NPF-90 and NPF-96 for Watts Bar, Units
1 and 2, respectively, located in Rhea County, Tennessee.
The proposed amendments would revise the implementation date for
the NRC-approved license amendments to upgrade the EAL schemes for
Browns Ferry, Units 1, 2, and 3; Sequoyah, Units 1 and 2; and Watts
Bar, Units 1 and 2.
The proposed change to the implementation date for the TVA
[Tennessee Valley Authority] EAL schemes to adopt the NRC-endorsed
guidance in NEI [Nuclear Energy Institute] 99-01, Revision 6,
does not reduce the capability to meet the emergency planning
requirements established in 10 CFR 50.47 and 10 CFR 50, Appendix E.
The proposed change does not reduce the functionality, performance,
or capability of the TVA ERO [Emergency Response Organization] to
conditions, and configuration of the facilities or the manner in
which the plants are operated and maintained. The proposed change
does not adversely affect the ability of structures, systems, and
components (SSC) to perform their intended safety function to
acceptable limits. The proposed changes do not affect the source
used in evaluating the radiological consequences of any accident
the types and amounts of radioactive effluent that may be released
occupational/public radiation exposure.
The proposed change to the implementation date for the TVA EAL
schemes to adopt the NRC-endorsed guidance in NEI 99-01, Revision 6,
does not involve any physical changes to plant systems or equipment.
The proposed change does not involve the addition of any new plant
equipment. The proposed change will not alter the design
configuration, or method of operation of plant equipment beyond its
normal functional capabilities. All TVA ERO functions will continue
to be performed as required. The proposed change does not create any
new credible failure mechanisms, malfunctions, or accident
[[Page 30467]]
does not alter or exceed a design basis or safety limit. There is no
change being made to safety analysis assumptions, safety limits, or
limiting safety system settings that would adversely affect plant
safety as a result of the proposed changes. There are no changes to
setpoints or environmental conditions of any structure, system, or
component (SSC) or the manner in which any SSC is operated. Margins
of safety are unaffected by the proposed change to the NEI 99-01,
Revision 6, EAL scheme guidance implementation date. The applicable
requirements of 10 CFR 50.47 and 10 CFR 50, Appendix E will continue
[[Page 30468]]
[[Page 30469]]
application for license amendment dated June 15, 2018 (ADAMS Accession
No. ML18169A222).
[FR Doc. 2018-13874 Filed 6-27-18; 8:45 am]