Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Addition of Steam Generator System (SGS) Thermal Relief Valves

Federal Register, Volume 83 Issue 32 (Thursday, February 15, 2018)

Federal Register Volume 83, Number 32 (Thursday, February 15, 2018)

Notices

Pages 6890-6891

From the Federal Register Online via the Government Publishing Office www.gpo.gov

FR Doc No: 2018-03167

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

NUCLEAR REGULATORY COMMISSION

Docket Nos. 52-025 and 52-026; NRC-2008-0252

Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Addition of Steam Generator System (SGS) Thermal Relief Valves

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption and combined license amendment; issuance.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information of Tier 1 of the generic AP1000 design control document (DCD) and is issuing License Amendment Nos. 99 and 98 to Combined Licenses (COL), NPF-91 and NPF-92, respectively. The COLs were issued to Southern Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation, MEAG Power SPVM, LLC, MEAG Power SPVJ, LLC, MEAG Power SPVP, LLC, and the City of Dalton, Georgia (the licensee); for construction and operation of the Vogtle Electric Generating Plant (VEGP) Units 3 and 4, located in Burke County, Georgia.

The granting of the exemption allows the changes to Tier 1 information that is requested in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently.

ADDRESSES: Please refer to Docket ID NRC-2008-0252 when contacting the NRC about the availability of information regarding this document. You may access information related to this document, which the NRC possesses and is publicly available, using any of the following methods:

Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2008-0252. Address questions about NRC dockets to Jennifer Borges; telephone: 301-287-

9127; email: email protected. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.

NRC's Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and then select ``Begin Web-

based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-

4737, or by email to email protected. The ADAMS accession number for each document referenced in this document (if that document is available in ADAMS) is provided the first time that a document is referenced. The request for the amendment and exemption was submitted by letter dated April 21, 2017 (ADAMS Accession No. ML17111A958), revised on August 15, 2017 (ADAMS Accession No. ML17227A775) and supplemented by letter dated September 18, 2017 (ADAMS Accession No. ML17261B157).

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.

FOR FURTHER INFORMATION CONTACT: Paul Kallan, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-2809; email: email protected.

SUPPLEMENTARY INFORMATION:

  1. Introduction

    The NRC is granting exemptions from paragraph B of section III, ``Scope and Contents,'' of Appendix D, ``Design Certification Rule for the AP1000,'' to part 52 of title 10 of the Code of Federal Regulations (10 CFR) and issuing License Amendment Nos. 99 and 98 to COLs, NPF-91 and NPF-92, respectively, to the licensee. The exemptions are required by paragraph A.4 of section VIII, ``Processes for Changes and Departures,'' appendix D, to 10 CFR part 52 to allow the licensee to depart from Tier 1 information. With the requested amendment, the licensee proposes changes to plant-specific Tier 1 information and corresponding changes to Appendix C. Specifically, the licensee proposes changes to plant-specific Tier 1, Table 2.2.4-1 and Figure 2.2.4-1 (Sheets 1 and 2) and corresponding changes to Appendix C of the COL to install two main feedwater thermal relief valves and two start-

    up feedwater thermal relief valves. The main feedwater thermal relief valves will be added to the main feedwater line between the main feedwater isolation valves and main feedwater control valves. The startup feedwater thermal relief valves will be added between the startup feedwater isolation valves and startup feedwater control valves. The proposed plant-specific DCD Tier 1 information and corresponding changes to Appendix C of the COL require additional changes to corresponding Tier 2 information in the Updated Final Safety Analysis Report, Chapter 3, ``Design of Structures, Components, Equipment, and Systems,'' and Chapter 10, ``Steam and Power Conversion.''

    Part of the justification for granting the exemptions was provided by the review of the amendments. Because the exemption is necessary in order to issue the requested license amendment, the NRC granted the exemptions and issued the amendments 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 exemptions 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 amendments were found to be acceptable as well. The combined safety evaluation is available in ADAMS under Accession No. ML17263A074.

    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. ML17263A079 and ML17263A078, respectively. The exemption is reproduced (with the exception of

    Page 6891

    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. ML17263A077 and ML17263A075, respectively. A summary of the amendment documents is provided in Section III of this document.

  2. Exemption

    Reproduced below is the exemption document issued to VEGP Units 3 and Unit 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 a letter dated April 21, 2017, revised on August 15, 2017, and supplemented by letter dated September 18, 2017, the licensee requested from the Commission an exemption from the provisions of 10 CFR part 52, appendix D, section III.B, as part of license amendment request 17-012, ``Addition of Steam Generator System (SGS) Thermal Relief Valves.''

      For the reasons set forth in Section 3.1, ``Evaluation of Exemption,'' of the NRC staff's Safety Evaluation, which can be found in ADAMS under Accession No. ML17263A074, the Commission finds that:

      1. The exemption is authorized by law;

      2. the exemption presents no undue risk to public health and safety;

      3. the exemption is consistent with the common defense and security;

      4. 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;

      5. the special circumstances outweigh any decrease in safety that may result from the reduction in standardization caused by the exemption; and

      6. 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, with corresponding changes to Appendix C of the Facility Combined Licenses as described in the licensee's request dated April 21, 2017, revised on August 15, 2017 and supplemented by letter dated September 18, 2017. This exemption is related to, and necessary for, the granting of License Amendment Nos. 99 and 98, which is being issued concurrently with this exemption.

    3. As explained in Section 5.0, ``Environmental Consideration,'' of the NRC staff's Safety Evaluation (ADAMS Accession No. ML17263A074), these exemptions 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.

    4. These exemptions are effective as of the date of its issuance.

  3. License Amendment Request

    By letter dated April 21, 2017, revised on August 15, 2017 and supplemented by letter dated September 18, 2017, the licensee requested that the NRC amend the COLs for VEGP, Units 3 and 4, COLs NPF-91 and NPF-92. The proposed amendment is described in Section I of this Federal Register notice.

    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 combined license, as applicable, proposed no significant hazards consideration determination, and opportunity for a hearing in connection with these actions, was published in the Federal Register on September 12, 2017 (82 FR 42844). 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.

  4. 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 April 21, 2017, revised on August 15, 2017, and supplemented by letter on September 18, 2017.

    The exemptions and amendments were issued on November 17, 2017, as part of a combined package to the licensee (ADAMS Accession No. ML17263A070).

    Dated at Rockville, Maryland, this 12th day of February, 2018.

    For the Nuclear Regulatory Commission.

    Jennifer L. Dixon-Herrity,

    Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of New Reactors.

    FR Doc. 2018-03167 Filed 2-14-18; 8:45 am

    BILLING CODE 7590-01-P

VLEX uses login cookies to provide you with a better browsing experience. If you click on 'Accept' or continue browsing this site we consider that you accept our cookie policy. ACCEPT