2018-02473. Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Station, Units 3 and 4; Addition of a Residual Heat Removal Suction Relief Valve for Low-Temperature Overpressure Protection
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Start Preamble
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 design control document (DCD) and is issuing License Amendment Nos. 104 and 103 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.
DATES:
The exemptions and amendments were issued on December 20, 2017.
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 Carol Start Printed Page 5466Gallagher; telephone: 301-415-3463; email: Carol.Gallagher@nrc.gov. 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 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 (if it is available in ADAMS) is provided the first time that it is mentioned in this document. The request for the amendment and exemption was submitted by letter dated July 14, 2017 (ADAMS Accession No. ML17195B047) and supplemented by letter dated October 3, 2017 (ADAMS Accession No. ML17276B537).
- 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: Paul.Kallan@nrc.gov.
End Further Info End Preamble Start Supplemental InformationSUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is granting an exemption 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. 104 and 103 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 to depart from Tier 2 information in the Updated Final Safety Analysis Report (which includes the plant-specific DCD Tier 2 information) and involves related changes to plant-specific Tier 1 (and associated COL Appendix C) information, and COL Appendix A, Technical Specifications. Specifically, the requested amendment proposes changes to add a second normal residual heat removal system (RNS) suction relief valve in parallel to the current RNS suction relief valve, with the necessary piping changes. Additionally, a change is proposed to Tier 1 Figure 2.2.1-1, for penetration P19, to accurately depict the orientation of the class break of containment isolation valve RNS-PL-V061.
Part of the justification for granting the exemption was provided by the review of the amendment. Because the exemption is necessary in order to issue the requested license amendment, the 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 amendments were found to be acceptable as well. The combined safety evaluation is available in ADAMS under Accession No. ML17332A521.
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. ML17332A515 and ML17332A516, 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. ML17332A517 and ML17332A519, 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 Vogtle 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 July 14, 2017, and supplemented by letter dated October 3, 2017, the licensee requested from the Commission an exemption to allow departures from Tier 1 information in the certified DCD incorporated by reference 10 CFR part 52, appendix D, “Design Certification Rule for the AP1000 Design,” as part of license amendment request (LAR) 17-022, “Addition of a Residual Heat Removal Suction Relief Valve for Low-Temperature Overpressure Protection.”
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. ML17332A521, 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;
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, with corresponding changes to Appendix C of the Facility Combined Licenses as described in the licensee's request dated July 14, 2017, and supplemented by letter dated October 3, 2017. This exemption is related to, and necessary for, the granting of License Amendment Nos. 104 (Unit 3) and 103 (Unit 4), 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. ML17332A521), 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.
III. License Amendment Request
By letter dated July 14, 2017, and supplemented by letter dated October 3, 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 Start Printed Page 546710 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.
IV. Conclusion
Using the reasons set forth in the combined safety evaluation, the staff granted the exemptions and issued the amendments that the licensee requested on July 14, 2017 and supplemented October 3, 2017.
The exemptions and amendments were issued on December 20, 2017 as part of a combined package to the licensee (ADAMS Accession No. ML17332A513).
Start SignatureDated at Rockville, Maryland, this 2nd 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. 2018-02473 Filed 2-6-18; 8:45 am]
BILLING CODE 7590-01-P
Document Information
- Published:
- 02/07/2018
- Department:
- Nuclear Regulatory Commission
- Entry Type:
- Notice
- Action:
- Exemption and combined license amendment; issuance.
- Document Number:
- 2018-02473
- Dates:
- The exemptions and amendments were issued on December 20, 2017.
- Pages:
- 5465-5467 (3 pages)
- Docket Numbers:
- Docket Nos. 52-025 and 52-026, NRC-2008-0252
- PDF File:
- 2018-02473.pdf
- Supporting Documents:
- » Southern Nuclear Operating Company Inc; Vogtle Electric Generating Plant Units 3 and 4
- » Southern Nuclear Operating Company Inc; Vogtle Electric Generating Plant Units 3 and 4
- » Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Inspections, Tests, Analyses, and Acceptance Criteria
- » Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Main Control Room Emergency Habitability System Changes
- » Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; PXS/ADS Line Resistance Changes
- » Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Pipe Rupture Hazard and Flooding Analysis
- » Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Station, Units 3 and 4; Addition of a Residual Heat Removal Suction Relief Valve for Low-Temperature Overpressure Protection; Exemption and Combined License Amendment; Issuance
- » Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Units 3 and 4; Clarification of Raceway and Raceway System Designations; Issuance of Exemption and Combined License Amendment
- » Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Units 3 and 4; Central Chilled Water System Optimization Changes; Issuance of Exemption and Combined License Amendment
- » Southern Nuclear Operating Company, Inc. Vogtle Electric Generating Plant, Units 3 and 4, Inspections, Tests, Analyses, and Acceptance Criteria; Determination of Successful Completion of Inspections, Tests, and Analyses