Southern Nuclear Operating Company, Inc.; Vogtle Electric Generating Plant, Units 3 and 4; Fire Protection System Nonsafety Cable Spray Removal, 53665-53666 [2018-23191]

Download as PDF Federal Register / Vol. 83, No. 206 / Wednesday, October 24, 2018 / Notices 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; Fire Protection System Nonsafety Cable Spray Removal Nuclear Regulatory Commission. ACTION: Combined license amendment; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing License Amendment Nos. 145 and 144 to Combined Licenses (COL), NPF–91 and NPF–92, respectively. The COLs were issued to Southern Nuclear Operating Company, 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 (collectively SNC); for construction and operation of the Vogtle Electric Generating Plant (VEGP) Units 3 and 4, located in Burke County, Georgia. The amendment authorizes changes in the form of departures to the VEGP Units 3 and 4 plant specific Design Control Document (PS–DCD) Tier 2 information contained within the Updated Final Safety Analysis Report and plant-specific Tier 1 information, with corresponding changes to Appendix C of the COL removing the fire protection system (FPS) nonsafetyrelated containment cable spray and installing passive fire stops and radiant energy shields. Specifically, the changes were for the removal of the FPS containment open nozzle water spray suppression system for the open nonsafety-related cable trays in fire zone 1100 AF 11300B and for installing passive fire stops and radiant energy shields. The exemption allows changes that impact Tier 1 of the PS–DCD and associated COL Appendix C of the Facility COL as specified in LAR 18– 015. This exemption is related to, and necessary for, the granting of the amendment which is being issued concurrently. DATES: The amendments were issued on October 4, 2018. ADDRESSES: Please refer to Docket ID NRC–2008–0252 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods: • Federal Rulemaking website: Go https://www.regulations.gov and search amozie on DSK3GDR082PROD with NOTICES1 SUMMARY: VerDate Sep<11>2014 17:43 Oct 23, 2018 Jkt 247001 for Docket ID NRC–2008–0252. Address questions about NRC dockets to Jennifer Borges; 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. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 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 April 27, 2018, designated License Amendment Request (LAR) 18–015, and supplemented by letter dated August 13, 2018 (ADAMS Accession Nos. ML18117A464 and ML18225A291, respectively). • 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: William (Billy) Gleaves, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone: 301–415–5848; email: Bill.Gleaves@nrc.gov. SUPPLEMENTARY INFORMATION: I. 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. 138 and 137 to COLs, NPF–91 and NPF–92, respectively, to SNC. The exemption is required by paragraph A.4 of section VIII, ‘‘Processes for Changes and Departures,’’ appendix D, to 10 CFR part 52 to allow SNC to depart from Tier 1 information. 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 met all applicable regulatory criteria and were found to be acceptable as well. The combined safety evaluation is available in ADAMS under Accession No. ML18247A407. PO 00000 Frm 00062 Fmt 4703 Sfmt 4703 53665 Identical exemption documents (except for referenced unit numbers and license numbers) were issued to SNC 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. ML18247A405 and ML18247A406, 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. ML18247A401 and ML18247A403, 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 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 27, 2018, as supplemented August 13, 2018, SNC requested from the Nuclear Regulatory Commission (NRC or Commission) an exemption to allow departure from Tier 1 information in the certified DCD incorporated by reference in Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Appendix D, ‘‘Design Certification Rule for the AP1000 Design,’’ as part of license amendment request (LAR) 18–015, ‘‘Fire Protection System Non-Safety Cable Spray Removal.’’ For the reasons set forth in Section 3.2 of the NRC staff’s Safety Evaluation, which can be found be found in ADAMS under Accession Number ML18247A407, 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, SNC is granted an exemption from the certified DCD Tier 1 information, with corresponding changes to Appendix C of the Facility E:\FR\FM\24OCN1.SGM 24OCN1 53666 Federal Register / Vol. 83, No. 206 / Wednesday, October 24, 2018 / Notices amozie on DSK3GDR082PROD with NOTICES1 Combined License, as described in the licensee’s request dated April 27, 2018, as supplemented August 13, 2018. This exemption is related to, and necessary for the granting of License Amendment No. 145 (Unit 3) and 144, which is being issued concurrently with this exemption. 3. As explained in Section 5.0 of the NRC staff’s Safety Evaluation (ADAMS Accession Number ML18247A407), 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. 4. This exemption is effective as of the date of its issuance. III. License Amendment Request By letter dated April 27, 2018, designated License Amendment Request (LAR) 18–015, and supplemented by letter dated August 13, 2018 (ADAMS Accession Nos. ML18117A464 and ML18225A291, respectively), 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 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 June 19, 2018 (83 FR 28463). 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 SNC requested by VerDate Sep<11>2014 17:43 Oct 23, 2018 Jkt 247001 letter dated April 27, 2018, supplemented by letter dated August 13, 2018 (ADAMS Accession Nos. ML18117A464 and ML18225A291, respectively). The exemptions and amendments were issued to the licensee on October 4, 2018, as part of a combined package (ADAMS Accession No. ML18247A399). Dated at Rockville, Maryland, on October 19, 2018. For the Nuclear Regulatory Commission. Jennifer L. Dixon-Herrity, Chief, Licensing Branch 4, Division of Licensing, Siting, and Environmental Analysis, Office of New Reactors. [FR Doc. 2018–23191 Filed 10–23–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Meeting of the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Future Plant Designs The ACRS Subcommittee on Future Plant Designs will hold a meeting on October 30, 2018 at U.S. Nuclear Regulatory Commission, Three White Flint North, 11601 Landsdown Street, Conference Rooms 1C3–1C5, North Bethesda, MD 20852. The entire meeting will be open to public attendance. The agenda for the subject meeting shall be as follows: Tuesday, October 30, 2018—8:30 a.m. Until 5:00 p.m. The Subcommittee will review guidance documents developed by the Advanced Reactor Licensing Modernization Program. The Subcommittee will hear presentations by and hold discussions with NRC staff, industry representatives, and other interested persons regarding this matter. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the Full Committee. Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official (DFO), Derek Widmayer (Telephone 301–221–1448 or Email Derek.Widmayer@nrc.gov) five days prior to the meeting, if possible, so that appropriate arrangements can be made. Thirty-five hard copies of each presentation or handout should be provided to the DFO thirty minutes before the meeting. In addition, one electronic copy of each presentation should be emailed to the DFO one day before the meeting. If an electronic copy cannot be provided within this PO 00000 Frm 00063 Fmt 4703 Sfmt 4703 timeframe, presenters should provide the DFO with a CD containing each presentation at least thirty minutes before the meeting. Electronic recordings will be permitted only during those portions of the meeting that are open to the public. The public bridgeline number for the meeting is 866–822–3032, passcode 8272423. Detailed procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on October 4, 2017 (82 FR 46312). Detailed meeting agendas and meeting transcripts are available on the NRC website at https://www.nrc.gov/readingrm/doc-collections/acrs. Information regarding topics to be discussed, changes to the agenda, whether the meeting has been canceled or rescheduled, and the time allotted to present oral statements can be obtained from the website cited above or by contacting the identified DFO. Moreover, in view of the possibility that the schedule for ACRS meetings may be adjusted by the Chairman as necessary to facilitate the conduct of the meeting, persons planning to attend should check with these references if such rescheduling would result in a major inconvenience. If attending this meeting, please enter through the Three White Flint North building, 11601 Landsdown Street, North Bethesda, MD 20852. After registering with Security, please proceed to conference room 1C3–1C5, located directly behind the security desk on the first floor. You may contact Mr. Theron Brown (Telephone 301– 415–6702) for assistance or to be escorted to the meeting room. Dated: October 18, 2018. Mark L. Banks, Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards. [FR Doc. 2018–23169 Filed 10–23–18; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [License No. XW019; Docket No. 11005986; NRC–2012–7946] Perma-Fix Northwest Richland, Inc. Nuclear Regulatory Commission. ACTION: Export license application; opportunity to comment, request a hearing, and petition for leave to intervene. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is reviewing an export license application (XW019), SUMMARY: E:\FR\FM\24OCN1.SGM 24OCN1

Agencies

[Federal Register Volume 83, Number 206 (Wednesday, October 24, 2018)]
[Notices]
[Pages 53665-53666]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-23191]



[[Page 53665]]

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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; Fire Protection System Nonsafety Cable 
Spray Removal

AGENCY: Nuclear Regulatory Commission.

ACTION: Combined license amendment; issuance.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing 
License Amendment Nos. 145 and 144 to Combined Licenses (COL), NPF-91 
and NPF-92, respectively. The COLs were issued to Southern Nuclear 
Operating Company, 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 (collectively SNC); for 
construction and operation of the Vogtle Electric Generating Plant 
(VEGP) Units 3 and 4, located in Burke County, Georgia.
    The amendment authorizes changes in the form of departures to the 
VEGP Units 3 and 4 plant specific Design Control Document (PS-DCD) Tier 
2 information contained within the Updated Final Safety Analysis Report 
and plant-specific Tier 1 information, with corresponding changes to 
Appendix C of the COL removing the fire protection system (FPS) 
nonsafety-related containment cable spray and installing passive fire 
stops and radiant energy shields. Specifically, the changes were for 
the removal of the FPS containment open nozzle water spray suppression 
system for the open nonsafety-related cable trays in fire zone 1100 AF 
11300B and for installing passive fire stops and radiant energy 
shields.
    The exemption allows changes that impact Tier 1 of the PS-DCD and 
associated COL Appendix C of the Facility COL as specified in LAR 18-
015. This exemption is related to, and necessary for, the granting of 
the amendment which is being issued concurrently.

DATES: The amendments were issued on October 4, 2018.

ADDRESSES: Please refer to Docket ID NRC-2008-0252 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly-available information related to this document 
using any of the following methods:
     Federal Rulemaking website: Go https://www.regulations.gov 
and search for Docket ID NRC-2008-0252. Address questions about NRC 
dockets to Jennifer Borges; 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 obtain publicly-available documents online in the 
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS 
Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 800-397-4209, 301-415-4737, or 
by email to [email protected]. 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 April 27, 2018, 
designated License Amendment Request (LAR) 18-015, and supplemented by 
letter dated August 13, 2018 (ADAMS Accession Nos. ML18117A464 and 
ML18225A291, respectively).
     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: William (Billy) Gleaves, Office of New 
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-5848; email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. 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. 138 and 137 to COLs, NPF-91 
and NPF-92, respectively, to SNC. The exemption is required by 
paragraph A.4 of section VIII, ``Processes for Changes and 
Departures,'' appendix D, to 10 CFR part 52 to allow SNC to depart from 
Tier 1 information. 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 met all 
applicable regulatory criteria and were found to be acceptable as well. 
The combined safety evaluation is available in ADAMS under Accession 
No. ML18247A407.
    Identical exemption documents (except for referenced unit numbers 
and license numbers) were issued to SNC 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. ML18247A405 and ML18247A406, 
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. ML18247A401 and ML18247A403, 
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 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 27, 2018, as supplemented August 13, 
2018, SNC requested from the Nuclear Regulatory Commission (NRC or 
Commission) an exemption to allow departure from Tier 1 information in 
the certified DCD incorporated by reference in Title 10 of the Code of 
Federal Regulations (10 CFR) Part 52, Appendix D, ``Design 
Certification Rule for the AP1000 Design,'' as part of license 
amendment request (LAR) 18-015, ``Fire Protection System Non-Safety 
Cable Spray Removal.''
    For the reasons set forth in Section 3.2 of the NRC staff's Safety 
Evaluation, which can be found be found in ADAMS under Accession Number 
ML18247A407, 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, SNC is granted an exemption from the certified DCD 
Tier 1 information, with corresponding changes to Appendix C of the 
Facility

[[Page 53666]]

Combined License, as described in the licensee's request dated April 
27, 2018, as supplemented August 13, 2018. This exemption is related 
to, and necessary for the granting of License Amendment No. 145 (Unit 
3) and 144, which is being issued concurrently with this exemption.
    3. As explained in Section 5.0 of the NRC staff's Safety Evaluation 
(ADAMS Accession Number ML18247A407), 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.
    4. This exemption is effective as of the date of its issuance.

III. License Amendment Request

    By letter dated April 27, 2018, designated License Amendment 
Request (LAR) 18-015, and supplemented by letter dated August 13, 2018 
(ADAMS Accession Nos. ML18117A464 and ML18225A291, respectively), 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 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 
June 19, 2018 (83 FR 28463). 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 SNC 
requested by letter dated April 27, 2018, supplemented by letter dated 
August 13, 2018 (ADAMS Accession Nos. ML18117A464 and ML18225A291, 
respectively). The exemptions and amendments were issued to the 
licensee on October 4, 2018, as part of a combined package (ADAMS 
Accession No. ML18247A399).

    Dated at Rockville, Maryland, on October 19, 2018.

    For the Nuclear Regulatory Commission.
Jennifer L. Dixon-Herrity,
Chief, Licensing Branch 4, Division of Licensing, Siting, and 
Environmental Analysis, Office of New Reactors.
[FR Doc. 2018-23191 Filed 10-23-18; 8:45 am]
 BILLING CODE 7590-01-P
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