South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Units 2 and 3; Passive Core Cooling System (PXS) Design Changes To Address Potential Gas Intrusion, 9080-9081 [2017-02211]

Download as PDF 9080 Federal Register / Vol. 82, No. 21 / Thursday, February 2, 2017 / Notices mstockstill on DSK3G9T082PROD with NOTICES portions that may be closed to protect information that is proprietary pursuant to 5 U.S.C. 552b(c)(4). The agenda for the subject meeting shall be as follows: Wednesday, February 22, 2017—8:30 a.m. Until 5:00 p.m. The Subcommittee will receive a briefing on Advanced Reactor Design Criteria. The Subcommittee will hear presentations by and hold discussions with the NRC staff 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), Michael Snodderly (Telephone 301–415–2241 or Email: Michael.Snodderly@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 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. Detailed procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on October 17, 2016, (81 FR 71543). Detailed meeting agendas and meeting transcripts are available on the NRC Web site at http://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 Web site 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 One White Flint North building, 11555 Rockville Pike, Rockville, Maryland. After registering with Security, please contact Mr. VerDate Sep<11>2014 16:31 Feb 01, 2017 Jkt 241001 Theron Brown (Telephone 240–888– 9835) to be escorted to the meeting room. Dated: January 26, 2017. Mark L. Banks, Chief, Technical Support Branch, Advisory Committee on Reactor Safeguards. [FR Doc. 2017–02213 Filed 2–1–17; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 52–027 and 52–028; NRC– 2008–0441] South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Units 2 and 3; Passive Core Cooling System (PXS) Design Changes To Address Potential Gas Intrusion Nuclear Regulatory Commission. ACTION: Exemption and combined license amendment; issuance. AGENCY: 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 No. 56 to Combined Licenses (COL), NPF– 93 and NPF–94. The COLs were issued to South Carolina Electric & Gas Company (the licensee); for construction and operation of the Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3, located in Fairfield County, South Carolina. The granting of the exemption allows the changes to Tier 1 information asked for 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 exemption and amendment were issued on November 25, 2016. ADDRESSES: Please refer to Docket ID NRC–2008–0441 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 Web site: Go to http://www.regulations.gov and search for Docket ID NRC–2008–0441. Address questions about NRC dockets to Carol Gallagher; 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. SUMMARY: PO 00000 Frm 00026 Fmt 4703 Sfmt 4703 • 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. The request for the amendment and exemption was submitted by letter dated June 2, 2016 (ADAMS Accession No. ML16154A226). • 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. SUPPLEMENTARY 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 No. 56 to COLs, NPF–93 and NPF–94, to the licensee. 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 the licensee to depart from Tier 1 information. With the requested amendment, the licensee sought proposed changes that would revise the Updated Final Safety Analysis Report in the form of departures from the incorporated plantspecific DCD Tier 2 information. The proposed amendment also involves related changes to plant-specific Tier 1 information, with corresponding changes to the associated COL Appendix C information. 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 E:\FR\FM\02FEN1.SGM 02FEN1 Federal Register / Vol. 82, No. 21 / Thursday, February 2, 2017 / Notices 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. ML16301A270. Identical exemption documents (except for referenced unit numbers and license numbers) were issued to the licensee for VCSNS Units 2 and 3 (COLs NPF–93 and NPF–94). The exemption documents for VCSNS Units 2 and 3 can be found in ADAMS under Accession Nos. ML16301A217 and ML16301A229, 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–93 and NPF–94 are available in ADAMS under Accession Nos. ML16301A198 and ML16301A203, respectively. A summary of the amendment documents is provided in Section III of this document. mstockstill on DSK3G9T082PROD with NOTICES II. Exemption Reproduced below is the exemption document issued to VCSNS Units 2 and Unit 3. 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 June 2, 2016, 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 16–02, ‘‘Passive Core Cooling System (PXS) Design Changes to Address Potential Gas Intrusion (LAR–16–02).’’ 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. ML16301A270, 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 VerDate Sep<11>2014 16:31 Feb 01, 2017 Jkt 241001 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 June 2, 2016. This exemption is related to, and necessary for, the granting of License Amendment No. 56, 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. ML16301A270), 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 June 2, 2016, the licensee requested that the NRC amend the COLs for VCSNS, Units 2 and 3, COLs NPF–93 and NPF–94. 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 13, 2016 (81 FR 62926). No comments were received during the 30day 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 00027 Fmt 4703 Sfmt 4703 9081 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 June 2, 2016. The exemption and amendment were issued on November 25, 2016 as part of a combined package to the licensee (ADAMS Accession No. ML16301A175). Dated at Rockville, Maryland, this 25th day of January 2017. For the Nuclear Regulatory Commission. Jennifer Dixon-Herrity, Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. 2017–02211 Filed 2–1–17; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Future Plant Designs; Notice of Meeting The ACRS Subcommittee on Future Plant Designs will hold a meeting on February 23, 2017, Room T–2B1, 11545 Rockville Pike, Rockville, Maryland. The meeting will be open to public attendance. The agenda for the subject meeting shall be as follows: Thursday, February 23, 2017—8:30 a.m. Until 12:00 p.m. The Subcommittee will review the design acceptance criteria inspection progress and results for piping and human factors. The Subcommittee will hear presentations by and hold discussions with the NRC staff 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), Christina Antonescu (Telephone 301–415–6792 or Email: Christina.Antonescu@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 timeframe, presenters should provide the DFO with a CD E:\FR\FM\02FEN1.SGM 02FEN1

Agencies

[Federal Register Volume 82, Number 21 (Thursday, February 2, 2017)]
[Notices]
[Pages 9080-9081]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-02211]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 52-027 and 52-028; NRC-2008-0441]


South Carolina Electric & Gas Company Virgil C. Summer Nuclear 
Station, Units 2 and 3; Passive Core Cooling System (PXS) Design 
Changes To Address Potential Gas Intrusion

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 No. 56 to Combined Licenses (COL), NPF-93 and NPF-94. 
The COLs were issued to South Carolina Electric & Gas Company (the 
licensee); for construction and operation of the Virgil C. Summer 
Nuclear Station (VCSNS) Units 2 and 3, located in Fairfield County, 
South Carolina.
    The granting of the exemption allows the changes to Tier 1 
information asked for 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 exemption and amendment were issued on November 25, 2016.

ADDRESSES: Please refer to Docket ID NRC-2008-0441 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 Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2008-0441. Address 
questions about NRC dockets to Carol Gallagher; 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 June 2, 2016 (ADAMS Accession No. ML16154A226).
     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.

SUPPLEMENTARY 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 No. 56 to COLs, NPF-93 and NPF-
94, to the licensee. 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 the licensee to depart from Tier 1 information. 
With the requested amendment, the licensee sought proposed changes that 
would revise the Updated Final Safety Analysis Report in the form of 
departures from the incorporated plant-specific DCD Tier 2 information. 
The proposed amendment also involves related changes to plant-specific 
Tier 1 information, with corresponding changes to the associated COL 
Appendix C information.
    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

[[Page 9081]]

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. ML16301A270.
    Identical exemption documents (except for referenced unit numbers 
and license numbers) were issued to the licensee for VCSNS Units 2 and 
3 (COLs NPF-93 and NPF-94). The exemption documents for VCSNS Units 2 
and 3 can be found in ADAMS under Accession Nos. ML16301A217 and 
ML16301A229, 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-93 and NPF-94 
are available in ADAMS under Accession Nos. ML16301A198 and 
ML16301A203, 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 VCSNS Units 2 
and Unit 3. 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 June 2, 2016, 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 16-02, ``Passive 
Core Cooling System (PXS) Design Changes to Address Potential Gas 
Intrusion (LAR-16-02).''
    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. ML16301A270, 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 June 2, 2016. This exemption is related to, 
and necessary for, the granting of License Amendment No. 56, 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. ML16301A270), 
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 June 2, 2016, the licensee requested that the NRC 
amend the COLs for VCSNS, Units 2 and 3, COLs NPF-93 and NPF-94. 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 13, 2016 (81 FR 62926). 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 exemption and issued the amendment that the licensee 
requested on June 2, 2016. The exemption and amendment were issued on 
November 25, 2016 as part of a combined package to the licensee (ADAMS 
Accession No. ML16301A175).

    Dated at Rockville, Maryland, this 25th day of January 2017.

    For the Nuclear Regulatory Commission.
Jennifer Dixon-Herrity,
Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of 
New Reactors.
[FR Doc. 2017-02211 Filed 2-1-17; 8:45 am]
 BILLING CODE 7590-01-P