Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Units 3 and 4; Automatic Depressurization System Stage 2, 3 & 4 Valve Flow Area Changes and Clarifications, 8440-8441 [2017-01695]

Download as PDF 8440 Federal Register / Vol. 82, No. 15 / Wednesday, January 25, 2017 / Notices outreach; and may be required to provide supporting documentation. The completed Profile is returned to NCUA 15 days after receipt by the contractor. Type of Review: New collection. Affected Public: Private Sector: Businesses or other for-profits. Estimated Total Annual Burden Hours: 38. By Gerard Poliquin, Secretary of the Board, the National Credit Union Administration, on January 19, 2017. Dated: January 19, 2017. Dawn D. Wolfgang, NCUA PRA Clearance Officer. [FR Doc. 2017–01654 Filed 1–24–17; 8:45 am] NATIONAL TRANSPORTATION SAFETY BOARD Sunshine Act Meeting 9:30 a.m., Tuesday, February 7, 2017. PLACE: NTSB Conference Center, 429 L’Enfant Plaza SW., Washington, DC 20594. STATUS: The one item is open to the public. MATTERS TO BE CONSIDERED: 8620A Railroad Accident Report— BNSF Railway Train Derailment and Subsequent Train Collision, Release of Hazardous Materials, and Fire, Casselton, North Dakota (DCA14MR004) NEWS MEDIA CONTACT: Telephone: (202) 314–6100. The press and public may enter the NTSB Conference Center one hour prior to the meeting for set up and seating. Individuals requesting specific accommodations should contact Rochelle Hall at (202) 314–6305 or by email at Rochelle.Hall@ntsb.gov by Wednesday, February 1, 2017. The public may view the meeting via a live or archived webcast by accessing a link under ‘‘News & Events’’ on the NTSB home page at www.ntsb.gov. Schedule updates, including weatherrelated cancellations, are also available at www.ntsb.gov. FOR MORE INFORMATION CONTACT: Candi Bing at (202) 314–6403 or by email at bingc@ntsb.gov. FOR MEDIA INFORMATION CONTACT: Eric Weiss at (202) 314–6100 or by email at eric.weiss@ntsb.gov. mstockstill on DSK3G9T082PROD with NOTICES TIME AND DATE: Dated: January 23, 2017. Candi R. Bing, Federal Register Liaison Officer. [FR Doc. 2017–01758 Filed 1–23–17; 11:15 am] BILLING CODE 7533–01–P 20:29 Jan 24, 2017 [Docket Nos. 52–025 and 52–026; NRC– 2008–0252] Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Units 3 and 4; Automatic Depressurization System Stage 2, 3 & 4 Valve Flow Area Changes and Clarifications 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. 62 to Combined Licenses (COLs), NPF– 91 and NPF–92. 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, Authority of Georgia, 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 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. SUMMARY: BILLING CODE 7535–01–P VerDate Sep<11>2014 NUCLEAR REGULATORY COMMISSION Jkt 241001 The exemption and amendment were issued on December 29, 2016. 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 Web site: Go to http://www.regulations.gov and search for Docket ID NRC–2008–0252. 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 publiclyavailable documents online in the DATES: PO 00000 Frm 00045 Fmt 4703 Sfmt 4703 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 25, 2016 (ADAMS Accession No. ML16207A340). • 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: Chandu Patel, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415–3025; email: Chandu.Patel@ 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. 62 to COLs, NPF–91 and NPF–92, to the licensee. The exemption is required by paragraph A.4 of Section VIII, ‘‘Processes for Changes and Departures,’’ of 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 allow changes in appendix C of the COLs to clarify the flow area for the Automatic Depressurization System (ADS) fourth stage squib valves and to reduce the minimum effective flow area for the second and third stage ADS control valves. 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 E:\FR\FM\25JAN1.SGM 25JAN1 Federal Register / Vol. 82, No. 15 / Wednesday, January 25, 2017 / Notices mstockstill on DSK3G9T082PROD with NOTICES 10 CFR 50.12, and 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. ML16357A681. 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. ML16357A659 and ML16357A665, 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. ML16357A651 and ML16357A654, 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 July 25, 2016, the licensee requested from the Commission an exemption to allow departures from Tier 1 information in the certified DCD incorporated by reference in 10 CFR part 52, appendix D, as part of license amendment request 16–012, ‘‘Automatic Depressurization System (ADS) Stage 2, 3, and 4 Valve Flow Area Changes and Clarifications.’’ 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. ML16357A681, 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 VerDate Sep<11>2014 20:29 Jan 24, 2017 Jkt 241001 changes to Appendix C of the Facility Combined Licenses as described in the licensee’s request dated July 25, 2016. This exemption is related to, and necessary for, the granting of License Amendment No. 62, 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. ML16357A681), 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 July 25, 2016 (ADAMS Accession No. ML16207A340), 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 August 30, 2016 (81 FR 59659). 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 dated July 25, 2016. The exemption and amendment were issued on December 29, 2016, as part of a PO 00000 Frm 00046 Fmt 4703 Sfmt 4703 8441 combined package to the licensee (ADAMS Accession No. ML16357A640). Dated at Rockville, Maryland, this 17th 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. 2017–01695 Filed 1–24–17; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on APR 1400; Notice of Meeting The ACRS Subcommittee on APR 1400 will hold a meeting on February 8, 2017, Room T–2B1, 11545 Rockville Pike, Rockville, Maryland. The meeting will be open to public attendance with the exception of 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 8, 2017—8:30 a.m. Until 5:00 p.m. The Subcommittee will review topical reports related to the APR 1400 Design Control Document, Chapter 4, ‘‘Reactor.’’ 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), Christopher Brown (Telephone 301–415–7111 or Email: Christopher.Brown@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 E:\FR\FM\25JAN1.SGM 25JAN1

Agencies

[Federal Register Volume 82, Number 15 (Wednesday, January 25, 2017)]
[Notices]
[Pages 8440-8441]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-01695]


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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; Automatic Depressurization System 
Stage 2, 3 & 4 Valve Flow Area Changes and Clarifications

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. 62 to Combined Licenses (COLs), NPF-91 and NPF-
92. 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, Authority of 
Georgia, 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 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 December 29, 2016.

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 Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2008-0252. 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 July 25, 2016 (ADAMS Accession No. ML16207A340).
     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: Chandu Patel, Office of New Reactors, 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; 
telephone: 301-415-3025; email: Chandu.Patel@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. 62 to COLs, NPF-91 and NPF-
92, to the licensee. The exemption is required by paragraph A.4 of 
Section VIII, ``Processes for Changes and Departures,'' of 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 allow changes in appendix C of the COLs to clarify 
the flow area for the Automatic Depressurization System (ADS) fourth 
stage squib valves and to reduce the minimum effective flow area for 
the second and third stage ADS control valves.
    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

[[Page 8441]]

10 CFR 50.12, and 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. 
ML16357A681.
    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. ML16357A659 and 
ML16357A665, 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. ML16357A651 and 
ML16357A654, 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 July 25, 2016, the licensee requested from the 
Commission an exemption to allow departures from Tier 1 information in 
the certified DCD incorporated by reference in 10 CFR part 52, appendix 
D, as part of license amendment request 16-012, ``Automatic 
Depressurization System (ADS) Stage 2, 3, and 4 Valve Flow Area Changes 
and Clarifications.''
    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. 
ML16357A681, 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 25, 2016. This exemption is related to, 
and necessary for, the granting of License Amendment No. 62, 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. ML16357A681), 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 July 25, 2016 (ADAMS Accession No. ML16207A340), 
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 
August 30, 2016 (81 FR 59659). 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 dated July 25, 2016. The exemption and amendment were 
issued on December 29, 2016, as part of a combined package to the 
licensee (ADAMS Accession No. ML16357A640).

    Dated at Rockville, Maryland, this 17th 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. 2017-01695 Filed 1-24-17; 8:45 am]
 BILLING CODE 7590-01-P