[Federal Register Volume 82, Number 81 (Friday, April 28, 2017)]
[Notices]
[Pages 19754-19755]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-08633]


=======================================================================
-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

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


South Carolina Electric & Gas Company, South Carolina Public 
Service Authority; Virgil C. Summer Nuclear Station, Units 2 and 3; 
Design Reliability Assurance Program (D-RAP) Changes

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. 70 to Combined Licenses (COLs), NPF-93 and NPF-
94. The COLs were issued to South Carolina Electric & Gas Company and 
the South Carolina Public Service Authority, (together referred to as 
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 April 11, 2017.

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: [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 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 (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 September 22, 2016 and is available in ADAMS under 
Accession No. ML16270A582.
     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: 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 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. 70 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 (UFSAR) 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. Specifically, the LAR revises 
the Design Reliability Assurance Program (D-RAP) to identify the covers 
for the in-containment refueling water storage tank (IRWST) vents and 
overflow weirs as the risk-significant components included in the D-RAP 
and to identify that the field control relays of each rod drive motor-
generator (MG) sets are a part of the rod drive power supply control 
cabinets in which the relays are located.
    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 Sec. Sec.  50.12, 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. ML17048A143.
    Similar exemption documents 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. 
ML17048A144 and ML17048A147, respectively. The exemption is reproduced 
(with the exception of abbreviated titles and additional citations) in 
Section II of this document. The similar amendment documents for COLs 
NPF-93 and NPF-94 are available in ADAMS under Accession Nos. 
ML17048A145 and ML17048A148, 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 an application dated September 22, 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

[[Page 19755]]

D, as part of license amendment request 16-14, ``Design Reliability 
Assurance Program (D-RAP) Changes.''
    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. 
ML17048A143, 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 related to the in-containment 
refueling water storage tank vents and overflow weirs, the rod drive 
motor-generator sets field control relays, and the rod drive power 
supply control cabinets, as described in the licensee's request dated 
September 22, 2016. This exemption is related to, and necessary for the 
granting of License Amendment No. 70, 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. ML17048A143), 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 September 22, 2016 (ADAMS Accession No. 
ML16270A582), 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 November 8, 2016 (81 FR 78652). 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 September 22, 2016.
    The exemption and amendment were issued on April 11, 2017, as part 
of a combined package to the licensee (ADAMS Accession No. 
ML17048A142).

    Dated at Rockville, Maryland, this 14th day of April 2017.

    For the Nuclear Regulatory Commission.
Brian Hughes,
Acting Branch Chief, Licensing Branch 4, Division of New Reactor 
Licensing, Office of New Reactors.
[FR Doc. 2017-08633 Filed 4-27-17; 8:45 am]
 BILLING CODE 7590-01-P