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Virgil C. Summer Nuclear Station, Units 2 and 3 South Carolina Electric & Gas Company; Control Rod Drive Mechanism Motor Generator Set Field Relay Change

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Nuclear Regulatory Commission.


Exemption and combined license amendment; issuance.


The U.S. Nuclear Regulatory Commission (NRC) is granting an Start Printed Page 20689exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment No. 27 to Combined Licenses (COLs), 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.


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 and search for Docket ID NRC-2008-0441. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415-3463; email: 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​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 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 October 30, 2014 (ADAMS Accession No. ML14303A448).
  • 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.
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Paul Kallan, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-2809; email:

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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. 27 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 specifies the use of latching control relays in lieu of breakers to de-energize the control rod drive mechanism (CRDM) motor generator (MG) set generator field on a diverse actuation system (DAS) reactor trip signal. The replacement of the CRDM MG set generator field breakers with field control relays requires an updated final safety analysis report (UFSAR) Tier 2 departure that involves changes to COL Appendix C, Tables 2.5.1-4, “Inspections, Tests, Analyses, and Acceptance Criteria,” and 3.7-1, “Risk-Significant Components,” along with corresponding departures from plant-specific DCD Tier 1 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 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. ML15135A211.

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. ML15135A160 and ML15135A170, 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. ML15135A145 and ML15135A156, 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 Summer 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 October 30, 2014, 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 13-27, “Control Rod Mechanism Motor Generator Set Field Relay Change (LAR-13-27).”

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. ML15135A211, 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, COL appendix C, Table 2.5.1-4, and Table 3.7-1, as described in the licensee's request dated October 30, 2014. This exemption is related to, and necessary for the granting of License Amendment No. 27, 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. ML15135A211), 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 June 10, 2015.Start Printed Page 20690

III. License Amendment Request

By letter dated October 30, 2014, 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 document.

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 January 6, 2015 (80 FR 520). 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 October 30, 2014. The exemption and amendment were issued on June 10, 2015 as part of a combined package to the licensee (ADAMS Accession No. ML15135A140).

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Dated at Rockville, Maryland, this 31st day of March 2016.

For the Nuclear Regulatory Commission.

John McKirgan,

Acting Branch Chief, Licensing Branch 4, Division of New Reactor Licensing, Office of New Reactors.

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[FR Doc. 2016-08123 Filed 4-7-16; 8:45 am]