ML26007A173
| ML26007A173 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/14/2026 |
| From: | Geoffrey Miller Plant Licensing Branch II |
| To: | Carr E Dominion Energy South Carolina |
| Miller, GE | |
| References | |
| EPID L-2025-LLA-0054 | |
| Download: ML26007A173 (0) | |
Text
January 14, 2026 Mr. Eric S. Carr Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, VA 23060-6711
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 - CORRECTION TO ISSUANCE OF AMENDMENT NO. 228 TO MODIFY TECHNICAL SPECIFICATION 6.8.4.g TO MODIFY THE CONTAINMENT LEAKAGE RATE TESTING PROGRAM (EPID L-2025-LLA-0054)
Dear Mr. Carr:
On December 30, 2025 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML25342A206), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 228 to Subsequent Renewed Facility Operating License No. NPF-12 for the Virgil C. Summer Nuclear Station, Unit 1. The amendments revised the Technical Specifications (TSs) by replacing the reference to Nuclear Energy Institute (NEI)
Technical Report 94-01, Revision 2-A, Industry Guideline for Implementing Performance-Based Option 10 CFR 50, Appendix J, October 2008, with NEI Technical Report 94-01, Revision 3-A, July 2012, and conditions and limitations specified in NEI 94-01, Revision 2-A.
Subsequently, it was identified that the camera-ready license page 3 provided with the amendment request didnt reflect the recently issued subsequent license renewal content.
Accordingly, the corrected license page 3 is enclosed with this letter. The corrections do not change any of the conclusions associated with the issuance of Amendment No. 228 to Renewed Facility Operating License No. NPF-12, and do not affect the no significant hazards consideration published in the Federal Register on May 14, 2025 (90 FR 20516).
E. Carr If you have any questions, please contact me at 301-415-4032, or via email at Ed.Miller@nrc.gov.
Sincerely,
/RA/
G. Edward Miller, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
Corrected License Page 3 cc: Listserv
3 Subsequent Renewed Facility Operating License No. NPF-12 Amendment No. 228 (5)
DESC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus of components; and (6)
DESC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This subsequent renewed license shall be deemed to contain, and is subject to, the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level DESC is authorized to operate the facility at reactor core power levels not in excess of 2900 megawatts thermal in accordance with the conditions specified herein and in to this subsequent renewed license.
The preoperational tests, startup tests and other items identified in Attachment 1 to this subsequent renewed license shall be completed as specified. Attachment 1 is hereby incorporated into this subsequent renewed license.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 228, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the subsequent renewed license. Dominion Energy South Carolina, Inc.
shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Conduct of Work Activities During Fuel Load and Initial Startup DESC shall review by committee all facility construction, preoperational testing, and system demonstration activities performed concurrently with facility initial fuel loading or with the facility startup test program to assure that the activity will not affect the safe performance of the facility fuel loading or the portion of the facility startup program being performed. The review shall address, as a minimum, system interaction, span of control, staffing, security, and health physics, with respect to the performance of the activity concurrently with the facility fuel loading or the portion of the facility startup program being performed. The committee for the review shall be composed of at least three members, knowledgeable in the above areas, and who meet the qualifications for professional-technical personnel specified by Section 4.4 of ANSI N18.7-1971. At least one of these three shall be a senior member of the Plant Manager's staff.
ML26007A173 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME GEMiller KZeleznock MMarkley GEMiller DATE 01/07/2026 01/13/2026 01/14/2026 01/14/2026