ML26040A262
| ML26040A262 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/11/2026 |
| From: | Edwards T Plant Licensing Branch 1 |
| To: | Carr E Dominion Nuclear Connecticut |
| References | |
| Download: ML26040A262 (0) | |
Text
February 11, 2026 Mr. Eric S. Carr Chief Nuclear Officer and President Nuclear Operations and Contracted Energy Dominion Energy Nuclear Connecticut, Inc.
Millstone Power Station Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - CORRECTION OF TYPOGRAPHICAL ERRORS INCURRED DURING ISSUANCE OF AMENDMENT NO. 293
Dear Mr. Carr:
On December 16, 2025 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML25339A001), the U.S. Nuclear Regulatory Commission (NRC, the Commission) issued Amendment No. 293 to Renewed Facility Operating License No. NPF-49 for Millstone Power Station, Unit No. 3. The amendment revised the Steam Generator (SG)
Program and the Steam Generator Tube Inspection Report TSs based on Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections (TSTF-577) ML21060B434), and the associated NRC staff safety evaluation (SE) of TSTF-577 (ML21098A188).
Recently, the Commission was notified of typographical errors on TS pages 6-17c and 6-21a that did not align with the conclusions made by the Commission.
The purpose of this letter is to issue a correction to TS pages 6-17c and 6-21a for Amendment No. 293. The NRC concludes that corrections are entirely editorial in nature and do not change the staffs previous conclusion in the safety evaluation for Amendment No. 293, nor does it affect the no significant hazards consideration, as published in the Federal Register on June 10, 2025 (90 FR 24420). Enclosed, please find the corrected TS pages 6-17c and 6-21a.
If you have any questions regarding this matter, please contact me at (301) 415-1721 or by email at Theo.Edwards@nrc.gov Sincerely,
/RA/
Theo Edwards, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosure:
Corrections to Amendment No. 293 cc: Listserv
ENCLOSURE MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423 CORRECTED PAGES TO LICENSE AMENDMENT NO. 293 RENEWED FACILITY OPERATING LICENSE NO. NPF-49 TECHNICAL SPECIFICATION PAGES 6-17C AND 6-21A
MILLSTONE - UNIT 3 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) d.
Provisions for SG tube inspections: Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet except for any portions of the tube that are exempt from inspection by alternate repair criteria, and that may satisfy the applicable tube plugging criteria. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the next SG inspection. A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.
- 1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation.
- 2. After the first refueling outage following SG installation, inspect 100% of the tubes in each SG at least every 54 effective full power months, which defines the inspection period. If none of the SG tubes have ever experienced cracking other than in regions that are exempt from inspection by alternate repair criteria and the SG inspection was performed with enhanced probes, the inspection period may be extended to 72 effective full power months. Enhanced probes have a capability to detect flaws of any type equivalent to or better than array probe technology. The enhanced probes shall be used from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet except any portions of the tube that are exempt from inspection by alternate repair criteria. If there are regions where enhanced probes cannot be used, the tube inspection techniques shall be capable of detecting all forms of existing and potential degradation in that region.*
As approved by License Amendment No. 277, inspection of the Millstone Unit 3 SGs A and C may be deferred, on a one-time basis, from fall 2020 (Refueling Outage 20) to spring 2022 (Refueling Outage 21).
Amendment No. 69, 186, 212, 238, 243, 245, 249, 252, 255, 256, 277, 6-17c
MILLSTONE - UNIT 3 ADMINISTRATIVE CONTROLS STEAM GENERATOR TUBE INSPECTION REPORT 6.9.1.7 A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with TS 6.8.4.g, Steam Generator (SG) Program. The report shall include:
a.
The scope of inspections performed on each SG; b.
The nondestructive examination techniques utilized for tubes with increased degradation susceptibility; c.
For each degradation mechanism found:
1.
The nondestructive examination techniques utilized; 2.
The location, orientation (if linear), measured size (if available), and voltage response for each indication. For tube wear at support structures less than 20 percent through-wall, only the total number of indications needs to be reported; 3.
A description of the condition monitoring assessment and results, including the margin to the tube integrity performance criteria and comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment; and 4.
The number of tubes plugged during the inspection outage.
d.
An analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection (the forward-looking tube integrity assessment) relative to the applicable performance criteria, including the analysis methodology, inputs, and results; e.
The number and percentage of tubes plugged to date, and the effective plugging percentage in each SG; f.
The results of any SG secondary side inspections; g.
The primary to secondary LEAKAGE rate observed in each SG (if it is not practical to assign the LEAKAGE to an individual SG, the entire primary to secondary LEAKAGE should be conservatively assumed to be from one SG) during the cycle preceding the inspection which is the subject of the report; Amendment No. 238, 245, 249, 252, 255, 256, 279, 289, 290, 6-21a
- via eConcurrence NRR-106 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL3/LA NRR/DORL/LPL1/BC (A)
NAME TEdwards SLent UShoop DATE 2/9/2026/
2/10/2026 2/11/2026 OFFICE NRR/DORL/LPL1/PM NAME TEdwards DATE 2/11/2026