ML26041A192

Unit-2: Upcoming Steam Generator Tube Inservice Inspection-Spring 2026

ML26041A192
Person / Time
Site:	Beaver Valley (NPF-073)
Issue date:	02/09/2026
From:	V Sreenivas NRC/NRR/DORL/LPL1
To:	Nevins K Vistra Corp
Sreenivas V, NRR/DORL/LPL1
References
Download: ML26041A192 (0)

Text

From:

Dr V Sreenivas To:

Nevins, Kathleen Cc:

Undine Shoop; Leslie Terry; Greg Makar; Paul Klein; Glenn Dentel; Neil Day

Subject:

BEAVER VALLEY UNIT-2: UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION-Spring 2026 Date:

Monday, February 9, 2026 9:10:00 AM Good Morning Kathy, Inservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. This is to request a telephone conference call with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Beaver Valley Power Station Unit 2 Spring 2026 refueling outage. This call will be scheduled once you inform the NRC responding to this e-mail after the majority of the tubes have been inspected, but before the SG inspection activities have been completed. The process is like the one that we successfully completed during Fall 2024 refueling outage.

Following is a quick list of discussion points:

STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS

The following discussion points have been prepared to facilitate the conference call arranged with the licensee to discuss the results of the steam generator tube inspections to be conducted during the upcoming Beaver Valley Unit 2, Spring 2026 outage. This conference call is scheduled to occur towards the end of the planned SG tube inspections, but before the unit completes the inspections and repairs. The NRC staff plans to document a publicly available summary of the conference call, as well as any material that is provided in support of the call.

1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.

2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.

3. Discuss any exceptions taken to the industry guidelines.

4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100 percent of dents/dings greater than 5 volts and a 20 percent sample between 2 and 5 volts), and the expansion criteria.

5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide the following:

a. A summary of the number of indications identified to date for each degradation mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition).

b. For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., voltage, depth, and length of the indication),

including whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss any analyses performed specifically for the most significant indications to

demonstrate tube integrity, if any indications were close to the condition monitoring limit.

c. Discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).

6. Describe repair/plugging plans.

7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).

8. Discuss the following regarding loose parts:

a. The inspections performed to detect loose parts.

b. A description of any loose parts detected and their location within the SG (including the source or nature of the loose part, if known).

c. If the loose parts were removed from the SG.

d. Indications of tube damage associated with the loose parts.

9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feed ring inspections, sludge lancing, assessing deposit loading, etc).

10. Discuss any unexpected or unusual results.

11. Provide the schedule for steam generator-related activities during the remainder of the current outage.

The U.S. Nuclear Regulatory Commission (NRC) staff will document a publicly available summary of the conference call, including any material that you provide to the NRC staff in support of the call. Just to reiterate, this call will be after the majority of the tubes have been inspected, but before the SG inspection activities have been completed. Please let us know the status to schedule a convenient date and time for this Teams conference call. Should you have any questions you can contact me at 301-415-2597 or by e-mail.

V. Sreenivas, Ph.D., CPM.,

Licensing Project Manager Beaver Valley, Ginna, Seabrook Stations Division of Operating Reactors Licensing, LPL1 U.S. Nuclear Regulatory Commission V.Sreenivas@nrc.gov

cc: Listserv