ML23089A125

NRR E-mail Capture - Beaver Valley Upcoming Steam Generator Tube Inservice Inspection

ML23089A125
Person / Time
Site:	Beaver Valley
Issue date:	03/30/2023
From:	Sujata Goetz NRC/NRR/DORL/LPL1
To:	Lashley P Energy Harbor Nuclear Corp
References
L-2023-LRO-0013
Download: ML23089A125 (5)

Text

From: Sujata Goetz Sent: Thursday, March 30, 2023 9:05 AM To: Lashley, Phil H Cc: Beck, Andrew

Subject:

Beaver Valley Upcoming Steam Generator Tube Inservice Inspection (EPID:

L-2023-LRO-0013)

Attachments: STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS for RFO 23.docx

Dear Mr. Lashley,

Inservice inspections of steam generator (SG) tubes play a vital role in assuring steam generator tube integrity. Therefore, The U.S. Nuclear Regulatory Commission would like to schedule a conference call to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming RFO 23 for Beaver Valley Unit 2. We would like to have this call after majority of the tubes have been inspected, but before the SG inspection activities have been completed.

I have attached list of question we would like to discuss..

The NRC 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.

If you have any questions, please call me.

Sincerely,

Sujata Goetz Project Manager, Calvert Cliffs

Nuclear Regulatory Commission 11555 Rockville Pike Office of the Nuclear Reactor Regulation NRC/NRR/DORL/LPL1 Office O8F2 Mailroom O8-B1A Rockville, MD 20852-2738 Washington, DC 20555-0001

(o) 301.415.8004 (f) 301.415.3313

Hearing Identifier: NRR_DRMA Email Number: 2022

Mail Envelope Properties (MN2PR09MB5467FAECA80E5876C8722DDF808E9)

Subject:

Beaver Valley Upcoming Steam Generator Tube Inservice Inspection (EPID L-2023-LRO-0013)

Sent Date: 3/30/2023 9:04:39 AM Received Date: 3/30/2023 9:04:00 AM From: Sujata Goetz

Created By: Sujata.Goetz@nrc.gov

Recipients:

"Beck, Andrew" <abeck@energyharbor.com>

Tracking Status: None "Lashley, Phil H" <phlashley@energyharbor.com>

Tracking Status: None

Post Office: MN2PR09MB5467.namprd09.prod.outlook.com

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STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS for RFO 23

The NRC would like to discuss the results of the steam generator tube inspections being conducted during the the spring 2023 Unit 2 refueling outage which is scheduled to start April 9, 2023.

NRC would like to schedule this conference call towards the end of the planned SG tube inspections, but before the unit completes the inspections and repairs. Please let the project manger know when you would like to schedule this call.

The NRC staff will document a publicly available summary of the conference call, as well as any material that is provided in support of the call.

Specifically, NRC would like to discuss with you the following:

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

2. Are there any secondary side pressure tests were performed during the outage and the associated results.?

3. Are there 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.

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. What are the repair/plugging plans?

7. What is the in-situ pressure test and tube pull plans and results (as applicable and if available)?

8. Discuss the following regarding loose parts:

a. Was there an inspections performed to detect loose parts?

b. Provide 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. Were loose parts removed from the SG?

d. Are there any indications of tube damage associated with the loose parts.

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

10. Were there any unexpected or unusual results?

11. Can you provide the schedule for steam generator-related activities during the remainder of the current outage?.