ML17066A488

Steam Generator ISG RAI for the Review of the Seabrook Station License Renewal Application

ML17066A488
Person / Time
Site:	05000432
Issue date:	03/16/2017
From:	Tam Tran License Renewal Projects Branch 1
To:	Mccartney E NextEra Energy Seabrook
Tran T, NRR/DLR 415-8517
References
CAC ME4028
Download: ML17066A488 (4)

Text

Tran, Tam From: Tran, Tam Sent: Thursday, March 16, 2017 8:48 AM To: 'Edward.Carley@nexteraenergy.com' Cc: James, Lois; Chazell, Russell; Morey, Dennis; Allik, Brian; Edmonds, Yvonne; Poole, Justin; McIntyre, David; Weil, Jenny; Dacus, Eugene; Harris, Brian; Ghosh, Anita; Wachutka, Jeremy; Gray, Mel; Bower, Fred; Cataldo, Paul; Meier, Peter; Vadella, Robert; Tifft, Doug; Sheehan, Neil; Screnci, Diane; Browne, Kenneth

Subject:

Steam Generator ISG RAI Attachments: SG ISG RAI.pdf UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Eric McCartney Site Vice President NextEra Energy Seabrook, LLC P.O. Box 300, Lafayette Road Seabrook, NH 03874

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SEABROOK STATION LICENSE RENEWAL APPLICATION (CAC NO. ME4028)

Dear Mr. McCartney:

By letter dated May 25, 2010, NextEra Energy Seabrook, LLC, submitted an application pursuant to 10 CFR Part 54, to renew the operating license NPF-86 for Seabrook Station, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.

This request for additional information was discussed with Mr. Edward Carley, and a mutually agreeable date for the response is no later than May 19, 2017. If you have any questions, please contact me at (301) 415-3617 or e-mail Tam.Tran@nrc.gov.

Sincerely, Tam Tran, Project Manager Project Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation 50-443

Enclosure:

1

ML17066a488

(*) concurred by e-mail OFFICE PM:RPB1:DLR BC:RARB:DLR BC:RPB1:DLR PM:RPB1:DLR NAME T Tran* D. Morey* R. Chazell* T Tran DATE 03/07/2017 03/ 16 /2017 03/ 14 /2017 03/16 /2017

SEABROOK STATION LICENSE RENEWAL APPLICATION (LRA)

REQUEST FOR ADDITIONAL INFORMATION (RAI)

RAI B.2.1.10-3

Background:

The staff issued License Renewal Interim Staff Guidance (LR-ISG) 2016-01, Changes to Aging Management Guidance for Various Steam Generator Components (ADAMS Accession No.

ML16237A383). LR-ISG-2016-01 provides the following guidance for aging management:

Visual inspections: steam generator head internal areas (head interior surfaces, divider plate assemblies, tubesheets (primary side) and tube-to-tubesheet welds) in order to identify signs of cracking or loss of material (e.g., rust stains and distortion of divider plates). GALL Report AMP XI.M19, Steam Generators, which includes these visual inspections, is used to manage loss of material due to boric acid corrosion for channel heads and tubesheets and cracking due to primary water stress corrosion cracking (PWSCC) for divider plate assembles and tube-to-tubesheet welds.

Frequency of the visual inspections: at least every 72 effective full power months or every third refueling outage whichever results in more frequent inspections.

Implementation of the EPRI steam generator guidelines, including: (a) EPRI Report 1022832 (primary-to-secondary leak guidelines); (b) EPRI Report 1025132 (in-situ pressure test guidelines); (c) EPRI Report 3002007571 (integrity assessment guidelines); and (d) EPRI Report 3002007572 (examination guidelines).

Issue:

The staff needs to confirm whether the applicants Steam Generator Tube Integrity Program is consistent with the guidance discussed above.

Request:

1. Clarify whether the Steam Generator Tube Integrity Program is consistent with the guidance discussed above (i.e., conduct of visual inspections to manage loss of material and cracking due to PWSCC; visual inspection frequency; and implementation or plans for implementation of the EPRI steam generator guidelines by the implementation dates provided by the industry). If not consistent, provide justification of why the applicants Steam Generator Tube Integrity Program is adequate for aging management. As part of the response, clarify whether the aging management associated with LRA item 3.1.1-81 for divider plates uses the Steam Generator Tube Integrity Program.

2. Given the divider plate assembles are made with Alloy 600 type material susceptible to primary water stress corrosion cracking, provide information to confirm that the industry

analyses in EPRI Report 3002002850 assessing the significance of divider plate cracking are applicable and bounding for the conditions at the applicants unit. If not bounding, identify a plant-specific program that will be used to manage cracking for the divide plate assemblies.

3. Provide updated UFSAR supplement for this program as necessary.

Enclosure