ML21354A837

Trp 11 St. Lucie SLRA Breakout Questions

ML21354A837
Person / Time
Site:	Saint Lucie
Issue date:	12/20/2021
From:	Office of Nuclear Reactor Regulation
To:
Rodriguez-Luccioni H
References
L-2021-SLR-0002
Download: ML21354A837 (2)

Text

St Lucie Units 1 and 2 SLRA Breakout Audit Questions Technical Reviewer Ali Rezai 12/20/2021 Technical Branch Chief Matthew Mitchell 12 /20/2021 TRP 11 - Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components

1. SLRA SLRA Question / Issue Why are we asking? Outcome of Discussion Section Page 1 B.2.3.5 B-57 The staff found no specific documents indication Confirm whether and when the to that the applicant has reviewed recent industry applicant has reviewed this B-61 operating experience (OE) documented in information and implemented any Electric Power Research Institute (EPRI) applicable guidance from it in this Technical Report 3002012244, Revision 3, AMP. If applicable guidance not Nondestructive Evaluation: Guideline for been implemented, confirm when Conducting Ultrasonic Examinations of Dissimilar the applicant is planning to Metal Welds, published in February 2018, in implement the guidance.

response to industry issues regarding the performance of DM weld examinations. This report provides enhanced guidance and Nuclear Energy Institute (NEI) 03-08, Guideline for the Management of Materials Issues, requirements and recommendations for the examinations of DM welds.

2 B.2.3.5 B-57 The staff found no specific documents indicating Confirm whether and when the to that the applicant has reviewed NRC Regulator applicant has reviewed this B-61 Issuance Summary (RIS) 2015-10, Applicability information for applicability to their of ASME Code Case N-770-1 as Conditioned in 10 Alloy 600 management plan to CFR 50.55a, Codes and Standards, to Branch ensure all applicable butt welds are Connection Butt Welds, issued in July 16, 2015. being inspected as required by the NRC regulations.