Document: NUREG-0800
Document ID: 6cdd237d-c5b3-4a09-8753-54cfe1fea503
Document Type: srp
Title: REACTOR VESSEL MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190007.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.1
CFR Part: 
CFR Title: 

Content:
lts under the special conditions. Revision 2 - March 2007 5.3.1-14 Such special procedures may be modifications or combinations of methods described in Section V, or may be entirely different, but the reviewer verifies that they have been proven by demonstration to result in an examination capable of detecting discontinuities under the special conditions to the same extent that applicable normal techniques which are included in Section V would result in detection of discontinuities under normal conditions. Such special procedures are submitted to the authorized inspector or inspecting agency for review and approval prior to use. 4. Special Controls and Special Processes Used for Ferritic Steels and Austenitic Stainless Steel. The controls on welding of ferritic steels and austenitic stainless steels discussed in SRP Section 5.2.3 are considered applicable to welding of the reactor vessel and its components. The reviewer verifies that any special welding control or special welding process is able to conform to the qualification requirements of the Code, Section IX, or that justification is made for this deviation. The reviewer also reviews the controls (before, during, and after welding of austenitic stainless steel) to avoid contamination and sensitization that could increase the possibility of stress corrosion cracking in austenitic stainless steel. Additionally, controls to avoid underclad cracking during weld cladding of the reactor vessel are reviewed. The abrasive work controls for austenitic stainless steel surfaces are reviewed and are verified as adequate to minimize the introduction of contaminants and surface cold-working which may promote stress corrosion cracking. For BWRs, the reactor vessel attachments and appurtenances are reviewed for conformance with the staff positions of GL 88-01 or the recommendations of NUREG-0313, Revision 2 with regard to protection against IGSSC in or near weldment to the reactor vessel. 5. Fracture Toughness. The information