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:
sts to those in ASTM A-262 that have been previously accepted include ASTM A 708. For BWRs, the control of sensitized steel per RG 1.44 should be modified as necessary to conform with the positions in Attachment A to GL 88-01 or the recommendations of NUREG-0313. The controls for abrasive work on austenitic stainless steel surfaces should, as a minimum, be equivalent to the controls described in RG 1.37 position C.5 to prevent contamination which promotes stress corrosion cracking. Tools which contain materials that could contribute to intergranular or stress-corrosion cracking or which, because of previous usage, may have become contaminated with such materials, should not be used on austenitic stainless steel surfaces. F. Additional controls, beyond those described above, are considered necessary to avoid intergranular stress corrosion cracking (IGSCC) in and near welds in BWR austenitic stainless steel reactor vessel attachments and appurtenances. The additional controls are described in Attachment A to GL 88-01 and in NUREG-0313, Revision 2. These controls include material and weldment specifications for IGSCC resistant materials, processing techniques, categorization of the IGSCC resistance of installations based upon material properties, treatment history, and post-weld treatments. The technical bases for these controls are described in NUREG-0313, Revision 2. The referenced regulatory guides are described in detail in the acceptance criteria of SRP Section 5.2.3. 5. Fracture Toughness. The acceptance criteria for this area of review are the requirements of Appendix G of 10 CFR Part 50. These criteria satisfy the requirements of GDC 31 and 10 CFR 50.60 regarding materials testing and acceptance standards for fracture toughness. Appendix G requires that the reactor vessel and appurtenances thereto which are made of ferritic materials shall meet the following minimum requirements for fracture toughness during system hydrostatic tests, conditions of normal