Document: NUREG-0800
Document ID: 4a46b35d-2e81-4517-9716-154b19f57049
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190006.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.3
CFR Part: 
CFR Title: 

Content:
se, the provisions of the Atomic Energy Act, and the NRC's regulations. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical 5.2.3-8 Revision 3 - March 2007 techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. 1. Material Specifications. The requirements of GDC 1, GDC 30, and § 50.55a regarding quality standards are met for material specifications by compliance with the applicable provisions of the ASME Code and by acceptable application of materials Code Cases as described in Regulatory Guide 1.84, “Design, Fabrication, and Materials Code Case Acceptability, ASME Section III.” The specifications for permitted materials are those identified in the ASME Code, Section III, Appendix I, or described in detail in the ASME Code, Section II, “Materials, Parts A, B, and C. Regulatory Guide 1.84 describes acceptable materials Code Cases and guidelines for their application in light-water-cooled nuclear power plants that may be used in conjunction with the above specifications. Staff positions related to BWR piping materials and materials processing are described in Attachment A to Generic Letter 88-01. The technical bases for the positions provided in Generic Letter 88-01 and similar recommendations related to minimizing stress corrosion cracking in susceptible piping of BWRs are detailed in NUREG-0313. 2. Compatibility of Materials with the Reactor Coolant. The requirements of GDC 4 relative to compatibility of components with environmental