Document: NUREG-0800
Document ID: e6a79bdb-930d-4b57-91b9-39db4d8a76f1
Document Type: srp
Title: ENGINEERED SAFETY FEATURES MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190010.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.1.1
CFR Part: 
CFR Title: 

Content:
component cooling water (CCW), station service water (SSW), and ESF ventilation. The fluid and material compatibility of these systems are reviewed in this SRP section upon request of the responsible staff. The specific areas of review are as follows: 1. Materials and Fabrication. The review includes the materials and fabrication procedures used in the construction of engineered safety features. The specific areas of review and review procedures are similar to those in SRP Section 5.2.3, “Reactor Coolant Pressure Boundary Materials,” and SRP Section 10.3.6, “Steam and Feedwater System Materials.” The purpose of the review is to assure compatibility of the materials with the specific fluids to which the materials are subjected. The review is performed to assure compliance with the applicable Commission regulations of 10 CFR Part 50, including the applicable general design criteria; the positions of applicable regulatory guides and branch technical positions, and the applicable provisions of the ASME Boiler and Pressure Vessel Code (hereinafter “the Code”), including Section II, Parts A, B, and C, Section III, Divisions 1 and 2, and Section IX. Areas that are reviewed include mechanical properties of materials (including fracture toughness), use of cold worked stainless steels, control of ferrite content in austenitic stainless steel welds, and control of ferritic steel welding. 2. Composition and Compatibility of ESF Fluids. The composition of the containment and core spray coolants must be controlled to ensure their compatibility with materials in the containment building, including the reactor vessel, reactor internals, piping, and structural and insulating materials. The methods and procedures to control the chemical composition of solutions recirculated within the containment after design-basis accidents (DBA) must be selected (a) to maintain the integrity of the RCPB, by preventing stress corrosion cracking of safety-related components, (b) to