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:
eous fission products, under long-term storage and prolonged spray operating conditions, is performed under SRP Section 6.5.2, “Containment Spray as a Fission Cleanup System.” 4. The review of the acceptability of the reactor coolant chemistry and associated chemistry controls (including additives such as inhibitors) as it relates to corrosion control and compatibility with ESF materials is performed under SRP Sections 5.4.8 “Reactor Water Cleanup System (BWR),” and 9.3.4, “Chemical and Volume Control System (PWR).” 6.1.1-4 Revision 2 - March 2007 5. The review of the adequacy of the design for structural integrity of components and their supports is performed under SRP Section 3.9.3, “ASME Code Class 1, 2, and 3 Components, Component Supports, and Core Support Structures.” 6. The determination of the adequacy of post-loss-of-coolant accident (LOCA) hydrogen control, including control of the volume of hydrogen gas expected to be generated by metal-water reaction involving the fuel cladding and radiolytic decomposition of the reactor coolant, and corrosion of metals by emergency core cooling and containment spray solutions is performed under SRP Section 6.2.5, “Combustible Gas Control in Containment.” The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. GDC 1, and 10 CFR 50.55a as they relate to quality standards for design, fabrication, erection, and testing of ESF components and the identification of applicable codes and standards. 2. GDC 4 as it relates to compatibility of ESF components with environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including LOCAs . 3. GDC 14 as it relates to design, fabrication, erection, and testing of the RCPB so as to have an extremely low probability of abnormal