Document: NUREG-0800
Document ID: 91fee075-c567-438d-bf9f-47be3177b457
Document Type: srp
Title: ENGINEERED SAFETY FEATURES MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070453.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.1.1
CFR Part: 
CFR Title: 

Content:
cy 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, as part of its primary review responsibility for SRP Section 6.2.5.26 For those areas of review identified above as part of reviews under other SRP sections, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP sections.27 II. ACCEPTANCE CRITERIA The acceptance criteria for the areas of review described in subsection I of this SRP section are based on meeting the relevant requirements of General Design Criteria (GDC) 1, 4, 14, 31, 35, 41 and Appendix B, 10 CFR Part 50, and 10 CFR Part 50, §50.55a as described below: 6.1.1-5 DRAFT Rev. 2 - April 1996 A. General Design Criterion 1, and 10 CFR Part 50, §50.55a, "Quality Standards and Records," and "Codes and Standards" - as they relate to quality standards being used for 28 design, fabrication, erection and testing of ESF components and the identification of applicable codes and standards. B. General Design Criterion 4 "Environmental and Missile Design Bases" - as it relates to 29 compatibility of ESF components with environmental conditions associated with normal operation, maintenance, testing and postulated accidents, including loss-of-coolant accidents. C. General Design Criterion 14, "Reactor Coolant Pressure Boundary" - as it relates to 30 design, fabrication, erection, and testing of the reactor coolant pressure boundary so as to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture. D. General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary" - as it relates to extremely low probability of rapidly propagating fracture 31 and gross rupture of the