Document: NUREG-0800
Document ID: 38291c4d-6d61-4922-8b44-6af61374cfaa
Document Type: srp
Title: ENGINEERED SAFETY FEATURES MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340646.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.1.1
CFR Part: 
CFR Title: 

Content:
ce of system cleanliness of fluid systems and associated components during the operational phase of the nuclear power plant are also reviewed. 3. Thermal Insulation CMEB reviews the composition of the non-metallic insulation and the control of leachable contaminants from the insulation. The branch also reviews the use of inhibitors to reduce the probability of stress corrosion cracking of automatic stainless steel components. 4. Coatings CMEB reviews the use, and qualifications of the protective coatings used in containment as part of SRP Section 6.1.2. Peeling, flaking or delamination of coatings can result in clogging of ESF system strainers and spray nozzles and thereby stop or slow down the flow rates of the ESF fluids. 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: General Design Criterion 1, and §50.55a, "Quality Standards and Records," and "Codes and Standards" - as they relate to quality standards being used for design, fabrication, erection and testing of ESF components and the identifica- tion of applicable codes and standards. General Design Criterion 4 "Environmental and Missile Design Bases" - as it relates to compatibility of; ESF components with environmental conditions asso- ciated with normal operation, maintenance, testing and postulated accidents, including loss-of-coolant accidents. General Design Criterion 14, "Reactor Coolant Pressure Boundary - as it relates to design, fabrication, erection, and testing of thFe reactor coolant pressure 6.1.1-3 Rev. 2 - July 1981 boundary so as to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture. General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary - as it relates to