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:
Guide 1.44, "Control of the Use of Sensitized Stainless Steel." Fabrication and heat treatment practices performed in accordance with these requirements provide added assurance that the probability of stress corrosion cracking will be reduced during the postulated accident time interval. Conformance with the Codes and Regulatory Guides and with the staff posi- tions mentioned above, constitute an acceptable basis for meeting the requirements of General Design Criteria 1, 4, 14, 35, and 41; Appendix B to 10 CFR Part 50, and 10 CFR Part 50, §50.55a, in which the systems are to be designed, fabricated, and erected so that the systems can perform their function as required. 2. General Design Criteria 1, 14, and 31 and Appendix B to 10 CFR Part 50 have been met with respect to assuring that the reactor coolant boundary and associated auxiliary systems have an extremely low probability of leakage, of rapidly propagating failures and of gross rupture. The controls placed on concentrations of leachable impurities in non-metallic thermal insulation used on components of the Engineered Safety Features are in accordance with the requirements of Regulatory Guide 1.36, "Nonmetallic Thermal Insulation for Austenitic Stainless Steels." Compliance with the requirements of Regulatory Guide 1.36 form a basis for meeting the require- g ments of GDC 1, 14 and 31. The protective coating systems have been qualified by tests acceptable to the staff. This qualification provides reasonable assurance that the coating systems will not degrade the operation of the ESF by delaminating, flaking or peeling. The coatings applied are in accordance with Regulatory Guide 1.54, "Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants." Conformance with this Regulatory Guide provides a basis for meeting the requirements of Appendix B to 10 CFR Part 50, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." 3. The requirements of