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:
rrosion cracking will be reduced during the postulated accident time interval. For BWRs, to assure adequate resistance against intergranular stress corrosion cracking, susceptible austenitic stainless steel piping appropriately conforms with the positions of Attachment A of GL 88-01 and the recommendations of NUREG-0313, Revision 2, “Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping.” Conformance with the Codes and Regulatory Guides and with the staff positions mentioned above constitutes an acceptable basis for meeting the requirements of GDC 1, 4, 14, 35, and 41; Appendix B to 10 CFR Part 50; and 10 CFR 50.55a, in which the systems are to be designed, fabricated, and erected so that the systems can perform their function as required. 2. GDC 1, 14, and 31 and Appendix B to 10 CFR Part 50 have been met with respect to assuring that the reactor coolant pressure 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 engineered safety features components are in accordance with the positions of RG 1.36, “Nonmetallic Thermal Insulation for Austenitic Stainless Steels.” Compliance with the positions of RG 1.36 is the basis for meeting the requirements of GDC 1, 14, and 31. 3. The requirements of GDC 4, 35, and 41 and Appendix B, 10 CFR Part 50 have been met with respect to compatibility of ESF components with environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents, since the controls on pH and chemistry of the reactor containment sprays and the emergency core cooling water following a 6.1.1-14 Revision 2 - March 2007 loss-of-coolant or design-basis accident are adequate to reduce the probability of stress corrosion cracking of the