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:
t 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” Criterion IX, “Control of Special Processes,” and Criterion XIII, “Handling, Storage and Shipping.” 9. Regulatory Guide (RG) 1.7, “Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident.” 10. RG 1.31, “Control of Ferrite Content in Stainless Steel Weld Metal.” 11. RG 1.36, “Nonmetallic Thermal Insulation for Austenitic Stainless Steel.” 12. RG 1.37, “Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants.” 13. RG 1.44, “Control of the Use of Sensitized Steel.” 14. RG 1.50, “Control of Preheat Temperature for Welding Low-Alloy Steel.” 15. RG 1.84, “Design, Fabrication, and Materials Code Case Acceptability ASME Section III.” 16. NUREG-0313, Revision 2, “Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping”; Hazelton, W.S., Koo, W.H.; Division of Engineering and Systems Technology; January, 1988. (Revision 0 of this document replaced Branch Technical Position MTEB 5-7, “Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping,” which was a part of previous revisions of SRP Section 5.2.3). 6.1.1-16 Revision 2 - March 2007 17. NRC Letter to All Licensees of Boiling Water Reactors (BWRs), and Holders of Construction Permits for BWRs, “NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping (Generic Letter (GL) No. 88-01)," January 25, 1988. 18. Branch Technical Position 6-1, “pH for Emergency Coolant Water for PWRs.” 19. ASME Boiler and Pressure Vessel Code, Section II, “Materials,"” Parts A, B, and C; Section III, “Rules for Construction of Nuclear Plant Components,” Division 1, including Appendix I and Division 2; and Section IX, “Welding and Brazing Qualifications,” American Society of Mechanical Engineers.