Document: NUREG-0800
Document ID: d8b522d4-dee5-4122-89d4-b2b45d0ca729
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070420.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.3
CFR Part: 
CFR Title: 

Content:
eel." 102. Regulatory Guide 1.37, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water Cooled Nuclear Power Plants." 123. Regulatory Guide 1.43, "Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components."131 134. Regulatory Guide 1.44, "Control of the Use of Sensitized Stainless Steel." 145. Regulatory Guide 1.50, "Control of Preheat Temperature for Welding of Low-Alloy Steel." 156. Regulatory Guide 1.71, "Welder Qualification for Areas of Limited Accessibility." 167. Regulatory Guide 1.85, "Code Case Acceptability ASME Section III Materials.""Materials Code Case Acceptability ASME Section III Division 1."132 178. 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 tThis document replacesd 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 this SRP Section)133 5.2.3-25 DRAFT Rev. 3 - April 1996 19. 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 No. 88-01)," January 25, 1988.134 20. NUREG/CR-4513 (ANL-90/42), "Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems," Chopra, O. K., prepared by Argonne National Laboratory for the U.S. Nuclear Regulatory Commission, June 1991.135 421. ASME Boiler and Pressure Vessel Code, Section II, "Materials," Parts A, B, and C,; Section III, "Rules for Construction of Nuclear Plant Components"; and Section IX, "Welding and Brazing Qualifications"; American Society of Mechanical Engineers.136 22. ASTM, A-262-1970 , "Detecting Susceptibility to Intergranular Attack in Stainless 137 Steels"; Practice A