Document: NUREG-0800
Document ID: 6a2cfd91-f202-4240-9d1c-0e5ba76660e5
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY INSERVICE INSPECTION AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550066.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.4
CFR Part: 
CFR Title: 

Content:
ng design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR 50.55a, “Codes and Standards.” 2. 10 CFR Part 50, Appendix A, General Design Criterion 32, “Inspection of Reactor Coolant Pressure Boundary.” 3. Regulatory Guide 1.150, “Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations.” 4. NUREG-0313, “Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping,” Revision 2, January 1988. 5.2.4-12 Revision 2 - March 2007 5. NRC letter to all licensees of operating boiling water reactors (BWRs) and holders of construction permits for BWRs, “NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping (Generic Letter No. 88-01),” January 25, 1988. 6. NRC letter to all licensees of operating boiling water reactors (BWRs) and holders of construction permits for BWRs, “NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping (Generic Letter No. 88-01, Supplement 1),” February 4, 1992. 7. NRC letter to all licensees of operating PWRs and holders of construction permits for PWRs, “Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants (Generic Letter No. 88-05),” March 17, 1988. 8. NRC bulletin to all holders of operating