Document: NUREG-0800
Document ID: 30b7aa8b-c731-4530-a18f-c72723774371
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY INSERVICE INSPECTION AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070421.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.4
CFR Part: 
CFR Title: 

Content:
uation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.62 V. IMPLEMENTATION63 The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plan for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 64 cases in which the applicant or licensee proposes an acceptable alternative method for complying with the specified portions of the Commission's regulations, the methods described herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.65 Implementation schedules are defined in Section 50.55a of 10 CFR Part 50, in reference 6, and 66 in Regulatory Guide 1.150.67 VI. REFERENCES 1. 10 CFR Part 50, §50.55a, "Codes and Standards."68 12. 10 CFR Part 50, Appendix A, General Design Criterion 32, "Inspection of Reactor 69 Coolant Pressure Boundary." 3. Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations."70 4. NUREG-0313, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping," Revision 2, January 1988.71 5.2.4-11 DRAFT Rev. 2 - April 1996 5. NUREG-1344, "Erosion/Corrosion Induced Pipe Wall Thinning in U.S. Nuclear Power Plants," April 1989.72 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)," January 25, 1988.73 7. NRC Letter to All