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:
eric Letter 88-01, and NUREG-0313, Revision 2. B. For BWR plants, the reviewer ascertains that the ISI program adequately addresses the augmented inspections of feedwater and control rod drive nozzles as discussed in NUREG-0619. The staff may approve alternatives to the inspection guidelines in NUREG-0619. C. For PWR plants, the reviewer verifies that the applicant or licensee has established a program to detect and correct potential RCPB corrosion caused by boric acid leaks, as described in Generic Letter 88-05. D. For Westinghouse PWR plants, the reviewer verifies that the applicant or licensee has established an inspection program to periodically confirm the integrity of incore neutron-monitoring system thimble tubes, as described in NRC Bulletin 88-09. 11. Operational Programs. For COL reviews, the description of the operational program and proposed implementation milestone(s) for the Preservice Inspection, Inservice Inspection and Inservice Testing Programs are reviewed in accordance with 10 CFR 50.55a(g) and 10 CFR Part 50, Appendix A. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. General Design Criterion 32 requires, in part, that all components that are part of the RCPB be designed to permit periodic inspection and testing of important areas and features to assess structural and leak-tight integrity. SRP Section 5.2.4 is the primary SRP section assessing compliance with General Design Criterion 32. Meeting the requirements of General Design Criterion 32 assures that an effective periodic inspection program can be performed on the RCPB, so that aging effects or other incipient degradation phenomena may be identified and preventive measures promptly taken to preclude potential loss of reactor coolant or impairment of reactor core cooling. 2. According to10 CFR 50.55a, "Codes and Standards," structures, systems, and