Document: NUREG-0800
Document ID: bfb38837-d37b-4298-91b0-44efa3061212
Document Type: srp
Title: INSERVICE INSPECTION AND TESTING OF CLASS 2 AND 3 COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550071.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.6
CFR Part: 
CFR Title: 

Content:
on 14.3 should be followed for the review of ITAAC. The review of ITAAC cannot be completed until after the completion of this section. IV. EVALUATION FINDINGS The reviewer verifies that the applicant has provided sufficient information and that the review and calculations (if applicable) support conclusions of the following type to be included in the staff's safety evaluation report. The reviewer also states the bases for those conclusions. 1. To ensure that no deleterious defects develop during service in ASME Code Class 2 system components, selected welds and weld heat-affected zones are inspected prior to reactor startup and periodically throughout the life of the plant. In addition, Code Class 2 and 3 systems receive visual inspections while the systems are pressurized in order to detect leakage, signs of mechanical or structural distress, and corrosion. The applicant (licensee) has stated that the inservice inspection (ISI) program will comply (complies) with the rules published in 10 CFR 50.55a, and Section XI of the ASME Code, ( ) Edition, including addenda through the ( ) Addenda. The ISI program will consist of a preservice inspection plan and an inservice inspection plan. Examples of Code Class 2 systems are: residual heat removal systems, portions of chemical and volume control systems (in PWR plants), portions of control rod drive systems (in BWR Plants), and engineered safety features not part of Code Class 1 systems. Examples of Code Class 3 systems are: component cooling water systems and portions of radwaste systems. All of these systems transport fluids. The staff concludes that the inservice inspection program is acceptable and meets the inspection and pressure testing requirements of General Design Criteria 36, 37, 39, 40, 42, 43, 45, and 46 and 10 CFR 50.55a. This conclusion is based on the applicant's or licensee's meeting the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power