Document: NUREG-0800
Document ID: 38c9e70d-6fc5-48a9-8504-06ce4c699bb8
Document Type: srp
Title: INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070450.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.6
CFR Part: 
CFR Title: 

Content:
tion has been provided in accordance with the requirements of this SRP section and that histhe evaluation supports conclusions of the 73 following type, to be included in the staff's safety evaluation report: 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 histhe inservice inspection (ISI) program will 74 comply (complies) with the rules published in 10 CFR Part 50, Section 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 Part 50, Section 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 Plant Components," as reviewed, by the staff and determined to be appropriate for this 75 application. For design certification reviews, the findings will also summarize, to the extent that the review