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:
access for inservice inspection in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, ( ) Edition, including Addenda through the ( ) Addenda. Suitable equipment will be (has been) developed and installed to facilitate the remote inspection of these areas of the reactor coolant pressure boundary that are not readily accessible to inspection personnel. The ISI program will consist of a preservice inspection plan and an inservice inspection plan. The conduct of periodic inspections and leakage and hydrostatic testing of pressure retaining components of the reactor coolant pressure boundary in accordance with the requirements in applicable Subsections of Section XI 60 of the ASME Code provides reasonable assurance that evidence of structural degradation DRAFT Rev. 2 - April 1996 5.2.4-10 or loss of leaktight-integrity occurring during service will be detected in time to permit corrective action before the safety function of a component is compromised. Compliance with the inservice inspections required by this Code constitutes an acceptable basis for satisfying in part the requirements of General Design Criterion 32. The staff concludes that the inservice program is acceptable and meets the inspection and testing requirements of General Design Criterion 32 and 10 CFR Part 50, Section 50.55a. This conclusion is based on the applicant's or licensees 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 61 appropriate for this application. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report (SER) sections, the staff's evaluation 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