Document: NUREG-0800
Document ID: f5ae448a-20e3-4127-90a9-888a9b291921
Document Type: srp
Title: REACTOR VESSEL INTEGRITY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340640.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.3
CFR Part: 
CFR Title: 

Content:
nd the effectiveness of nondestruc- tive evaluation methods are interrelated, the reviewer must rely on state- of-the-art knowledge and past practice to determine whether the proposed combinations are compatible and acceptable. 4. Inspection Requirements The basic requirements for performing nondestructive inspections, the quality assurance criteria for the reactor vessel, and the regulations that all of these criteria satisfy, are detailed in SRP Section 5.3.1. These requirements and criteria are contained in Sections III and V of the Code. Acceptance criteria for compatibility with materials and fabrication areas are discussed in previous sections. Very important relationships are those among in-process and final shop inspections, and the inservice inspection requirements of Section XI of the Code. The reviewer must determine that the methods of inspection, the sensitivity levels, and flaw evaluation criteria are compatible with Section XI, and that the results of the preservice baseline inspection can be correlated with the results of later inservice inspections. 5. Shipment and Installation The basic acceptance criteria for procedures and care to maintain proper cleanliness and freedom from contamination during all stages of shipping, storage, and installation of the reactor vessel, and the regulations that these criteria satisfy, are given in SRP Section 5.2.3. The purpose of this area of review is to verify that the as-built character- istics of the reactor vessel are not degraded by improper handling. Accept- ability in these areas is assured for current designs and materials by compliance with the basic acceptance criteria. If nonstandard materials or designs are used, the reviewer must determine that these criteria will be adequate, based on current technology. If the basic criteria are not followed, either intentionally or through error, the reviewer must evaluate, on a case basis, whether the integrity 5.3.3-4 Rev. 1 - July 1981 of the reactor vessel is