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:
concerning evaluation of examination results is reviewed for compliance with Articles17 IWC-3000, "Acceptance Standards," and IWD-3000, "Acceptance Standards," of the 18 19 Code. If these requirements are in course of preparation in the applicable Code edition for a program, suitable alternative provisions, such as the requirements in Article20 IWB-3000 or those in later approved editions of the Code, should be proposed by the applicant or licensee. 6.6-3 DRAFT Rev. 2 - April 1996 6. System Pressure Tests The pressure test program is reviewed for compliance with Articles IWC-5000, "System Pressure Tests," and IWD-5000, "System Pressure Tests," of Section XI to establish 21 22 that leakage and signs of structural distress are inspected for on a periodic basis. 7. Augmented ISI to Protect Against Postulated Piping Failures The augmented inservice inspection program as specified in SRP Section 3.6.12 to 23 provide assurance against postulated piping failures of high-energy fluid systems between containment isolation valves is reviewed. 8. Code Exemptions The ASME Section XI Code exemptions as permitted by Subsubarticles IWC- or IWD- 1220, "Components Exempt from Examination," are reviewed. 24 9. Relief Requests Requests for relief from the ASME Code Section XI examination requirements which are found to be impractical due to the limitations of design, geometry, or materials of construction of components are evaluated in accordance with Section 50.55a of 10 CFR Part 50. Review Interfaces25 ECGB also performs the following review under the SRP section indicated: The preservice and inservice inspection requirements for ASME Code Class 1 components in the reactor coolant pressure boundary are reviewed as part of the primary review responsibility for SRP Section 5.2.4, "Reactor Coolant Pressure Boundary Inservice Inspection and Testing."26 In addition, the ECGB will coordinate with other branch evaluations that interface with the overall review of this section as follows: