Document: NUREG-0800
Document ID: 26d3dd2f-a261-4586-aded-3fb5d42820d9
Document Type: srp
Title: NUREG-0
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340627.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5
CFR Part: 
CFR Title: 

Content:
NUREG-0 (Formerly NUREG-75/007) .%o, U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION SECTION 5.4.2.2 STEAM GENERATOR TUBE INSERVICE INSPECTION REVIEW RESPONSIBILITIES Primary - Materials Engineering Branch (MTEB) Secondary - None I. AREAS OF REVIEW General Design Criterion 32 of Appendix A of 10 CFR Part 50 requires, in part, that components which are part of the reactor coolant pressure boundary (RCPB) or other components important to safety be designed to permit periodic inspection and testing of critical areas for structural and leaktight integrity. The inservice inspection program for steam generator tubes, which constitute part of the reactor coolant pressure boundary, is based on the detailed positions of Regulatory Guide 1.83, 'Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes," and the applicable Standard Technical Specifications for each nuclear steam system supplier (NUREG-0103, 0212, or 0452). The design of the steam generators as described in the preliminary safety analysis report (PSAR) is reviewed to establish that use of the specified inspection techniques is feasible. The provisions made for baseline inspection prior to startup, the methods to be used for the inspections, and the inservice inspection program are reviewed in the final safety analysis report (FSAR) and plant Technical Specifications. The requirement of General Design Criterion 32 concerning the reactor vessel mate- rial surveillance program is reviewed by MTEB in Standard Review Plan Section 5.3.3, "Reactor Vessel Integrity." The inservice inspection of other areas of the reactor coolant pressure boundary and steam generator are also reviewed by MTEB in Standard Review Plan Sections 5.2.4 and 6.6. II. ACCEPTANCE CRITERIA The guidelines for periodic inspection and testing of the steam generator tube por- tion of the reactor coolant pressure boundary are specified in Regulatory Guide 1.83 and the applicable Standard