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:
ns of the following type, to be included in the staff's safety evalua- tion report: To ensure that no deleterious defects develop during service, steam generator tubes will be inspected prior to plant startup and periodi- cally throughout the life of the plant. The applicant (licensee) has stated that his inservice inspection program will comply (complies) with the recommendations in Regulatory Guide 1.83, "Inservice Inspec- tion of Pressurized Water Reactor Steam Generator Tubes," and the applicable Standard Technical Specifications, NUREG ( >, concerning the inspection methods to be used, access for inservice inspection, provisions for a baseline inspection, selection and sam- pling of tubes, inspection intervals, actions to be taken in the event defects are identified, and reporting requirements. The staff concludes that the inservice inspection program of steam generator tubes is acceptable and meets the inspection and testing Rev. 1 - July 1981 5.4.2.2-2 requirements of General Design Criterion 32. This conclusion is based on the applicant's (licensee's) following the recommendations in Regulatory Guide 1.83, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes," and the Standard Technical Specifications, NUREG ( ), as reviewed by the staff and determined to be appropriate for this application. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides, NUREGs, and in 10 CFR Part 50, §50.36. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Reactor