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:
R plants, the reviewer verifies that the applicant or licensee has established a program to detect and correct potential RCPB corrosion caused by boric acid leaks, as described in Generic Letter 88-05 (Reference 8).55 For Westinghouse PWR plants, the reviewer verifies that the applicant or licensee has established an inspection program to periodically confirm incore neutron monitoring system thimble tube integrity, as described in NRC Bulletin 88-09 (Reference 10).56 For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site interface requirements and combined license action items, meet the acceptance criteria given in subsection II. SRP Section 14.3 (proposed) contains procedures for the review of certified design material (CDM) for the standard design, including the site parameters, interface criteria, and ITAAC.57 IV. EVALUATION FINDINGS The reviewer verifies that adequate information is provided in accordance with the requirements of this SRP section, and that histhe evaluation supports conclusions of the following type, to be 58 included in the staff's safety evaluation report: To ensure that no deleterious defects develop during service, selected welds and weld heat-affected zones will be inspected prior to plant startup and periodically throughout the life of the plant. The applicant (licensee) has stated that histhe inservice inspection 59 (ISI) program will comply (complies) with the rules published in 10 CFR Part 50, Section 50.55a. The design of the reactor coolant system incorporates provisions for 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)