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:
eria II. Acceptance Criteria (Item 3.c); to provide guidance for application of ASME Section III. Review Procedures (Item 3). XI, Appendices VII and VIII for qualification of personnel and performance demonstration of ultrasonic examination systems. 493 Revise Review Procedures to include Regulatory II. Acceptance Criteria (Items 3.d Guide 1.150 as reference for ultrasonic testing of and 5.c); III. Review Procedures reactor vessel welds. (Items 3 and 5.c), V. Implementation, and VI. References (Item 3). 494 Develop Review Procedures for review of BWR III. Review Procedures (Item 9) augmented inservice inspections developed to and VI. References (Items 4, 6, address intergranular stress corrosion cracking and 7). (IGSCC). 616 Develop Review Procedures for review of surveillance III. Review Procedures (Item 9) programs to ensure that boric acid corrosion does not and VI. References (Item 8). lead to degradation of the reactor coolant pressure boundary. 622 Develop Review Procedures for inspection programs III. Review Procedures (Item 9) to monitor bottom mounted instrumentation thimble and VI. References (Item 10). tube performance in Westinghouse designed reactors. 1492 Consider incorporating in Review Procedures a III. Review Procedures (Item 9) discussion on augmented inspections of CRD and and VI. References (Item 13) feedwater nozzles in accordance with NUREG-0619.