Document: NUREG-0800
Document ID: 6a2cfd91-f202-4240-9d1c-0e5ba76660e5
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY INSERVICE INSPECTION AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550066.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.4
CFR Part: 
CFR Title: 

Content:
icensee's program should list the exemptions taken in accordance with the ASME Code. 8. Code Cases. ASME code cases referenced by the COL application are reviewed for acceptability and compliance with Regulatory Guide 1.147. Code cases not specifically referenced in Regulatory Guide 1.147 will be reviewed and accepted on a case-by-case basis. 9. Augmented ISI to Protect Against Postulated Piping Failures. The reviewer verifies that the high-energy system piping between containment isolation valves should receive an augmented ISI as follows: A. Protective measures, pipe whip restraints, structures, supports and guard pipes should not prevent access required to conduct the inservice examinations specified in the ASME Code, Section XI, Division 1. B. For those portions of high-energy fluid system piping between containment isolation valves, the inservice examination completed during each inspection interval should provide 100% volumetric examination of circumferential and longitudinal pipe welds. C. For those portions of high-energy fluid system piping enclosed in guard pipes, inspection ports should be provided in the guard pipes to permit the required examination of circumferential pipe welds. Inspection ports should not be located in the portion of the guard pipe passing through the annulus of dual-barrier containment structures. D. The areas subject to examination should be defined in accordance with the Examination Category for Class 1 piping welds specified in Article IWB-2000. 5.2.4-7 Revision 2 - March 2007 10. Other Inspection Programs A. For BWR plants, the reviewer ascertains that the ISI program addresses the staff positions concerning augmented inspections for intergranular stress corrosion cracking (IGSCC) provided in Generic Letter 88-01, Supplement 1 to Generic Letter 88-01, and NUREG-0313, Revision 2. B. For BWR plants, the reviewer ascertains that the ISI program adequately addresses the augmented inspections of feedwater and control rod drive nozzles