Document: NUREG-0800
Document ID: 14a7348a-8b3c-404a-bddd-d0b57465bf85
Document Type: srp
Title: COMPLIANCE WITH AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1422/ML14227A623.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.1.1
CFR Part: 
CFR Title: 

Content:
ire that a COL applicant provide, in its safety analysis report, a description of the programs and their implementation necessary to ensure that the systems and components meet the requirements of the ASME BPV Code and ASME OM Code in accordance with 10 CFR 50.55a at a level sufficient to enable the NRC to reach a final conclusion on all safety matters that must be resolved before COL issuance. RG 1.206 provides guidance for the content of COL applications for a description of the ISI and IST programs to meet 10 CFR 50.55a. The requirements in 10 CFR 52.79(a)(11) and the guidance in RG 1.206 provide confidence in an applicant’s compliance with 10 CFR 50.55a. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 1. In accordance with 10 CFR 52.47(a)(8), 10 CFR 52.47(a)(21), and 10 CFR 52.47(a)(22), and 10 CFR 52.79(a)(17) and 10 CFR 52.79(a)(20), for new reactor license applications submitted under 10 CFR Part 52, the applicant is required to (1) address the proposed technical resolution of unresolved safety issues and medium and high-priority generic safety issues which are identified in the version of NUREG-0933, “Resolution of Generic 5.2.1.1-7 Draft Revision 4 - August 2015 Safety Issues,” current on the date up to 6 months before the docket date of the application and which are technically relevant to the design; (2) demonstrate how the operating experience insights have been incorporated into the plant design; and, (3) provide information necessary to demonstrate compliance with any technically relevant portions of the Three Mile Island requirements set forth in 10