Document: NUREG-0800
Document ID: 76e2cd41-eada-4a81-bc9e-1df5cf439180
Document Type: srp
Title: SPECIAL TOPICS FOR MECHANICAL COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1422/ML14227A637.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.1
CFR Part: 
CFR Title: 

Content:
omponent supports, reactor core support structures, and reactor vessel internal components form a complete basis for the design of the reactor coolant pressure 3.9.1-7 Draft Revision 4 – August 2015 boundary for all anticipated conditions and extremely low-probability events expected during the service life of the plant. 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 SRP 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(21), and 10 CFR 52.47(22), and 10 CFR 52.79(a)(17) and 10 CFR 52.79(20), for new reactor license applications submitted under 10 CFR Part 52, “Licenses, Certifications, and Approval for Nuclear Power Plants,” 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 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 CFR 50.34(f), except paragraphs 10 CFR 50.34 (f)(1)(xii), 10 CFR 50.34 (f)(2)(ix), and 10 CFR 50.34 (f)(3)(v). These cross-cutting review areas should be addressed by the reviewer for each technical subsection and relevant conclusions documented in the corresponding safety evaluation report (SER) section. 2. The list