Document: NUREG-0800
Document ID: 5e3dbec9-a39f-4531-9eb9-705982190066
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1613/ML16134A059.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
re less than the specified limits for the core support structures. 5. For the review of a DC application, the NRC staff reviewer should follow the above procedures to verify that the design, including requirements and restrictions (e.g., interface requirements and site parameters), specified in the final safety analysis report (FSAR) submitted with the DC application, meet the SRP acceptance criteria. Some DC applicants have referred to their FSAR as the design control document (DCD). The reviewer should also determine whether the identified COL action items are adequate and sufficient. Where the reviewer identifies additional COL action items, these COL action items should be included in the DC FSAR or DCD. For review of a COL application, the scope of the review is dependent on whether the COL applicant references a DC, an early site permit (ESP) or other NRC approvals (e.g., manufacturing license, site suitability report or topical report). The NRC staff reviewer should determine whether the COL applicant has adequately responded to each COL action item, and supplemented the DC application or other referenced NRC approvals to address any plant-specific design aspects. For review of both DC and COL applications, SRP Section 14.3 should be followed for the review of ITAAC. For review of a construction permit (CP) application under 10 CFR Part 50, the reviewer should verify that the design described in the preliminary SAR will meet the acceptance criteria. For the review of an operating license (OL) application under 10 CFR Part 50, the reviewer should follow the above procedures to verify that the design described in the FSAR meets the acceptance criteria. For review of submittals for replacement components or extended power uprate (EPU) for operating reactors, the reviewer should follow the above procedures to verify that the design meets the acceptance criteria. 6. Tier 2* Information Based on the NRC review of the DC application for the ESBWR nuclear power plant