Document: NUREG-0800
Document ID: 97b395a8-6e49-47d5-a249-28113b429fe3
Document Type: srp
Title: MASS AND ENERGY RELEASE ANALYSIS FOR POSTULATED SECONDARY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070620010.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1.4
CFR Part: 
CFR Title: 

Content:
plication, the reviewer should follow the above procedures to verify that the design, including requirements and restrictions (e.g., interface requirements and site parameters), set forth in the final safety analysis report (FSAR) meets the acceptance criteria. DCs have referred to the FSAR as the design control document (DCD). The reviewer should also consider the appropriateness of identified COL action items. The reviewer may identify additional COL action items; however, to ensure these COL action items are addressed during a COL application, they should be added to the DC FSAR. 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). For review of both DC and COL applications, SRP Section 14.3 should be followed for the review of ITAAC. The review of ITAAC cannot be completed until after the completion of this section. IV. EVALUATION FINDINGS The reviewer verifies that the applicant has provided sufficient information and that the review and calculations, if applicable (section III.2) support conclusions of the following type to be included in the staff's safety evaluation report. The reviewer also states the bases for those conclusions. The evaluation findings will follow the format provided in SRP Section 6.2.1 and conclude that the applicant followed the SRP acceptance criteria identified above [or identified deviations from the SRP acceptance criteria with appropriate justification] and meets GDC 50 as it relates to providing sufficient conservatism in the mass and energy release analysis for postulated pressurized-water reactor (PWR) secondary system pipe ruptures for the containment design basis. 6.2.1.4-7 Revision 2 - March 2007 For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and