Document: NUREG-0800
Document ID: 75cfe33d-deac-4762-b598-93d97976a959
Document Type: srp
Title: 15.3.2.-9
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550010.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
Revision 2 - March 2007 • reactor power; • heat fluxes (average and maximum); • reactor coolant system pressure; • core and recirculation loop coolant flow rates (BWR), if applicable); • coolant conditions (inlet temperature, core average temperature PWR core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions); • steam line pressure (BWR): • pressure relief valve flow rate; and • flow rate from the reactor coolant system to the containment system (if applicable). Values of the more important of these parameters for the core flow increase AOOs are compared to those predicted for other similar plants for whether they are within the expected range. The reactor systems organization reviews the SAFDLs. The organization responsible for emergency preparedness and radiation protection is notified of the extent of fuel failures predicted by the analysis if SAFDLs are exceeded. The quality assurance and maintenance review confirms whether the SAR or DCD commits to conduct pre-operational tests to verify flow coast-down calculations. 6. For review of a DC application, 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). IV. EVALUATION FINDINGS The reviewer