Document: NUREG-0800
Document ID: 6997f9d9-dedc-49d7-ac15-7615c1bd9713
Document Type: srp
Title: SPECTRUM OF ROD DROP ACCIDENTS (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550015.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.9
CFR Part: 
CFR Title: 

Content:
viewer 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 verifies that the applicant has provided sufficient information and that the review and calculations (if applicable) 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 staff concludes that the rod drop accident analysis is acceptable and meets GDC 13 and GDC 28 requirements. This conclusion is based on the following findings: The applicant meets GDC 13 requirements by demonstrating that all credited instrumentation was available, and that actuations of protection systems, automatic and manual, occurred at values of monitored parameters that were within the instruments’ prescribed operating ranges. The applicant meets GDC 28 requirements as to prevention of postulated reactivity accidents that could result in damage to the reactor coolant pressure boundary greater than limited local yielding or damage that impairs core cooling capability significantly. The staff has evaluated the applicant's analysis of the assumed control rod drop accident and finds the assumptions, calculation techniques, and consequences acceptable. As the calculations predict peak fuel temperatures below melting conditions, prompt fuel rupture with consequent rapid heat transfer to the coolant from finely dispersed molten U02 presumably did not occur. The pressure surge results in a pressure increase below "Service Limit C" (as defined in Section III of the ASME 15.4.9-6 Revision 3 - March 2007 Boiler and Pressure Vessel Code) for the maximum control