Document: NUREG-0800
Document ID: baab1f26-b869-4986-9c53-36842ceaa7c3
Document Type: srp
Title: SPECTRUM OF ROD DROP ACCIDENTS (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070723.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.9
CFR Part: 
CFR Title: 

Content:
computed by an acceptable method. c. The reviewer determines that the amount of fuel exceeding melting conditions has been computed by an acceptable method. 4. For ABWR reviews, the reviewer compares the applicant's safety analysis report (SAR) with assumptions used by the staff to compute rod drop accident doses and with the resultant radiological consequences. Thus, the reviewer either confirms that the applicant's design would produce similar results or notes significant differences.20 For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site interface requirements and combined license action items, meet the acceptance criteria given in subsection II. SRP Section 14.3 (proposed) contains procedures for the review of certified design material (CDM) for the standard design, including the site parameters, interface criteria, and ITAAC.21 IV. EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided, and histhe review supports 22 conclusions of the following type, to be included in the staff's safety evaluation report: The staff concludes that the analysis of the rod drop accident is acceptable and meets the requirements of General Design Criterion 28. This conclusion is based on the following: The applicant met the requirements of GDC 28 with respect to preventing postulated reactivity accidents that could result in damage to the reactor coolant pressure boundary greater than limited local yielding or cause sufficient damage that would significantly impair the capability to cool the core. The requirements have been met since the staff has evaluated the applicant's analysis of the assumed control rod drop accident and finds the assumptions, calculational techniques, and