Document: NUREG-0800
Document ID: 2f83f917-2d38-4def-9f6a-6368d0c22116
Document Type: srp
Title: SPECTRUM OF ROD EJECTION ACCIDENTS (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070721.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.8
CFR Part: 
CFR Title: 

Content:
. 5) are used. 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.42 IV. EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided and histhat the review 43 supports conclusions of the following type, to be included in the staff's safety evaluation report (SER):44 The staff concludes that the analysis of the rod ejection accidents 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 (1) result in damage to the reactor 45 coolant pressure boundary greater than limited local yielding, or (2) cause sufficient damage that would significantly impair the capability to cool the core. The requirements have been met by demonstrating that the regulatory positions of DRAFT Rev. 3 - April 1996 15.4.8-6 Regulatory Guide 1.77, "Assumptions Used for Evaluating a Control Rod Ejection Accident for PWR'sPressurized Water Reactors," are complied with. 46 The staff has evaluated the applicant's analysis of the assumed control rod ejection accident and finds the assumptions, calculation techniques, and consequences acceptable. Since the calculations resulted in peak fuel enthalpies less than 280 cal/gm, prompt fuel rupture with consequent rapid heat transfer to the coolant from finely dispersed molten U0 was assumed not to