Document: NUREG-0800
Document ID: 73a7c7ff-f0ac-467b-ba1d-0fb71e328868
Document Type: srp
Title: examines this margin to ensure that specified acceptable fuel design limits are not
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070705.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.2
CFR Part: 
CFR Title: 

Content:
all reactor internal pumps (RIPs) with offsite power available. Normally, such transients are treated as anticipated operational occurrences, which must not result in specified acceptable fuel design limits being exceeded. For this special case, the transient is not expected to occur during the lifetime of the plant and is not classified as an anticipated operational occurrence, but rather as an anticipated transient involving a common-mode software failure. Accordingly the following criterion for the radiological dose calculation was established: fuel failure need not be assumed in dose calculations for fuel rods that are at or below a temperature of approximately 600 C (1111 F) for o o less than 60 seconds for fuel that has achieved a burnup of 20 gigawatt-days per metric ton or less. (For fuel beyond this burnup, the dose calculations must assume fuel failure for all fuel rods that achieve transition boiling because the test data do not go beyond 20 gigawatt-days per metric ton.) The resulting dose should not exceed 10 percent of 10 CFR Part 100, which is considered appropriate for an event of such frequency because of the unique design features of ABWR instrumentation and control systems.62 CPB is consulted regardingThe SRXB reviews the specified acceptable fuel design limits 63 (SAFDLs). AEBThe PERB is notified regarding the extent of fuel failures predicted by the 64 analysis if SAFDLs are exceeded. The SER should present one statement for all similar transients. b 15.3.1-9 DRAFT Rev. 2 - April 1996 The PTRBHQMB review confirms that a commitment has been made in the SAR to conduct 65 preoperational tests to verify flow coastdown calculations. 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