Document: NUREG-0800
Document ID: 1877a6e5-f5a2-4394-bd63-c323831e96d0
Document Type: srp
Title: INTRODUCTION - TRANSIENT AND ACCIDENT ANALYSES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML2231/ML22319A149.pdf
Revision Date: 2023-07
Chapter: 15
Section ID: 15.0
CFR Part: 
CFR Title: 

Content:
with respect to fuel performance, the fuel cladding fission product barrier must be maintained for all AOOs; however, for initiating events categorized as postulated accidents, a loss of fuel cladding integrity may be permitted under some circumstances and instead the fuel is required to remain amenable to cooling. The reviewer will consider the results of the applicant’s or licensee’s analyses and evaluations of individual events to ascertain whether the applicant or licensee has satisfied the applicable analysis acceptance criteria for each of the events. The applicant or licensee may propose the use of alternate acceptance criteria appropriate to the particular plant design and operation (e.g., for new reactor design applications). In such cases, the reviewer will consider the alternate criteria and determine whether they are equivalent or more conservative, in function and consequences, to the current criteria. A list of the fundamental criteria necessary to meet the requirements of GDCs for AOOs and postulated accidents is provided in Table 15.0-1 below. Individual sections of the SRP may specify additional criteria pertaining to a certain postulated event. Table 15.0-1: Analysis Acceptance Criteria Figure of Merit AOO Postulated Accident2 Fuel Performance Specified acceptable fuel design limits (SAFDLs)3 Fuel damage shall be limited to the extent consistent with applicable radiological criteria achieve and maintain a safe and stable condition, and maintain the core in a known configuration amenable to cooling Maximum RCS and Main Steam Pressures ASME Service Level B ASME Service Level C Radiological Release 10 CFR Part 20 Graded approach of 10 CFR 50.34(a)(1), or equivalent4 2 For loss-of-coolant accidents (LOCAs), additional acceptance criteria of 10 CFR 50.46(b) shall be satisfied. 3 Typical SAFDLs for demonstrating fuel integrity include limits on the departure from nucleate boiling ratio (DNBR) or critical power ratio (CPR) to prevent overheating, fuel