Document: NRC Regulatory Guide
Document ID: 8a2332d3-66ca-40af-84e1-507db8b26559
Document Type: regulatory_guide
Title: TRIAL - Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2123/ML21235A008.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.247
CFR Part: 
CFR Title: 

Content:
thods or technologies), some direct review by the NRC staff may be warranted. Submitted applications that use NDMs with open F&Os are subject to review by the NRC to determine the acceptability of the method, its implementation in the PRA, and its potential impact on the application. The peer review of an NDM should meet certain requirements specific to that type of peer review. An acceptable set of requirements against which the acceptability of an NDM are listed below: RG 1.247, Page 60 • The purpose and scope of the NDM are clearly stated. • The NDM is based on sound engineering and science relevant to its purpose and scope. • The data (note that data can be numeric or nonnumeric) are relevant to the NDM, technically sound, and properly analyzed and applied. • Uncertainties in the NDM are characterized. Sources of model uncertainties and related assumptions are identified. • The results of the NDM are reproducible, reasonable, and consistent with the assumptions and data, given the purpose and scope of the method. • The documentation of the NDM provides traceability of the work and facilitates incorporation of the method in a PRA model. C.3 Demonstrating the Acceptability of a Probabilistic Risk Assessment Used to Support an Application This section of the RG provides guidance to applicants and licensees on an approach acceptable to the NRC staff to demonstrate the acceptability of a PRA and its results used to support an application. For all applications, the PRA-related information provided in the submittal should do the following: • Describe the PRA’s scope–such as, but not limited to, consideration of all radiological sources, hazards, plant operating states and levels of analysis− level of detail, and degree of plant representation. • Demonstrate that the PRA has been developed and used in a technically acceptable manner, including the appropriateness of the assumptions and approximations used in developing the PRA. • Identify the