Document: NRC Regulatory Guide
Document ID: cde52d5a-adf9-49be-9d1f-59449dfca895
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:
analysis are as follows: • The analysis is plant-specific. • The analysis uses SSC-specific information. • The analysis uses accepted engineering methods. RG 1.247, Page 43 • Walkdowns or the evaluation of available data and findings of investigations of the plant design and operations information for plants that have not started construction or do not have enough construction complete to perform physical walkdowns focus on all POSs of the plant configuration. • The analysis identifies and characterizes the uncertainties related to other hazards’ fragility. The objective of the other hazards plant response analysis is to develop a model that includes all important initiating events and other important failures caused by the effects of the hazard that can contribute to plant risk. The model is adapted from the internal events PRA model for all modeled POSs and sources of radioactive materials to incorporate unique aspects related to the hazard analyzed that are different from the internal events PRA model. The characteristics and attributes needed to achieve the objectives of the other hazards plant response analysis are as follows: • The analysis includes all important initiating events related to the hazard analyzed. • The analysis includes other significant failures that can contribute to plant risk. • The analysis is adapted from the internal events PRA model for all modeled POSs and radiological sources. • The analysis incorporates unique aspects related to the hazard analyzed that are different from the internal events PRA model. • The analysis identifies and characterizes the uncertainties related to other hazards plant response. C.1.3.15 Event Sequence Quantification Probabilistic Risk Assessment Element This section identifies the objectives and the characteristics and attributes of the event sequence quantification analysis PRA element for an NLWR PRA that addresses all radiological sources, all hazards, all POSs, and all levels of