Document: NUREG-0800
Document ID: f60cdc8f-3c25-45c3-a1d3-b0f530961625
Document Type: srp
Title: DETERMINING THE TECHNICAL ADEQUACY OF PROBABILISTIC RISK
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1219/ML12193A107.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.1
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Content:
ASSESSMENT FOR RISK-INFORMED LICENSE AMENDMENT REQUESTS AFTER INITIAL FUEL LOAD REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of probabilistic risk assessment. Secondary - None I. AREAS OF REVIEW Introduction This Standard Review Plan (SRP) section addresses the technical adequacy of a baseline probabilistic risk assessment (PRA) used by a licensee to support license amendments for an operating reactor, as well as license amendment requests submitted after initial fuel load for new reactors. Technical adequacy, scope, and level of detail are components of overall PRA quality. Regulatory Guide (RG) 1.174 provides guidance regarding all three attributes of PRA quality. Note that the technical adequacy of the PRA used by an applicant to support the design certification (DC) or combined license (COL) application, and by a licensee to support license amendments submitted prior to the initial fuel load is addressed in SRP Section 19.0. In using this SRP section, the reviewer should focus on determining if the baseline PRA reflects the status of the design and the appropriate operational features. 19.1- 2 Rev. 3 – September 2012 This SRP section defines what constitutes a technically acceptable baseline PRA, which is addressed by RG 1.200. RG 1.200 describes the necessary scope, the technical elements of a PRA, and the technical attributes and characteristics for a full-scope PRA. RG 1.200 allows the use of PRA standards and peer reviews to demonstrate conformance. As such, RG 1.200 also provides the needed attributes and characteristics of a peer review and endorses both American Society of Mechanical Engineers (ASME) and American Nuclear Society (ANS) standards, as well as industry peer review guidance. Applicability This SRP section is applicable to any licensee amendment request submitted for U.S. Nuclear Regulatory Commission (NRC) review and approval for which information from a PRA is used to support the requested action. This SRP