Document: NUREG-0800
Document ID: ac43f632-9db1-4857-9f56-bfba45965456
Document Type: srp
Title: * These are modifications to a plant’s design, operations, or other activities that require NRC approval. These modifica
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0232/ML023250195.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19
CFR Part: 
CFR Title: 

Content:
ERAL GUIDANCE INTRODUCTION This chapter of the Standard Review Plan (SRP) identifies the roles and responsibilities of organizations in the U.S. Nuclear Regulatory Commission (NRC) that participate in risk-informed reviews of licensees’ proposals for changes to the licensing basis (LB)* of nuclear power plants. The SRP identifies the types of information that may be used in fulfilling an organization’s responsibilities and provides general guidance on how the information from a probabilistic risk assessment (PRA) can be combined with other pertinent information in the process of making a regulatory decision. The guidance in this document is a logical extension of current NRC policy on the use of PRA in regulatory activities. This policy is documented in the Commission’s PRA policy statement and implementation plan (Refs. 1-3). In developing this SRP chapter, the staff considered the NRC’s guidance on the use of PRA in risk-informed regulatory applications as documented in Regulatory Guide 1.174 (Ref. 4) as well as the relevant industry guidance documented by the Electric Power Research Institute (EPRI) in its "Probabilistic Safety Assessment (PSA) Applications Guide" (Ref. 5). In addition, this chapter references other SRP chapters that provide additional guidance for reviewing specific applications of PRA in regulated activities. The appendices to this Chapter 19 provide more specific guidance. Included are Appendix A, “Guidance for a Focused-Scope Application-Specific PRA Review”; Appendix B, “Integrated Decisionmaking”; Appendix C, “Categorization of Plant Elements with Respect to Safety Significance”; and Appendix D, “Use of Risk Information in Review of Non-Risk-Informed License Amendment Requests.” In the process of risk-informed decisionmaking, the NRC will rely on the approach discussed in this Chapter 19. Above all, the design, construction, and operational practices of each plant are expected to be consistent SRP 19-2 with its LB.