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:
ion report should contain findings equivalent to the following. • The calculation for the change in LERF resulting from a proposed change has systematically taken into account the dominant causes of containment failure. In particular, the calculation has considered bypass sequences; sequences posing relatively severe challenges to containment or sequences occurring during periods of reduced containment functionality (shutdown); performance of systems involved in containment safety functions, including containment heat removal, sprays, isolation, and restoration of containment functionality (shutdown); and performance of systems involved in accident management strategies. A.11 Bibliography This section provides a list of documents of that the staff could use as reference or background material during the review process. This bibliography is divided into general categories in the areas of desirable PRA attributes, review of the PRA, uncertainty and sensitivity analyses, and use of the PRA in risk ranking. In addition, a bibliography is provided for each of the review categories discussed in Sections A.1 through A.10 of this appendix. General - Desirable PRA Attributes Electric Power Research Institute, "PSA Applications Guide," EPRI TR-105396, August 1995. Electric Power Research Institute, "Development of a Quality Pedigree Process and Application to the Duane Arnold Energy Center Probabilistic Safety Assessment," EPRI TR-106575, August 1996 (proprietary document - contact EPRI for availability). International Atomic Energy Agency, "Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 1)," IAEA Safety Series No.50-P-4, 1992. SRP 19-A25 USNRC, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants," NUREG-1150, January 1991. USNRC, "A Review of NRC Staff Uses of Probabilistic Risk Assessment," NUREG-1489, March 1994. USNRC, "Individual Plant Examination Program: Perspectives on Reactor Safety and Plant