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:
P.W., "Characterization and Evaluation of Uncertainty in Probabilistic Risk Analysis," Nuclear Safety, 22(1), pages 28 - 42, 1981. Proceedings of Workshop I in Advanced Topics in Risk and Reliability Analysis, Model Uncertainty: Its Characterization and Quantification, held in Annapolis, Maryland, October 20-22, 1993, University of Maryland Press, 1996. Special Issue on Treatment of Aleatory and Epistemic Uncertainty, Reliability Engineering and System Safety, Vol. 54, nos 2 and 3, November/December 1996. USNRC, "A Review of NRC Staff Uses of Probabilistic Risk Assessment," NUREG-1489 Appendix C.6, March 1994. USNRC, "Sensitivity Analysis Techniques: Self Teaching Curriculum," NUREG/CR-2350, June 1982. USNRC, "Approaches to Uncertainty Analysis in Probabilistic Risk Assessment," NUREG/CR-4836, January 1988. General - Use of PRA for Risk Ranking USNRC, "Measures of Risk Importance and Their Applications," NUREG/CR-3385, July 1983. Vesely, W.E., "The Use of Risk Importances for Risk-Based Applications and Risk-Based Regulation," in proceedings of PSA ’96, Park City Utah, September 1996. Initiating Events Electric Power Research Institute, "ATWS--A Reappraisal, Part 3, Frequency of Anticipated Transients," EPRI NP-2330, 1982. Nuclear Safety Analysis Center, "Loss of Offsite Power at U.S. Nuclear Power Plants Through 1991," NSAC-182, March 1992. USNRC, "Evaluation of Station Blackout Accidents at Nuclear Power Plants," NUREG-1032, June 1988. USNRC, "Development of Transient Initiating Event Frequencies for Use in Probabilistic Risk Assessments," NUREG/CR-3862, May 1985. USNRC, "Modeling Time to Recovery and Initiating Event Frequency for Loss of Offsite Power Incidents at Nuclear Power Plants," NUREG/CR-5032, January 1988. SRP 19-A27 USNRC, "ISLOCA Research Program Final Report," NUREG/CR-5928, July 1993. Accident Sequence Analysis (Event Trees) USNRC, "PRA Procedures Guide," NUREG/CR-2300 Chapter 3.4, January 1983. System Modeling Analysis (Fault Trees) USNRC,