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:
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, "Fault Tree Handbook," NUREG-0492, January 1981. USNRC, "PRA Procedures Guide," NUREG/CR-2300 Chapter 3.5, January 1983. Dependent Failure Analysis USNRC, "PRA Procedures Guide," NUREG/CR-2300 Chapter 3.7, January 1983. Determination of Success Criteria Brookhaven National Laboratory, "MAAP 3.0B Code Evaluation Final Report," FIN L-1499, October 1992. Electric Power Research Institute, "MAAP Thermal-Hydraulic Quantification Studies," EPRI TR-100741, June 1992. Electric Power Research Institute, "MAAP BWR Application Guidelines," EPRI TR-100742, June 1992. Electric Power Research Institute, "MAAP PWR Application Guidelines for Westinghouse and Combustion Engineering Plants," EPRI TR-100741, June 1992. Fauske & Associates, Inc., "MAAP 3.0B Users Manual," March 1990. USNRC, "RELAP5/MOD3 Code Manual," NUREG/CR-5535 Volumes 1-5, June 1990. USNRC, "TRAC-PF1/MOD2 Code Manual," NUREG/CR-5673 Volumes 1-4, 1994. Westinghouse Electric Corporation, "Reactor Coolant Pump Seal Performance Following Loss of All AC Power," WCAP-10541, Revision 1. Use of Appropriate Data Electric Power Research Institute, "Nuclear Plant Reliability: Data Collection and Usage Guides," EPRI TR-100381, April 1992. Idaho National Engineering Laboratory, "Emergency Diesel Generator Power System Reliability 1987-1993," INEL-95/0035, February 1996. SRP 19-A28 Institute of Electrical and Electronics Engineers, "Guide to the Selection and Presentation of Electrical, Electronic and Sensing Component Reliability Data for Nuclear Power Generating Stations," IEEE-STD-500 Rev. 1, 1984. International Atomic Energy Agency, "Component Reliability Data for Use in Probabilistic Safety Assessment," IAEA-TECDOC-478, October 1988. International Atomic Energy Agency, "Evaluation of Reliability Data Sources," IAEA-TECDOC-504,