Document: NUREG-0800
Document ID: 7916b088-fb90-4163-84fe-027bd315bcc5
Document Type: srp
Title: REVIEW OF RISK INFORMATION USED TO SUPPORT PERMANENT PLANT-
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0717/ML071700658.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.2
CFR Part: 
CFR Title: 

Content:
/BR-0167. "Software Quality Assurance Program and Guidelines." NRC: Washington, DC. February 1993. Modeling of Containment Response and Changes in Large Early Release Frequency U.S. Nuclear Regulatory Commission. NUREG-1570 (Draft for Comment). "Risk Assessment of Severe Accident-Induced Steam Generator Tube Rupture." NRC: Washington, DC. May 1997. U.S. Nuclear Regulatory Commission. NUREG/CR-4551. "Evaluation of Severe Accident Risks: Surry Unit 1." Volume 3, Revision 1, Part 1. NRC: Washington, DC. October 1990. U.S. Nuclear Regulatory Commission. NUREG/CR-4551. "Evaluation of Severe Accident Risks: Peach Bottom Unit 2." Volume 4, Revision 1, Part 1. NRC: Washington, DC. December 1990. 19.2-68 June 2007 U.S. Nuclear Regulatory Commission. NUREG/CR-4551. "Evaluation of Severe Accident Risks: Sequoyah Unit 1." Volume 5, Revision 1, Parts 1 and 2. NRC: Washington, DC. December 1990. U.S. Nuclear Regulatory Commission. NUREG/CR-4551. "Evaluation of Severe Accident Risks: Grand Gulf Unit 1." Volume 6, Revision 1, Parts 1 and 2. NRC: Washington, DC. December 1990. U.S. Nuclear Regulatory Commission. NUREG/CR-5305. "Integrated Risk Assessment for the LaSalle Unit 2 Nuclear Power Plant: Phenomenology and Risk Uncertainty Evaluation Program (PRUEP)." NRC: Washington, DC. December 1990. U.S. Nuclear Regulatory Commission. NUREG/CR-4551. "Evaluation of Severe Accident Risks: Zion Unit 1." Volume 7, Revision 1. NRC: Washington, DC. March 1993. U.S. Nuclear Regulatory Commission. NUREG/CR-6595. "An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events." NRC: Washington, DC. Revision 1, October 2004. 19.2-69 June 2007 APPENDIX B Integrated Decisionmaking Risk-informed applications are expected to require a process to integrate traditional engineering and probabilistic considerations to form the basis for acceptance. In order for this decisionmaking process to be effective in rendering accurate representations of plant safety and risk,