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:
r PRA Analysis." EPRI RP-2170-3 (Draft). EPRI: Palo Alto, CA. December 1984. 19.2-67 June 2007 Electric Power Research Institute. "An Approach to the Analysis of Operator Actions in Probabilistic Risk Assessment." EPRI TR-100259. EPRI: Palo Alto, CA. June 1992 (proprietary document - contact EPRI for availability). Electric Power Research Institute. "SHARP1 - A Review of Systematic Human Action Reliability Procedure." EPRI TR-101711. EPRI: Palo Alto, CA. December 1992 (proprietary document - contact EPRI for availability). U.S. Nuclear Regulatory Commission. NUREG/CR-1278. "Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications." NRC: Washington, DC. August 1983. U.S. Nuclear Regulatory Commission. NUREG/CR-2254. "A Procedure for Conducting a Human Reliability Analysis for Nuclear Power Plants." NRC: Washington, DC. 1983. U.S. Nuclear Regulatory Commission. NUREG/CR-2986. "The Use of Performance Shaping Factors and Quantified Expert Judgement in the Evaluation of Human Reliability: An Initial Appraisal." NRC: Washington, DC. 1983. U.S. Nuclear Regulatory Commission. NUREG/CR-3518. "SLIM/MAUD: An Approach to Assessing Human Error Probabilities Using Structured Expert Judgement." Volumes 1 and 2. NRC: Washington, DC. 1984. U.S. Nuclear Regulatory Commission. NUREG/CR-4772. "Accident Sequence Evaluation Program - Human Reliability Analysis Procedure." NRC: Washington, DC. February 1987. Sequence Quantification Institute of Electrical and Electronics Engineers. "IEEE Standard for Software Verification and Validation Plans." IEEE Standard 1012-1986. IEEE: New York, NY. 1986. U.S. Nuclear Regulatory Commission. NUREG/CR-2300, Chapter 6. "PRA Procedures Guide." NRC: Washington, DC. January 1983. U.S. Nuclear Regulatory Commission. NUREG/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