HRA methodology applied in Surry Power Station

American Nuclear Society International Topical Meeting on Probabilistic Safety Analysis, PSA 05

Volumn 2005, Issue , 2005, Pages 615-618

  Shen, Song Hua ^a  

^a Dominion   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

HRA METHODOLOGY; PRA MODELS;

MATHEMATICAL MODELS; REGIONAL PLANNING; RISK ASSESSMENT;

RISK MANAGEMENT;

EID: 33745813130     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (5)

1. THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS, "ASME RA-Sa-2003 Addenda to ASME RA-S-2002 Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications", The United States of America, New York, 2003.
2. A. D. SWAIN, "Accident Sequence Evaluation Progran Human Reliability Analysis Procedure", NUREG/CR-4772, Washington D.C., U.S. Nuclear Regulatory Commission, February 1987.
3. D. J. WAKEFIELD, G. W. PARRY, G. W. HANNAMAN, and A. J. SPURGIN, "SHARP1 - A Revised Systematic Human Action Reliability Procedure", EPRI TR-101711, Palo Alto CA, Electric Power Research Institute, December 1992.
4. A. J. SPURGIN, "Operator Reliability Experiments Using Power Plant Simulators", EPRI NP-6937, Palo Alto CA, Electric Power Research Institute, July 1990.
5. A. D. SWAIN, and H. E. GUTTMANN, "Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications", NUREG/CR-1278, Washington D.C., U.S. Nuclear Regulatory Commission, August 1983, pp. 10-27.