- Author
- Payne, A. C., Jr. | Sype, T. T. | Whitehead, D. W. | Shiver, A. W.
- Title
- Analysis of the LaSalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (RMIEP). Integrated Quantification and Uncertainty Analysis.
- Coporate
- Sandia National Labs., Albuquerque, NM
- Sponsor
- Nuclear Regulatory Commission, Washington, DC
- Report
- SAND92-0537C, July 1992, 650 p.
- Distribution
- Available from National Technical Information Service
- Contract
- GRANT-A1386
- Keywords
- nuclear power plants | risk assessment | methodology | accident investigations | uncertainty
- Identifiers
- Probabilistic Risk Assessment (PRA); Risk Methods Integration and Evaluation Program (RMIEP); LaSalle Nuclear Power Plant; integrated quantification and uncertainty analysis; level 1
- Abstract
- This volume presents the methodology and results of the integrated accident sequence analysis of the LaSalle Unit 2 Nuclear Power Plant. Integrated results are obtained by merging all of the accident sequences cut sets from the internal and external events analyses. The final dominant accident sequences are determined and the integrated risk reduction, risk increase, and uncertainty importance measures are obtained. Also, an overall ranking of the dominant cut sets was obtained. The total core damage frequency at LaSalle from all events has a mean value of 1.01D-04/R-yr. with a 5th percentile of 5.34E-6/R-yr., a median value of 2.92E-05/R-yr., and a 95th percentile of 2.93E-04/R-yr. The dominant accident, 35.4% of the core damage frequency, involves a los of all injection as a result of failures occurring after a loss of offsite power. The dominant cut sets of this sequence represent a short-term station blackout type accident. The second most likely sequence, 17.2% of the core damage frequency is the result of a control room fire which is not suppressed and becomes large enough to require evacuation of the control room. Auto actuation of the systems fails as a result of the fire and the operators do not operate the remote shutdown panel correctly due to the high stress. Loss of all injection occurs and short-term core damage results.