Integrated Level III risk assessment for the LaSalle Unit 2 Nuclear Power Plant
Technical Report
·
OSTI ID:10115255
In this paper we discuss the methodology and results of the integrated Level III Probabilistic Risk Assessment (PRA) of the LaSalle County Station Unit 2 Nuclear Power Plant. Methods were developed for integrating internal and external events into one analysis based on a common model of the plant and a common method for representing the output. Additional methods were developed for representing and propagating uncertainties in the basic inputs to the models to determine their effects on the final (or intermediate) results. The integrated core damage frequency for the LaSalle plant is 1.01E-4/R-yr., with a 5th percentile of 5.34E-6/R-yr., a median value of 2.92E-5/R-yr., and a 95th percentile of 2.93E-4/R-yr. The dominant sequence is short-term station blackout. The risk from the LaSalle plant is low, especially with respect to the NRC safety goals. The mean individual early fatality risk within one mile and the mean individual latent cancer risk are 1.1E-10/R-yr. and 8.5E-9/R-yr., respectively; both of which are several orders of magnitude less than the safety goals. 10 refs., 11 figs., 7 tabs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 10115255
- Report Number(s):
- SAND--91-1668C; CONF-911079--21; ON: DE92006677
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502
220900
ATWS
BLACKOUTS
CONTAINMENT
E CODES
FAULT TREE ANALYSIS
FIRES
FISSION PRODUCT RELEASE
FLOODS
L CODES
LA SALLE COUNTY-1 REACTOR
LA SALLE COUNTY-2 REACTOR
LOSS OF COOLANT
NEOPLASMS
P CODES
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
RADIATION DOSES
RADIATION HAZARDS
RADIOACTIVE EFFLUENTS
REACTOR SAFETY
REGRESSION ANALYSIS
RISK ASSESSMENT
SEISMIC EFFECTS
STATISTICAL DATA
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502
220900
ATWS
BLACKOUTS
CONTAINMENT
E CODES
FAULT TREE ANALYSIS
FIRES
FISSION PRODUCT RELEASE
FLOODS
L CODES
LA SALLE COUNTY-1 REACTOR
LA SALLE COUNTY-2 REACTOR
LOSS OF COOLANT
NEOPLASMS
P CODES
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
RADIATION DOSES
RADIATION HAZARDS
RADIOACTIVE EFFLUENTS
REACTOR SAFETY
REGRESSION ANALYSIS
RISK ASSESSMENT
SEISMIC EFFECTS
STATISTICAL DATA