Analysis of the LaSalle Unit 2 nuclear power plant: Risk Methods Integration and Evaluation Program (RMIEP). Volume 8, Seismic analysis

Technical Report · Mon Nov 01 00:00:00 EST 1993

DOI:https://doi.org/10.2172/10106923· OSTI ID:10106923

Wells, J E; Lappa, D A; Bernreuter, D L; Chen, J C; Chuang, T Y ^[1]; Johnson, J J; Campbell, R D; Hashimoto, P S; Maslenikov, O R; Tiong, L W; Ravindra, M K; Kincaid, R H ^[2]; Sues, R H; Putcha, C S ^[3]

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1. Lawrence Livermore National Lab., CA (United States)
2. EQE, International, Irvine, CA (United States)
3. NTS Engineering, Long Beach, CA (United States)

This report describes the methodology used and the results obtained from the application of a simplified seismic risk methodology to the LaSalle County Nuclear Generating Station Unit 2. This study is part of the Level I analysis being performed by the Risk Methods Integration and Evaluation Program (RMIEP). Using the RMIEP developed event and fault trees, the analysis resulted in a seismically induced core damage frequency point estimate of 6.OE-7/yr. This result, combined with the component importance analysis, indicated that system failures were dominated by random events. The dominant components included diesel generator failures (failure to swing, failure to start, failure to run after started), and condensate storage tank.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); EQE International, Inc., Irvine, CA (United States); NTS Engineering, Long Beach, CA (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 10106923
• Report Number(s): NUREG/CR-4832-Vol.8; UCID-21245-Vol.8; ON: TI94003922; TRN: 94:002040
• Resource Relation: Other Information: PBD: Nov 1993
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LA SALLE COUNTY-2 REACTOR
SEISMIC EFFECTS
PROBABILISTIC ESTIMATION
DAMAGE
REACTOR SAFETY
S CODES
FAULT TREE ANALYSIS
FAILURE MODE ANALYSIS
EARTHQUAKES
RISK ASSESSMENT
220900
210100
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED