Analysis of the LaSalle Unit 2 Nuclear Power Plant: Risk Methods Integration and Evaluation Program (RMIEP). Volume 3, Part 2, Internal events accident sequence quantification: Appendices
- Sandia National Labs., Albuquerque, NM (United States)
This volume presents the methodology and results of the internal event accident sequence analysis of the LaSalle Unit II nuclear power plant performed as part of the Level III Probabilistic Risk Assessment being performed by Sandia National Laboratories for the Nuclear Regulatory commission. The total internal core damage frequency has a mean valve of 4.41E-05/R-yr. with a 5th percentile of 2.05E-6/R-yr., a median value of 1.64E-05/R-yr. , and a 95th percentile of 1.39E-04/R-yr. The dominant sequences involve a loss of off-site power (LOSP), immediate or delayed failure of on-site AC power resulting in station-blackout, and failure of the reactor core isolation cooling system (RCIC). The events most important to risk reduction are: frequency of LOSP, non-recovery of offsite power within one hour, diesel generator (DG) cooling water pump common mode failure, and non-recoverable isolation of RCIC during station blackouts. The events most important to risk increase are: failure of various AC power circuit breakers resulting in partial loss of onsite AC power, failure to scram, and DG cooling water common mode failure. The dominant contributors to uncertainty are: control circuit failure rates, relay coil failure to energize, energized relay coils failing deenergized, frequency of LOSP, and DG failure to start.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 10174542
- Report Number(s):
- NUREG/CR-4832-Vol.3-Pt.2; SAND-92-0537-Vol.3-Pt.2; ON: TI92019896
- Country of Publication:
- United States
- Language:
- English
Similar Records
Integrated Level III risk assessment for the LaSalle Unit 2 Nuclear Power Plant
Analysis of the LaSalle Unit 2 nuclear power plant: Risk Methods Integration and Evaluation Program (RMIEP). Volume 8, Seismic analysis
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LA SALLE COUNTY-2 REACTOR
RISK ASSESSMENT
LOSS OF COOLANT
REACTOR SAFETY
COMPILED DATA
TRANSIENTS
ECCS
FAILURES
REACTOR COMPONENTS
FAILURE MODE ANALYSIS
BLACKOUTS
PUMPS
220900
210100
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED