Analysis of core damage frequency from internal events: Sequoyah, Unit 1
This document contains the accident sequence analyses for Sequoyah, Unit 1, one of the reference plants being examined as part of the NUREG-1150 effort by the Nuclear Regulatory Commission (NRC). NUREG-1150 will document the risk of a selected group of nuclear power plants. As part of that work, this report contains the overall core damage frequency estimate for Sequoyah, Unit 1, and the accompanying plant damage state frequencies. Sensitivity and uncertainty analyses provided additional insights regarding the dominant contributors to the Sequoyah core damage frequency estimate. The numerical results are influenced by modeling assumptions and data selection for issues such as reactor coolant pump seal LOCA, common cause failure probabilities, and operator response to emergency conditions such as small LOCA and station blackout. The sensitivity studies explored the impact of alternate theories and data on these issues.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Systems Safety
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6570407
- Report Number(s):
- NUREG/CR-4550-Vol.5; SAND-86-2084-Vol.5; ON: TI87009189
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
ATWS
COOLING SYSTEMS
DAMAGE
DATA BASE MANAGEMENT
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
FLUID MECHANICS
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OPERATION
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REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR OPERATION
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SENSITIVITY ANALYSIS
SEQUOYAH-1 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
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