Severe Accident Sequence Analysis Program: Anticipated transient without scram simulations for Browns Ferry Nuclear Plant Unit 1

Technical Report · Fri May 01 00:00:00 EDT 1987

DOI:https://doi.org/10.2172/6370654· OSTI ID:6370654

Dallman, R J; Gottula, R C; Holcomb, E E; Jouse, W C; Wagoner, S R; Wheatley, P D

An analysis of five anticipated transients without scram (ATWS) was conducted at the Idaho National Engineering Laboratory (INEL). The five detailed deterministic simulations of postulated ATWS sequences were initiated from a main steamline isolation valve (MSIV) closure. The subject of the analysis was the Browns Ferry Nuclear Plant Unit 1, a boiling water reactor (BWR) of the BWR/4 product line with a Mark I containment. The simulations yielded insights to the possible consequences resulting from a MSIV closure ATWS. An evaluation of the effects of plant safety systems and operator actions on accident progression and mitigation is presented.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6370654
• Report Number(s): NUREG/CR-4165; EGG-2379; ON: TI87010676
• Country of Publication: United States
• Language: English

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ACCIDENTS
ATWS
BROWNS FERRY-1 REACTOR
BWR TYPE REACTORS
C CODES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
COOLING SYSTEMS
EMERGENCY PLANS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
HEAT TRANSFER
MATERIALS
MIXED SPECTRUM REACTORS
OPERATION
PERSONNEL
POWER REACTORS
R CODES
RADIOACTIVE EFFLUENTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
S CODES
SAFETY
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS