ATWS analysis for Browns Ferry Nuclear Plant Unit 1

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:6054908

Dallman, R J; Jouse, W C

Analyses of postulated Anticipated Transients Without Scram (ATWS) were performed at the Idaho National Engineering Laboratory (INEL). The Browns Ferry Nuclear Plant Unit 1 (BFNP1) was selected as the subject of this work because of the cooperation of the Tennessee Valley Authority (TVA). The work is part of the Severe Accident Sequence Analysis (SASA) Program of the US Nuclear Regulatory Commission (NRC). A Main Steamline Isolation Valve (MSIV) closure served as the transient initiator for these analyses, which proceeded a complete failure to scram. Results from the analyses indicate that operator mitigative actions are required to prevent overpressurization of the primary containment. Uncertainties remain concerning the effectiveness of key mitigative actions. The effectiveness of level control as a power reduction procedure is limited. Power level resulting from level control only reduce the Pressure Suppression Pool (PSP) heatup rate from 6 to 4F/min.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6054908
• Report Number(s): EGG-M-21485; CONF-8510173-56; ON: TI86005286
• Resource Relation: Conference: 13. water reactor safety research information meeting, Gaithersburg, MD, USA, 22 Oct 1985
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BROWNS FERRY-1 REACTOR
ATWS
COMPUTER CODES
R CODES
STEAM LINES
VALVES
ACCIDENTS
BWR TYPE REACTORS
CONTROL EQUIPMENT
ENRICHED URANIUM REACTORS
EQUIPMENT
FLOW REGULATORS
MIXED SPECTRUM REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled