Evaluation of Susquehanna steam electric station emergency procedures related to ATWS
A number of variations in operator response strategy to a severe anticipated transient without scram (ATWS) event may be considered. Calculations have been performed for the Susquehanna Steam Electric Station, a two-unit 1050-MW(e) boiling water reactor, to compare the relative effectiveness of various level and flow control strategies for ATWS mitigation. The objectives of this evaluation were to determine the critical timing parameters of the various response strategies, their demands for operator action, and their relative effectiveness. The evaluations performed have considered ATWS from full power with no rod insertion for both isolation and nonisolation events. These evaluations have not considered the impact of additional equipment failure such as loss of the high-pressure coolant injection system or the standby liquid control system.
- Research Organization:
- Pennsylvania Power and Light Co., Allentown
- OSTI ID:
- 6570143
- Report Number(s):
- CONF-860610-; TRN: 87-021591
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ATWS
EMERGENCY PLANS
SUSQUEHANNA-1 REACTOR
REACTOR SAFETY
SUSQUEHANNA-2 REACTOR
FAILURES
FUEL ELEMENT FAILURE
MITIGATION
REACTOR CORES
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SHUTDOWN
SAFETY INJECTION
TRANSIENTS
ACCIDENTS
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
OPERATION
PERSONNEL
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SHUTDOWNS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled