Assessment of the AMSAC safety function at Maanshan Nuclear Power Station

Conference · Fri Jun 01 04:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6022625

Pei, Baushei; Yu, Geping; Lin, Gueiching; Ma, Yinpang ^[1]

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1. National Tsing-Hua Univ. (Taiwan)

Anticipated transient without trip (ATWT) events involve the failure of the reactor trip system whenever it is called on during a nuclear power plant transient. Several transients have been postulated as the initiating events to study the different responses of plants under ATWT events. For a pressurized water reactor, analysis has shown that a complete loss-of-normal-feedwater (LONF) transient can be the most severe initiating event to threaten the integrity of the primary-side pressure boundary. A series of generic analyses on ATWTs shows that acceptable consequences can result provided that the turbine is tripped and the auxiliary feedwater flow is initiated in a timely manner. The final US Nuclear Regulatory Commission ATWT rule requires that all the Westinghouse-designed plants install ATWT mitigation system actuation circuitry (AMSAC) to initiate a turbine trip and to actuate the auxiliary feedwater flow independently of the reactor trip system. The Westinghouse design of the AMSAC system for the Maanshan nuclear power station (MNPS) monitor one out of three of the signals from the feedwater pumps, the feedwater flow control valves, or the feedwater isolation valves for the AMSAC actuation logic.

• OSTI ID: 6022625
• Report Number(s): CONF-900608--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 61
• Country of Publication: United States
• Language: English

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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTROL ELEMENTS
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COOLING SYSTEMS
ENERGY SYSTEMS
FAILURES
FEEDWATER
HYDROGEN COMPOUNDS
LOSS OF COOLANT
MITIGATION
MODERATORS
NATIONAL ORGANIZATIONS
OPERATION
OPTIMIZATION
OXYGEN COMPOUNDS
PRESSURIZERS
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR MONITORING SYSTEMS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTORS
SECONDARY COOLANT CIRCUITS
SENSITIVITY
SIMULATION
STEAM GENERATORS
TIME DELAY
TRANSIENTS
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US ORGANIZATIONS
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS