Digital implementation of AMSACs at Harris and Robinson plants
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6808442
The Code of Federal Regulations was altered in July 1984 to include a section on Requirements for Reduction of Risk from Anticipated Transients Without Scram Events for Light Water Cooled Nuclear Power Plants. For pressurized water reactors the code required equipment diverse from the reactor trip system to automatically initiate the auxiliary (or emergency) feedwater system and initiate a turbine trip under conditions indicative of an anticipated transient without scram (ATWS). The equipment in question is called ATWS mitigation system actuation circuitry (AMSAC). The AMSACs for Carolina Power and Light Company's Shearon Harris and Robinson power plants have been designed and built by Atomic Energy of Canada Limited (AECL) from commercially available components to meet stringent reliability requirements and minimize operational burdens.
- OSTI ID:
- 6808442
- Report Number(s):
- CONF-880422-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 56
- Country of Publication:
- United States
- Language:
- English
Similar Records
Anticipated transient without SCRAM experiments at LOFT
Analysis of results from a loss-of-offsite-power-initiated ATWS experiment in the LOFT facility. [PWR]
Analysis of results from a loss-of-offsite-power-initiated ATWS experiment in the LOFT Facility
Conference
·
Fri Dec 31 23:00:00 EST 1982
· Proc. Am. Power Conf.; (United States)
·
OSTI ID:6693023
Analysis of results from a loss-of-offsite-power-initiated ATWS experiment in the LOFT facility. [PWR]
Technical Report
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5624591
Analysis of results from a loss-of-offsite-power-initiated ATWS experiment in the LOFT Facility
Journal Article
·
Fri Jul 01 00:00:00 EDT 1983
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:6703417
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
CONTROL SYSTEMS
ENRICHED URANIUM REACTORS
FEEDWATER
HARRIS-1 REACTOR
HARRIS-2 REACTOR
HARRIS-3 REACTOR
HARRIS-4 REACTOR
HYDROGEN COMPOUNDS
OPERATION
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR OPERATION
REACTORS
RELIABILITY
ROBINSON-2 REACTOR
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
CONTROL SYSTEMS
ENRICHED URANIUM REACTORS
FEEDWATER
HARRIS-1 REACTOR
HARRIS-2 REACTOR
HARRIS-3 REACTOR
HARRIS-4 REACTOR
HYDROGEN COMPOUNDS
OPERATION
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR OPERATION
REACTORS
RELIABILITY
ROBINSON-2 REACTOR
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS