Reducing scrams by modifying reactor setpoints for a Westinghouse four-loop plant
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5770351
The operating statistics of nuclear power plants show that a large number of reactor scrams have occurred and resulted in unscheduled plant outages. The safety and economic significance of unnecessary scrams in nuclear plants warrants concentrated effort. Several approaches are being taken to reduce the scram frequency. They are better operator training, improved equipment reliability, and better operating procedures. The effort on scram reduction at the Nuclear Safety Analysis Center (NSAC) complements these approaches. Specifically, NSAC is performing thermal-hydraulic analyses to relax or eliminate a number of scram setpoints without violating safety limits. It is believed that through this means a significant fraction of the scram occurrences will be eliminated.
- Research Organization:
- Electric Power Research Institute, Palo Alto, CA
- OSTI ID:
- 5770351
- Report Number(s):
- CONF-851115-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 50
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reducing scram frequency by modifying reactor setpoints for a Westinghouse four-loop plant
Setpoint relaxation for scram reduction on C-E PWRs
Protection system modifications in Westinghouse pressurized water reactors to reduce the frequency of unnecessary feedwater-related trips
Journal Article
·
Wed Dec 31 23:00:00 EST 1986
· Nucl. Technol.; (United States)
·
OSTI ID:7089386
Setpoint relaxation for scram reduction on C-E PWRs
Conference
·
Thu Oct 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5770345
Protection system modifications in Westinghouse pressurized water reactors to reduce the frequency of unnecessary feedwater-related trips
Conference
·
Sat Dec 31 23:00:00 EST 1988
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6922926
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
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
COMPUTER CODES
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MECHANICS
OXYGEN COMPOUNDS
PWR TYPE REACTORS
R CODES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RELIABILITY
SAFETY
SCRAM
SHUTDOWNS
SPECIFICATIONS
STEAM GENERATORS
TRAINING
TRANSIENTS
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTINGHOUSE STANDARD REACTOR
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BOILERS
COMPUTER CODES
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FEEDWATER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MECHANICS
OXYGEN COMPOUNDS
PWR TYPE REACTORS
R CODES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RELIABILITY
SAFETY
SCRAM
SHUTDOWNS
SPECIFICATIONS
STEAM GENERATORS
TRAINING
TRANSIENTS
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTINGHOUSE STANDARD REACTOR