Validation of critical signals for the safety parameter display system: Final report
Technical Report
·
OSTI ID:6541428
Signal validation in the context of this project is the process of combining information from multiple plant sensors to produce highly reliable information about plant conditions. In this project, the signal validation methodology that has been developed in previous EPRI-sponsored projects has been enhanced and applied toward validation of critical safety related signals in the Northeast Utilities Millstone 3 Westinghouse PWR plant and the Millstone 2 Combustion Engineering PWR plant. The designs were implemented in FORTRAN software and tested off-line using recorded plant sensor data, RETRAN generated simulation data, and data to exercise software logic branches and test the integration of software modules. Designs and software modules have been developed for 15 variables required by 6 critical safety functions that have been selected as a shared SPDS requirement by a utility advisory group attached to the project.
- Research Organization:
- Babcock and Wilcox Co., Lynchburg, VA (USA); Electric Power Research Inst., Palo Alto, CA (USA)
- OSTI ID:
- 6541428
- Report Number(s):
- EPRI-NP-5066M; ON: TI87920396
- Country of Publication:
- United States
- Language:
- English
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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
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
COMMUNICATIONS
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
DATA
DATA ACQUISITION
DATA TRANSMISSION
DISPLAY DEVICES
EMERGENCY PLANS
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
FORTRAN
INFORMATION
INTERACTIVE DISPLAY DEVICES
MILLSTONE-2 REACTOR
MILLSTONE-3 REACTOR
MONITORING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
POWER PLANTS
POWER REACTORS
PROGRAMMING
PROGRAMMING LANGUAGES
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
SAFETY
SIGNALS
TESTING
THERMAL POWER PLANTS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
COMMUNICATIONS
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
DATA
DATA ACQUISITION
DATA TRANSMISSION
DISPLAY DEVICES
EMERGENCY PLANS
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
FORTRAN
INFORMATION
INTERACTIVE DISPLAY DEVICES
MILLSTONE-2 REACTOR
MILLSTONE-3 REACTOR
MONITORING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
POWER PLANTS
POWER REACTORS
PROGRAMMING
PROGRAMMING LANGUAGES
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
SAFETY
SIGNALS
TESTING
THERMAL POWER PLANTS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS