Validation and integration of critical PWR signals for safety parameter display systems

Technical Report · Thu May 01 04:00:00 EDT 1986

OSTI ID:5505090

Benedict, B J; Godbole, S S; Lutz, R I

This document describes the progress to date and the functional requirements generated for EPRI Project RP-2292-1, ''Validation and Integration of Critical PWR Signals.'' The purpose of the project is to develop a methodology and a system of computer software for on-line validation of signals for use in nuclear power plants. The project scope is limited to validation of signals which input to a Safety Parameter Display System, however, the methodology generated is to have generic applicability. A Utility Advisory Group periodically reviews status and helps provide project direction. The methodology developed is being applied to produce signal validation software for a host plant, Northeast Utilities' Millstone-2 plant. The generic capability of the software will be checked by analysis of Commonwealth Edison's Zion plant. System design first identifies the functions which require validated inputs. Then variables which define the functions are identified. Finally, the sensors which provide a value for each variable are identified. Signal validation techniques are applied to the list of variables depending on the number of sensors for a variable. In each case software modules are to be developed for each variable. Preliminary algorithms for the Millstone-2 modules using physically redundant sensors have been generated, but still require detailed design work to make them generic. Conceptual design of modules that use complex functional relationships is still in progress. Requirements for the signal validation system are provided. Requirements for the system design, computer system software and hardware, input/output format, and testing are addressed.

• Research Organization: Babcock and Wilcox Co., Lynchburg, VA (USA). Nuclear Power Div.
• OSTI ID: 5505090
• Report Number(s): EPRI-NP-4566; ON: TI86920360
• Country of Publication: United States
• Language: English

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
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
DESIGN
DISPLAY DEVICES
EMERGENCY PLANS
ENGINEERED SAFETY SYSTEMS
PWR TYPE REACTORS
REACTORS
SIGNALS
TESTING
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS