Implementation of an advanced digital feedwater control system at the Prairie Island nuclear generating station

Technical Report · Tue May 01 00:00:00 EDT 1990

OSTI ID:6913577

Paris, R E; Gaydos, K A ^[1]; Hill, J O; Whitson, S G; Wirkkala, R ^[2]

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1. Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear and Advanced Technology Div.
2. Northern States Power Co., Welch, MN (USA). Prairie Island Nuclear Station

EPRI Project RP2126-4 was a cooperative effort between TVA, EPRI, and Westinghouse which resulted in the demonstration of a prototype of a full range, fully automatic feedwater control system, using fault tolerant digital technology, at the TVA Sequoyah simulator site. That prototype system also included advanced signal validation algorithms and an advanced man-machine interface that used CRT-based soft-control technology. The Westinghouse Advanced Digital Feedwater Control System (ADFCS) upgrade, which contains elements that were part of that prototype system, has since been installed at Northern States Power's Prairie Island Unit 2. This upgrade was very successful due to the use of an advanced control system design and the execution of a well coordinated joint effort between the utility and the supplier. The project experience is documented in this report to help utilities evaluate the technical implications of such a project. The design basis of the Prairie Island ADFCS signal validation for input signal failure fault tolerance is outlined first. Features of the industry-proven system control algorithms are then described. Pre-shipment hardware-in-loop and factory acceptance testing of the Prairie Island system are summarized. Post-shipment site testing, including preoperational and plant startup testing, is also summarized. Plant data from the initial system startup is included. The installation of the Prairie Island ADFCS is described, including both the feedwater control instrumentation and the control board interface. Modification of the plant simulator and operator and I C personnel training are also discussed. 6 refs., 14 figs., 3 tabs.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA); Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear and Advanced Technology Div.; Northern States Power Co., Welch, MN (USA). Prairie Island Nuclear Station
• Sponsoring Organization: EPRI
• OSTI ID: 6913577
• Report Number(s): EPRI-NP-6758; TRN: 90-016027
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRAIRIE ISLAND-2 REACTOR
REACTOR CONTROL SYSTEMS
DIGITAL SYSTEMS
FEEDWATER
INSTALLATION
MAN-MACHINE SYSTEMS
PERFORMANCE TESTING
STEAM GENERATORS
TRAINING
BOILERS
CONTROL SYSTEMS
ENRICHED URANIUM REACTORS
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
TESTING
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220400* - Nuclear Reactor Technology- Control Systems
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled