Title :
Lessons learned from the NRC review of the SPDS
Author :
Eckenrode, Richard J. ; Lapinsky, George W., Jr. ; Ramirez, Raymond G.
Author_Institution :
US Nucl. Regulatory Comm., Washington, DC, USA
Abstract :
The Safety Parameter Display System (SPDS) became a requirement for all nuclear power plants in November 1980 with the publication of NUREG-0737. In December 1982, Supplement 1 to NUREG-0737 was published to provide clarification of the specification requirements for Emergency Response Capability. In 1985 the NRC staff began a series of post-implementation audits at operating reactors. No serious safety concerns have been uncovered but many problems have been identified indicating that the basic requirements of Supplement 1 to NUREG-0737 are not being met. To date, nearly forty audits have been conducted and the results indicate that approximately 70% of the SPDSs declared operational by utilities do not meet one or more of the basic requirements of Supplement 1 to NUREG-0737. It is noted that as a group, however, the audits produced significant information on good features and alternative methods of satisfying the requirements.<>
Keywords :
fission reactor safety; interactive terminals; nuclear engineering computing; Emergency Response Capability; NUREG-0737; Safety Parameter Display System; nuclear power plants; post-implementation audits; reactors; Auditory displays; Computer displays; Control systems; Cooling; Inductors; Industrial training; Power generation; Radio control; Safety; Temperature control;
Conference_Titel :
Human Factors and Power Plants, 1988., Conference Record for 1988 IEEE Fourth Conference on
Conference_Location :
Monterey, CA, USA
DOI :
10.1109/HFPP.1988.27502