A history and overview of the safety parameter display system concept
Journal Article
·
· IEEE Trans. Nucl. Sci.; (United States)
Inquiries into the accident at the Three Mile Island Nuclear Power Plant Unit 2, on March 28, 1979 brought to public attention the need to improve operators' capabilities to interact with the systems under their control. Recommendations ran the full gamut of human/machine interaction, from improvements in training and procedures to improvements in control and display hardware in the control room. This presentation briefly traces the history and development of a display concept that evolved in the post-TMI era, the Safety Parameter Display System or SPDS. The SPDS is intended to function as a detection aid for control room operators, providing an integrated overview of significant plant parameters. The purpose of this report is to describe the general concept of SPDS, its history, and its current regulatory status. A review of NRC guidance documents is included, as well as a discussion of NRC requirements placed on the SPDS. The presentation concludes with an outline of the NRC staff review process for safety parameter display systems and a synopsis of the results of generic SPDS reviews performed thus far.
- Research Organization:
- U.S. Nuclear Regulatory Commission, Washington, DC 20555
- OSTI ID:
- 5870234
- Journal Information:
- IEEE Trans. Nucl. Sci.; (United States), Journal Name: IEEE Trans. Nucl. Sci.; (United States) Vol. 30:1; ISSN IETNA
- Country of Publication:
- United States
- Language:
- English
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Thu Jan 31 23:00:00 EST 1985
· IEEE Trans. Nucl. Sci.; (United States)
·
OSTI ID:5982429
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·
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· Trans. Am. Nucl. Soc.; (United States)
·
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Technical Report
·
Fri May 01 00:00:00 EDT 1981
·
OSTI ID:5818599
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTROL EQUIPMENT
CONTROL ROOMS
CONTROL SYSTEMS
DISPLAY DEVICES
ENRICHED URANIUM REACTORS
EQUIPMENT
PERSONNEL
POWER REACTORS
PWR TYPE REACTORS
RADIATION PROTECTION
REACTOR CONTROL SYSTEMS
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
REGULATIONS
SAFETY
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTROL EQUIPMENT
CONTROL ROOMS
CONTROL SYSTEMS
DISPLAY DEVICES
ENRICHED URANIUM REACTORS
EQUIPMENT
PERSONNEL
POWER REACTORS
PWR TYPE REACTORS
RADIATION PROTECTION
REACTOR CONTROL SYSTEMS
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
REGULATIONS
SAFETY
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS