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Post-implementation review of inadequate core cooling instrumentation
| Content Provider | United States Department of Energy Office of Scientific and Technical Information (OSTI.GOV) |
|---|---|
| Author | Anderson, J. L. Anderson, R. L. Hagen, E. W. Morelock, T. C. Huang, T. L. Phillips, L. E. |
| Organization | Oak Ridge National Lab., TN (USA) |
| Abstract | Studies of Three Mile Island (TMI) accident identified the need for additional instrumentation to detect inadequate core cooling (ICC) in nuclear power plants. Industry studies by plant owners and reactor vendors supported the conclusion that improvements were needed to help operators diagnose the approach to or existence of ICC and to provide more complete information for operator control of safety injection, flow to minimize the consequences of such an accident. In 1980, the US Nuclear Regulatory Commission (NRC) required further studies by the industry and described ICC instrumentation design requirements that included human factors and environmental considerations. On December 10, 1982, NRC issued to Babcock and Wilcox (BandW) licensees' orders for Modification of License and transmitted to all pressurized water reactor (PWR) licensees Generic Letter 82-28 to inform them of the revised NRC requirements. The instrumentation requirements for detection of ICC include upgraded subcooling margin monitors (SMMs), upgraded core exit thermocouples (CETs), and installation of a reactor coolant inventory tracking system (RCITS). |
| Related Links | https://www.osti.gov/biblio/6649715 |
| Page Count | 11 |
| File Format | |
| Language | English |
| Publisher Date | 1988-01-01 |
| Publisher Place | United States |
| Access Restriction | Open |
| Subject Keyword | GENERAL STUDIES OF NUCLEAR REACTORS SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS PWR TYPE REACTORS REACTOR CORES REACTOR INSTRUMENTATION HEAT TRANSFER HYDRAULICS REACTOR ACCIDENTS REACTOR COOLING SYSTEMS REACTOR SAFETY REGULATIONS TEMPERATURE MONITORING ACCIDENTS COOLING SYSTEMS ENERGY SYSTEMS ENERGY TRANSFER FLUID MECHANICS MECHANICS MONITORING REACTOR COMPONENTS REACTORS SAFETY WATER COOLED REACTORS WATER MODERATED REACTORS 220900 - Nuclear Reactor Technology-- Reactor Safety Nonboiling Water Cooled LightWater Moderated Power Reactors Nonbreeding |
| Content Type | Text |
| Resource Type | Article |
