Operator/instrumentation interactions during the Three Mile Island incident
Description
A discussion is presented of the operator/instrumentation interactions which had an effect on the course of the incident at the Three Mile Island-2 Nuclear Power Plant. A brief review of the sequence of occurrences at TMI-2 over the first 16 hours of the incident is given with particular emphasis on operator/instrumentation interactions. A breakdown of the six major items that seemed to have contributed to the characteristics of the incident is then given and also an outline of some of the currently proposed operator/instrumentation improvements. The six major items involve water level indication in the reactor, electromatic relief valve operation, auxiliary feed-water flow indication, containment isolation, extended range instrumentation, and computer readout
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- UCRL--82227
Conference
- Title
- IEEE symposium on nuclear power systems.
- Dates
- 19 Oct 1979.
- Place
- San Jose, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11517522
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- PERFORMANCE; PERSONNEL; REACTOR ACCIDENTS; REACTOR INSTRUMENTATION; REACTOR OPERATION; THREE MILE ISLAND-2 REACTOR
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-791060--1.