Published 1980
| Version v1
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Response trees for emergency operator action at the LOFT facility
Description
Following the onset of an accident which disables equipment used for normal reactor cooling, the first priority of the nuclear plant operator is to ensure that the reactor core is covered and that adequate cooling water flow is established. During this time, he must evaluate the situation, determine which emergency procedures apply, find the appropriate procedures, and perform the prescribed actions. Failure to respond quickly and effectively could result in expensive facility damages and potential hazards to the public. A procedure which attempts to streamline this short-term response process has been developed and implemented for the Loss of Fluid Test (LOFT) facility
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
11541305.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- CONF-800403--2
Conference
- Title
- ANS thermal reactor safety meeting.
- Dates
- 8 - 11 Apr 1980.
- Place
- Knoxville, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11541305
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAULT TREE ANALYSIS; LOFT REACTOR; PERSONNEL; REACTOR ACCIDENTS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; PWR TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS