ML19220C984
| ML19220C984 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/11/1979 |
| From: | Cunningham M NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| SER-790511, NUDOCS 7905160139 | |
| Download: ML19220C984 (1) | |
Text
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4 For the purposes of comparison, the TMI-2 event would be defined in the RSS nomenclature as an accident sequence labeled TMLQ,'with TM referring to the loss of the main feedwater system, L referring to the failure or.
demand of the auxiliary feedwater system, and Q being the failure of the power-operated relief valve to reclose.
Implicit in this definition is the operability of the ECCS system and the containment ESFs.
In the RSS, the accident sequence TMLQ was assessed to cause.large scale melting of the core. However, because of tne operation of the containment ESFs, the release of radioactive material to the environment was relatively small, and public health impacts were estimated to be insignificant.
The TMI-2 event was different from the RSS accident sequence TMLQ in a number of respects.
For example, human actions following the initial event which either shut off systems (i.e., HPIS) or restored systea operability (AFWS restoration and reclosing the relief valve, were considered in RSS, but were not specifically included in the analysis.
s Other differences, such as in the' plant design, and core inventories f various radioisotopes, also are noteworthy in comparison of the TMI-o event and the RSS analyses.
The combination of these differences results in the outcome of the TMI event being significantly less core damage (i.e., no gross fuel-melting) and insignificant public nealth effects.
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