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Foley, W.J.; Dean, R.S.; Hennick, D.A.
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Projects III, IV, V and Special Projects; Parameter, Inc., Elm Grove, WI (USA)1988
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Projects III, IV, V and Special Projects; Parameter, Inc., Elm Grove, WI (USA)1988
AbstractAbstract
[en] Documentation is provided in this report for the closeout of IE Bulletin 80-14 regarding degradation of safety-related scram discharge volume (SDV) systems in General Electric (GE) boiling water reactors (BWRs). Closeout is based on the implementation and verification of six required licensee actions. Evaluation of utility responses and NRC/Region inspection reports indicates that the bulletin is closed for all of the 23 facilities to which it was issued for action. The bulletin was issued June 12, 1980, as a result of SDV events at two plants. Furthermore, studies of related anticipated transients without scram (ATWS) raised concern that the SDV function may be degraded by the undetected presence of fluid in the SDV. The bulletin was forwarded for information only to all GE power reactor facilities with a construction permit
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Nov 1988; 17 p; PARAMETER/IE--172; NTIS, PC A03/MF A01 - US Govt. Printing Office. - OSTI as TI89002947
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