Agency topical meetings in 1995 to review the status of generic safety issues


Reactor type Topic

WWER-440/230 Reactor pressure vessel integrity.
Confinement improvement options.
Confinement leak rate measurements.
WWER-1000 Control rod insertion reliability.
Steam generator integrity
RBMK Evaluation of void and other reactivity effects.
Shutdown system modernization.
Leak before break applications.

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