DESCRIPTION

This NUREG-0471[1]item is an ACRS generic concern which involves assessing the uncertainties in calculations of the control rod drop accident, including

DESCRIPTION

This issue was documented in NUREG-0471[1]and stemmed from an ACRS recommendation that the staff explore diverse means of obtaining ECCS capability for f

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Historical Background

This issue is described in NUREG-0471[1]and was raised by the ACRS who recommended that stud

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There are no current criteria for acceptability of solidification agents.

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Interpretations of NEPA require the environmental impact assessment include land use impacts and alternatives in nuclear power plant licensing cases.

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SRP[1]Section 15.7.3 requires an analysis of the consequences of failure of tanks containing radioactive liquids

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Licensees are required to estimate the design-basis flood levels for each nuclear power plant site consistent with the requirements in General Design Criterion 2, "Design Bases for P

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This NUREG-0471[1]item was an ACRS generic concern that initially addressed the common mode failure of identical components exposed to identical or nearl

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Historical Background

Structural damage to the primary system, including the reactor pressure vessel and internals, associated piping and steam generator tubing in PWRs, can

DESCRIPTION

Historical Background

The operating experience of nuclear power plants indicates that a number of valves, valve operators, and pumps fail to operate as specified in the techn