United States Nuclear Regulatory Commission - Protecting People and the Environment

Resolution of Generic Safety Issues: NUREG-0933: Footnote 97 ( NUREG-0933, Main Report with Supplements 1–35 )

97.NUREG-0623, "Generic Assessment of Delayed Reactor Coolant Pump Trip during Small Break Loss-of-Coolant Accidents in Pressurized Water Reactors," U.S. Nuclear Regulatory Commission, November 1979.