ML20097H694

Probability of Pipe Failure in the Reactor Coolant Loops of Westinghouse PWR Plants.Volume 2:Pipe Failure Induced by Crack Growth

ML20097H694
Person / Time
Issue date:	08/31/1984
From:	Benda B, Mensing R, Woo H LAWRENCE LIVERMORE NATIONAL LABORATORY
To:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
CON-FIN-A-0133, CON-FIN-A-133, FRN-51FR12502 AB76-2-29, AB76-2-298, NUREG-CR-3660, NUREG-CR-3660-V02, NUREG-CR-3660-V2, UCID-19988, NUDOCS 8409200445
Download: ML20097H694 (71)