| Nuclear Regulatory Commission

Issue 18: Steam Line Break with Consequential Small LOCA

This issue effects all PWR-type reactors (Westinghouse, CE, B&W).

In the event of a LOCA in which offsite power remains available, the reactor operator may choose to shut down the emergency

This issue involves a potential deficiency in the ability to control leakage past the main steam isolation valves

This issue addressed the potential problem of radiation embrittlement of reactor vessel support structures

Cracking has occurred in PWR piping systems as a result of stress corrosion, vibratory and thermal fatigue, and dynamic loa

This is an ACRS concern raised by the Subcommittee on TMI-2 Implications in October 1979.

A memorandum[1]from AEOD to NRR dated May 23, 1980 drew attenti

This issue which is identified in NUREG-0705[1]was raised because of the discovery of stress corrosion cracking in the low p

This issue apparently originated as a DOR proposal and was discussed in SECY-80-325.

Under the scope of the TMI Action Plan Item II.K.3 in NUREG-0660,[1]the NRC Bulletin and Orders Task Force conducted generic