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On November 10, 1979, an event occurred at the Oconee Power Station, Unit 3, that resulted in loss of power to a non-Class 1E 120-volt AC single-phase power panel that supplied power
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 diesel generators shortly af
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 loading.
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 attention to the generic issue of BW
This issue which is identified in NUREG-0705[1]was raised because of the discovery of stress corrosion cracking in the low pressure discs of Westinghouse
This issue apparently originated as a DOR proposal and was discussed in SECY-80-325.[1]The i
