Pages that link to "PNO-I-87-043, on 870514,during Reactor Trip Breaker Response Time Testing,Reactor Trip Occurred.Steam Generator Feedwater Isolation Pressure Transient Resulted in Failure of Two Lines to Thermal Relief Valves.Cause Under Investigation"

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The following pages link to PNO-I-87-043, on 870514,during Reactor Trip Breaker Response Time Testing,Reactor Trip Occurred.Steam Generator Feedwater Isolation Pressure Transient Resulted in Failure of Two Lines to Thermal Relief Valves.Cause Under Investigation:

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