This is a late non-emergency notification to the NRC Operations Center in accordance with
10 CFR 50.72(b)(3)(ii)(A) due to the degradation of a principal safety barrier.
A flaw in a weld in a 3/4 inch test connection off the seal water injection line for the 4B reactor coolant pump was identified at approximately 1230 during a containment entry on August 7, 2008. The flaw is leaking at the rate of approximately 0.14 gpm (current total), it [the leak] is isolable, and the leakage is currently considered as unidentified leakage from the reactor coolant system. The Technical Specification limit for unidentified leakage is 1.0 gpm.
Currently, the leak is being monitored while repair options are evaluated.
The licensee notified the NRC Resident Inspector.
