Lead Expansion Anchor Load Capacity in Reactor Buildings at the Savannah River Site.

摘要

Walkdowns to determine the seismic adequacy of selected safety systems have been performed for L and K reactors utilizing the Unresolved Safety Issue (USI) A-46 methodology sponsored by the Seismic Qualification Utility Group (SQUG). Actual experience data from earthquakes, test data compiled by the Electric Power Research Institute (EPRI), and other data for certain classes of nuclear plant equipment make up the SQUG data base. Anchorage is also addressed in the USI A-46 methodology. However, lead expansion anchors are not included. Some safety related equipment in the Savannah River Site (SRS) reactor buildings is supported by lead expansion anchors. Design load capacity was based on the allowable loads listed in SRS Standard B8M which was intended to provide a factor of safety of 4. However, walkdowns have revealed that some lead anchors are not installed per B8M, and therefore the actual load capacity of these anchors may be less than indicated in the B8M. A testing program (SP-2449) was developed and 107 abandoned anchors in K, L, P and R reactor buildings were tested to determine shear and tension load capacities. 14 figs., 2 tabs.