Daily Rules, Proposed Rules, and Notices of the Federal Government
On July 10, 2012, the petitioners requested that the NRC take action with regard to Brunswick. The petitioners request that the NRC take action in the form of an order either modifying the Brunswick operating licenses' technical specifications (as detailed in the petition) or requiring the licensee to submit amendment requests for these licenses.
As the basis for this request, the petitioners stated that “the current technical specifications for the Brunswick Units 1 and 2, reactors are based on the assumption that the sole scenario involving damage to irradiated fuel outside of the reactor vessel is that resulting from a fuel handling accident involving recently irradiated fuel (i.e., fuel that was within a critical reactor core within the past 24 hours).” However, “loss of water inventory from the spent fuel pool or sustained loss of its cooling capability can also result in damage to irradiated fuel. And the potential extent of that damage and the amount of radioactivity released from damaged fuel can be considerably larger than that resulting from a fuel handling accident.” The petitioners stated that “because the probability of spent fuel pool water inventory or cooling loss is not so low as to be neglected, the technical specification provisions that currently manage the risk from a fuel handling accident must be extended to also cover other credible spent fuel pool events.”
The NRC is handling this petition pursuant to Title 10 of the
For the Nuclear Regulatory Commission.