The calculations of differential pressure that occur in containment subcompartments from a loss-of-coolant event require a complex fluid dynamic analysis to assure that the subcompartment design pressures are not exceeded. To check the various industry computer codes used for the analyses, a standard problem was issued to the reactor vendors and architect/engineers (A/E) so that their models and calculational methods could be
evaluated. This NUREG-0471[1] task involved the review and evaluation of the subcompartment standard problem analyses supplied by vendors and A/Es to determine the validity of their models. Changes in the computer codes utilized by the NRC staff could also result from this task.
This item is a Licensing Issue. As a part of the improvements to NUREG-0933, the NRC staff clarified in SECY-11-0101, "Summary of Activities Related to Generic Issues Program," dated July 26, 2011,[2] that the
Generic Issues Program will not pursue any further actions toward resolution of licensing and regulatory impact issues. Because licensing and regulatory impact issues are not safety issues by the classification guidance
in the legacy Generic Issues Program, these issues do not meet at least one of the Generic Issues Program screening criteria and do not warrant further processing in accordance with Management Directive 6.4, "Generic
Issues Program," dated November 17, 2009.[3] Therefore, this issue will not be pursued any further in the Generic Issues Program.
[1] NUREG-0471, "Generic Task Problem Descriptions (Categories B, C, and D)," U.S. Nuclear Regulatory Commission, June 1978.
[2] SECY-11-0101, "Summary of Activities Related to Generic Issues Program," July 26, 2011. [ML111590814]
[3] Management Directive 6.4, "Generic Issues Program," U.S. Nuclear Regulatory Commission, November 17, 2009.
Page Last Reviewed/Updated 06/24/2025