This Interim Staff Guidance (ISG) provides guidance to the staff on classifying spent nuclear
fuel as either (1) damaged, (2) undamaged, or (3) intact, before interim storage or
transportation. This is not a regulation or requirement and can be modified or superseded by
an applicant with supportable technical arguments.
Revision 2
The objective of this calculation is to calculate the probability of occurrence for fuel assembly (FA) misloads (i.e., FA placed in the wrong location) and FA damage during FA movements. The scope of this calculation is provided by the information obtained from the Framatome ANP 2001a report. The first step in this calculation is to categorize each fuel-handling event that occurred at nuclear power plants. The different categories are based on FAs being damaged or misloaded. The next step is to determine the total number of FAs involved in the event.
This report describes the characterization plan, methods, and results for light water reactor (LWR) Materials Characterization Center (MCC) spent fuel Approved Testing Material (ATM)-101. ATM-101 is spent fuel from H. B. Robinson, Unit 2, Assembly B0-5, a moderate-burnup, pressurized water reactor (PWR) fuel that released very small quantities of fission products and fission gas from the fuel during commercial operation.
