Hopefully this email will get to all the Westinghouse pwr Reactor Engineers for them to reply.
Wolf Creek is currently putting together the paperwork for an application to the NRC for Plant Life Extension. We currently track and evaluate incore thimble tube fretting wear in our lower internals, fuel assembly bottom nozzle, and lower core plate using a spreadsheet we have developed that has an input from Eddy Current Test results that are obtained every refueling outage. The group set up for gathering information for Plant Life Extension indicates the NRC requires a procedure instead for the analysis and actions taken as a result of the analysis.
1) Do any of you use such a procedure, and if you do, could you supply me a copy to model one after to use at Wolf Creek? 2) If any of you have been approved for Plant Life Extension, did the NRC require such a procedure for your plant in order to be approved. 3) How do you account for wear scars that may extend into the area of repositioned thimble tube,i.e., a repositioning of 2 inches still is in the wear area and the next ECT shows large amount of wear in one cycle of operation.
I would appreciate the above information so that if I need to write a procedure for analysis, it is very similar to procedures at other plants so it will not be used to ratchet other plants to revise their procedure or NOT get approved for Plant Life Extension.