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51315-5767-Testing and Analyses of Davis-Besse Alloy 600 Control Rod Drive Mechanism Nozzles

Product Number: 51315-5767-SG
ISBN: 5767 2015 CP
Author: David Alley
Publication Date: 2015
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$20.00
$20.00
During an inspection in 2002 control rod drive mechanism (CRDM) nozzle 3 and its associated weld of the original reactor pressure vessel head (RPVH-1) at Davis-Besse Nuclear Power Station Unit 1 was found to be damaged due to a combination of pressurized water stress corrosion cracking (PWSCC) and boric acid corrosion. This nozzle was fabricated from alloy 600 heat M3935. Due to the extent of damage to RPVH-1 it was replaced with an identical head from the cancelled Midland plant. The majority of CRDM housings in the replacement head (RPVH-2) were fabricated from alloy 600 heat M7929. Operations resumed in 2004. During a 2010 inspection cracking was detected in 24 of 69 CRDM nozzles and their associated welds of RPVH-2. Repairs were made to these nozzles. In 2011 RPVH-2 was replaced with a head containing nozzles fabricated from alloy 690. This paper discusses crack growth rate and material characterization performed on samples removed from RPVH-2 and compares these results to previously conducted testing from RPVH-1. While crack growth rates of both materials were found to be high substantial differences were observed between the two samples in both microstructure and grain boundary chemistry.
During an inspection in 2002 control rod drive mechanism (CRDM) nozzle 3 and its associated weld of the original reactor pressure vessel head (RPVH-1) at Davis-Besse Nuclear Power Station Unit 1 was found to be damaged due to a combination of pressurized water stress corrosion cracking (PWSCC) and boric acid corrosion. This nozzle was fabricated from alloy 600 heat M3935. Due to the extent of damage to RPVH-1 it was replaced with an identical head from the cancelled Midland plant. The majority of CRDM housings in the replacement head (RPVH-2) were fabricated from alloy 600 heat M7929. Operations resumed in 2004. During a 2010 inspection cracking was detected in 24 of 69 CRDM nozzles and their associated welds of RPVH-2. Repairs were made to these nozzles. In 2011 RPVH-2 was replaced with a head containing nozzles fabricated from alloy 690. This paper discusses crack growth rate and material characterization performed on samples removed from RPVH-2 and compares these results to previously conducted testing from RPVH-1. While crack growth rates of both materials were found to be high substantial differences were observed between the two samples in both microstructure and grain boundary chemistry.
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