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          NRC Library  Document Collections  NUREG-Series Publications  Publications Prepared by NRC ContractorsUltrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Validation (NUREG/CR-7142, PNNL-21547)

On this page: Publication Information AbstractDownload complete document NUREG/CR-7142 (PDF - 6.19 MB)Publication Information **Manuscript Completed:** July 2012**Date Published:** August 2012 **Prepared by:** S. L. Crawford, A. D. Cinson, P. J. MacFarlan, B. D. Hanson, R. A. Mathews Pacific Northwest National Laboratory P.O. Box 999 Richland, WA 99352 G. Oberson, NRC Project Manager NRC Job Code N6783 Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington DC 20555-0001 Availability Notice Abstract The objective of this investigation was to evaluate the efficacy of ultrasonic testing (UT) for primary water leak path assessments of reactor pressure vessel (RPV) upper head penetrations. Operating reactors have experienced leakage when stress corrosion cracking of nickel-based alloy penetrations allowed primary water into the annulus of the interference fit between the penetration and the low-alloy steel RPV head. In this investigation, UT leak path data were acquired for an Alloy 600 control rod drive mechanism nozzle penetration, referred to as Nozzle 63, which was removed from the North Anna Unit 2 reactor when the RPV head was replaced in 2002. In-service inspection prior to the head replacement indicated that Nozzle 63 had a probable leakage path through the interference fit region. Nozzle 63 was examined using a phased-array UT probe with a 5.0-MHz, eight-element annular array. Immersion data were acquired from the nozzle inner diameter surface. The UT data were interpreted by comparing to responses measured on a mockup penetration with known features. Following acquisition of the UT data, Nozzle 63 was destructively examined to determine if the features identified in the UT examination, including leakage paths and crystalline boric acid deposits, could be visually confirmed. Additional measurements of boric acid deposit thickness and low-alloy steel wastage were made to assess how these factors affect the UT response. The implications of these findings for interpreting UT leak path data are described. 
      
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