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Nondestructive Examination Guidance for Dry Storage Casks

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Nondestructive Examination Guidance for Dry Storage Casks PNNL-24412 Rev. 1 Nondestructive Examination Guidance for Dry Storage Casks September 2016 RM Meyer S Suffield EH Hirt JD Suter JP Lareau JW Zhuge A Qiao TL Moran P Ramuhalli PNNL-24412 Rev. 1 Nondestructive Examination Guidance for Dry Storage Casks RM Meyer S Suffield EH Hirt JD Suter JP Lareau JW Zhuge A Qiao TL Moran P Ramuhalli September 2016 Prepared for the U.S. Nuclear Regulatory Commission under a Related Services Agreement with the U.S. Department of Energy Contract DE-AC05-76RL01830 Pacific Northwest National Laboratory Richland, Washington 99352 Abstract This report reviews nondestructive examination (NDE) methods and their applicability to aging effects in concrete overpack and metal canister components to support U.S. Nuclear Regulatory Commission staff with review of renewal applications for welded canister-type dry storage systems (DSSs). In the United States, several DSSs for commercial spent nuclear fuel are approaching the end of their initial licensed or certified term. Many of these systems have originally been licensed or certified for 20 years, after which they may be renewed for periods up to 40 years, according to Title 10 of the Code of Federal Regulations (10 CFR), Part 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High- Level Radioactive Waste, and Reactor-Related Greater than Class C Waste.” An analysis of implementation of NDE methods to concrete horizontal storage modules (HSMs) in Transnuclear NUHOMS 80 and 102 DSSs is provided as an example to illustrate factors that should be considered when reviewing NDE methods proposed by applicants for welded canister-type DSSs in general. The analysis for concrete HSM components is performed by literature review of documents by the American Concrete Institute (ACI), Transportation Research Board (TRB), International Atomic Energy Agency (IAEA), U.S. Department of Energy (DOE), the BAM Federal Institute for Materials Research and Testing in Germany, and others. For the metal canister, the American Society for Mechanical Engineers Boiler & Pressure Vessel Code is used primarily as the basis for NDE methods considered, along with currently funded efforts through industry (Electric Power Research Institute) and the DOE to develop inspection technologies for canisters. iii Summary In the United States, several dry storage systems (DSSs) for commercial spent nuclear fuel are approaching the end of their initial licensed or certified term. Many of these systems have originally been licensed or certified for 20 years, after which the licensing or certification may be renewed for periods up to 40 years, according to Title 10 of the Code of Federal Regulations (10 CFR), Part 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste.” Guidance for review of license renewal applications is provided in NUREG-1927, Standard Review Plan for Renewal of Spent Fuel Dry Cask Storage System Licenses and Certificates of Compliance. A review of aging effects that could affect important to safety (ITS) structures, systems, and components (SSCs) is required in renewal applications and applicants are required to address aging effects using either a time-limited aging analysis or an aging management program. The U.S. Nuclear Regulatory Commission (NRC) has recently prepared a revision to NUREG- 1927 (Rev. 1) to clarify guidance on aging management expectations for renewal applications. This report is intended to support NRC staff in the reviews of renewal applications for welded canister DSSs. It provides a review of nondestructive examination (NDE) techniques applicable to concrete structures and metal welded canisters in DSSs. For each of the NDE techniques, the report provides a summary of the operating principles, a narrative of laboratory and field experience, a discussion of the important factors that influence the quality of the data, and a listing of the limitations. Although the NUHOMS 80 and 102 system designs are specifically considered in this report, the information on NDE methods and their applicability to aging effects in ITS SSCs included in Sections 2.0 and 3.0 are generally applicable to all welded canister DSSs that employ similar materials. The application to NUHOMS 80 and 102 system designs provides an example to highlight factors NRC staff should consider in reviewing proposed applications of NDE methods to welded canister DSS designs, in general. Several documents provide the basis for the NDE methods considered in this report for inspection of horizontal storage module (HSM) concrete components including documents by the American Concrete Institute (ACI): ACI 349.3R, Evaluation of Existing Nuclear Safety-Related Concrete Structures and ACI 228.2R-13, Report on Nondestructive Test Methods for Evaluation of Concrete in Structures. In addition, documents by the Transportation Research Board (TRB), International Atomic Energy Agency (IAEA), U.S. Department of Energy (DOE), and the BAM Federal Institute for Materials Research and Testing in Germany have informed the consideration of NDE methods for concrete structures in this report. Applicability of NDE methods is analyzed for several aging effects in concrete including delaminations and voids, vertically oriented cracks, continuously distributed degradation, corrosion of embedded steel, and changes in dimensions. Implementation capability for NDE methods is also analyzed for HSM components by considering relevant factors such as the specimen thickness, size and density of reinforcing steel, accessibility to the surface, and specimen geometry. For the metal canister, the American Society for Mechanical Engineers (ASME) Boiler & Pressure Vessel Code (B&PV Code) is used primarily as the basis for NDE methods considered, along with currently funded efforts through industry (Electric Power Research Institute) and the DOE to develop inspection technologies for canisters. This limited the scope of NDE methods considered for the metal canister to visual testing, bulk ultrasound testing, guided ultrasonic wave testing, eddy current testing, and acoustic emission testing. The aging effects in metals considered include surface-breaking cracks and localized corrosion. The applicability of NDE methods to cracks in metal is determined on the basis of several studies to assess and document performance of NDE methods for detecting cracks in metallic components in light water reactors (LWRs). In these studies, crack detection was based on direct observation of a crack. Localized corrosion can infer the likelihood of crack formation or may infer that cracking already exists. In this scenario, cracks can also be detected indirectly through the observation of localized corrosion. v Acknowledgments The work described in this report was sponsored by the U.S. Nuclear Regulatory Commission (NRC) under the contract number NRC-HQ-60-14-D-0020. Gratitude is extended to Bruce Lin who served as the NRC project manager and to Darrell Dunn and Ricardo Torres of the NRC who provided input on the content of the report. Gratitude is also reserved for Kay Hass of Pacific Northwest National Laboratory who helped edit and format this report. vii Acronyms and Abbreviations AASHTO American Association of State Highway and Transportation Officials ACI American Concrete Institute AE acoustic emission AET acoustic emission testing ASME American Society for Mechanical Engineers ASNT American Society for Nondestructive Testing ASTM American Society for Testing and Materials B&PV Code Boiler & Pressure Vessel Code BWR boiling water reactor COD crack opening displacement DOE U.S. Department of Energy DMW dissimilar metal weld DSC dry shielded canister DSS dry storage systems ECT eddy current testing EMAT electromagnetic acoustic transducer EPRI Electric Power Research Institute GPM galvanostatic pulse measurement GPR ground penetrating radar GUW guided ultrasonic wave HCP half-cell potential HSM horizontal storage module IAEA International Atomic Energy Agency ID inner diameter IE impact echo IGSCC intergranular stress corrosion cracking IR impulse response IRT infrared thermography ISFSI independent spent fuel storage installation ISI inservice inspection ITS important to safety LPR linear polarization resistance LWR light water reactor LWRS Light Water Reactor Sustainability (program) MsS magnetostrictive sensor NDE nondestructive examination ix NDT nondestructive testing NRC U.S. Nuclear Regulatory Commission OD outer diameter PAUT phased-array ultrasonic testing PDT partially destructive testing PINC Program for the Inspection of Nickel Alloy Components POD probability of detection PTZ pan-tilt-zoom PWR pressurized water reactor RM resistivity measurements SASW spectral analysis of surface waves SCC stress corrosion cracking SH shear horizontal SHRP 2 Second Strategic Highway Research Program SNR signal-to-noise ratio SSCs structures, systems, and components TOFD time-of-flight diffraction TRB Transportation Research Board UPE ultrasonic pulse echo UPV ultrasonic pulse velocity USW ultrasonic surface wave UT ultrasonic testing Vg group velocity Vp phase velocity VT visual testing x Definitions Air Void* A space in cement paste, mortar, or concrete filled with air Aggregate* Granular material, such as sand, gravel, crushed stone, crushed hydraulic cement concrete, or iron blast-furnace slag, used with a cementing medium to produce either concrete or mortar Cement* Any of a number of materials that are capable of binding
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