ML13220A063

Dsd ED2013 3267 Presentation, Primary Water Stress Corrosion Cracking Tests and Metallurgical Analyses of Davis-Besse Control Rod Drive Mechanism Nozzle #4.

ML13220A063
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Site:	Davis Besse
Issue date:	08/30/2013
From:	Alexandreanu B, David Alley, Bruemmer S, Jay Collins, Darrell Dunn, Toloczko M Argonne National Lab (ANL), Office of Nuclear Regulatory Research, Pacific Northwest National Laboratory
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Dunn D
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Primary Water Stress Corrosion Cracking Tests and Metallurgical Analyses of Davis

-Besse Control Rod Drive Mechanism Nozzle #4 D.S. Dunn 1, J. Collins 1, D. Alley 1, B. Alexandreanu 2 , S.M. Bruemmer 3 , M.B. Toloczko 3 1 United States Nuclear Regulatory Commission, Washington DC 2 Argonne National Laboratory, Argonne, IL 3 Pacific Northwest National Laboratory, Richland, WA Disclaimer: The work reported in this paper was supported by the Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. The views expressed in this paper are not necessary those of the U.S. Nuclear Regulatory Commission

Outline Background Test materials Crack growth rate testing Metallurgical analyses Summary Environmental Degradation of Materials in Nuclear Power Systems

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Background

2002 PWSCC indication

-Through wall PWSCC in Nozzle #3

-Significant corrosion of the low alloy steel reactor pressure vessel head (RPVH)

-Replaced with RPVH from the cancelled Midland, MI PWR -Operation resumed in 2004 2010 PWSCC indication

-Observed after 5.5 effective full power years of operation

-Bare metal visual: 13 potential leaking nozzles, Nozzle #4 confirmed leaker -Volumetric: 11 axial indications, 1 small circumferential indications, and 2 leak paths Nozzles #4 & #67

-Surface: 12 indications; 6 were potential leakers Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 3 2010 Inspection Results Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 4 Continued Operation Licensee performed 1/2 nozzle repairs on 24 nozzles Sample of Nozzle #4 provided to the NRC for testing and analyses On June 18, 2010, the licensee informed NRC that Davis

-Besse would shut down on October 1, 2011 to replace the head Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 5 Test Materials Environmental Degradation of Materials in Nuclear Power Systems

- 2013 Alloy 600 heat Ni Cr Fe Mn C P Cu Co Si S B* (appm) SB-167 Specification 72.0 min 14.0-17.0 6.0-10.0 1.0 max 0.15 max N/A 0.5 max N/A 0.5 max 0.015 max N/A M3935 77.89 15.58 6.25 0.27 0.028 0.004 0.01 0.01 0.37 0.0022 69 M7929 75.28 16.12 7.24 0.26 0.03 N/A 0.01 0.05 0.45 0.003 77 *Boron concentration measured by PNNL Alloy 600 heat Yield Strength, MPa Tensile Strength, MPa Elongation, percent Hardness, Vickers

• Min Max Ave +/- SDEV SB-167 Specification 205 min 550 min 35 min N/A N/A N/A M3935 334 590 60 146.6 190.7 160.2 +/- 6.5 M7929 296 668 53 166.6 209.5 186.5 +/- 9.6 *Hardness in the crack growth plane for M3935

-RPVH #1-CRDM #1 and M7929

-RPVH #2-CRDM #4 measured by PNNL 8/13/2013 6 Nozzle #4 Section 90 o section of Nozzle #4 cut from below the J

-groove weld Penetrant test revealed no surface cracking indications 5 compact tension (CT) test specimens machined from this section Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 7 Test Specimen Machining Layout for compact tension specimens Sample for metallurgical analyses (next to Specimen DB

-3) All specimens were free releasable after machining Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 8 Test Specimens 2 - 1/2 thickness (T)

- compact tension (CT) specimens -Tested at Argonne National Laboratory (ANL) 3 - 1/4 T-CT specimens

-1 tested at ANL -2 tested at Pacific Northwest National Laboratory (PNNL)

Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 9 Testing and Analyses Machined compact tension test specimens supplied to Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL) Primary objective was to obtain crack growth rates for the replacement RPVH alloy 600 nozzle material (heat M7929).

Secondary objective was to characterize Alloy 600 material microstructure and correlate microstructure to crack growth rates Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 10 Crack Growth Rate Testing Crack growth rate test systems located at ANL used to obtain accurate crack growth rates Testing in autoclaves under simulated PWR conditions Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 11 Crack Growth Rate Testing Corrections applied to measured CGR to account for the formation of ligaments Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 12 Crack Growth Rate Testing Formation and breaking of ligaments that affected CGR measurements was also observed at constant K Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 13 Crack Growth Rate Testing Formation of ligaments that affected CGR measurements was confirmed by examination of the fracture surfaces Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 14 Crack Growth Rates Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 15 Temperature Sensitivity Activation energy typical of alloy 600 Environmental Degradation of Materials in Nuclear Power Systems

- 2013 10-1210-1110-1010-91.551.601.651.701.751.80M7929 1/2T CT DB-5 (DB600-CL-2)M7929 1/2T CT DB-4 (DB600-CL-1)CGR (m/s)1000/T (°K)Alloys 600 Heat M7929 PWR Water 10-45 cc/kg H 2333315298283Temperature (°C)352Q = 145 kJ/mol (35 kcal/mol)

Kmax = 27 MPa m1/28/13/2013 16 Fracture Surfaces Predominately intergranular cracking on fracture surface of the CT specimens Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 17 Fracture Surfaces Transgranular extension during air precracking at room temperature.

Rapid intergranular engagement High degree of crack branching Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 18 Metallurgical Analyses Replacement Davis

-Besse RPVH CRDM Nozzle #4

- Alloy 600 Heat M7929 Red arrows: grain boundaries Blue Arrows: carbides

Conclusion:

carbides located on prior grain boundaries; not an ideal microstructure for PWSCC resistance Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 19 20 µm 20 µm Metallurgical Analyses Original Davis

-Besse RPVH CRDM Nozzle #3

- Alloy 600 Heat M3935 Carbides present at grain boundaries Material was susceptible to PWSCC (NUREG/CR-6921, November 2005) Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 20 Atomic Probe Tomography Environmental Degradation of Materials in Nuclear Power Systems

- 2013 M3935 M7929 8/13/2013 21 Environmental Degradation of Materials in Nuclear Power Systems

- 2013 Davis-Besse Alloy 600 Original RPVH 15.78 EFPY PWSCC of CRDM nozzles and boric acid corrosion of the low alloy steel RPVH Alloy 600 heat M3935

-Grain boundary carbides with 500 - 700 nm spacing

-200 - 400 micron grain size

-160.2 +/- 6.5 Hv -6 atomic percent boron at grain boundaries with significant chromium depletion Replacement RPVH 5.5 EFPY PWSCC of CRDM nozzles Alloy 600 heat M7929

-Transgranular carbides on prior grain boundaries 30 micron grain size

-186.5 +/- 9.6 Hv -2.5 atomic percent boron at grain boundaries 8/13/2013 22 Summary Laboratory crack growth rates in the replacement Davis

-Besse RPVH were typically between the 25% and 95% of the MRP

-55 disposition curves Fracture surface examinations show a high degree of intergranular engagement consistent with materials susceptible to PWSCC Alloy 600 heat M3935 from the original RPVH were found to have significant enrichment of boron on grain boundaries that were depleted in chromium Microstructure of the alloy 600 M7929 heat from the replacement RPVH likely contributed to the increased PWSCC susceptibility Environmental Degradation of Materials in Nuclear Power Systems

- 2013 8/13/2013 23 Acknowledgements The authors gratefully acknowledge the work by Mr. Jim Hyres at BWXT to decontaminate some of the samples and helpful suggestions provided by Drs. Mirela Gavrilas and Rob Tregoning Environmental Degradation of Materials in Nuclear Power Systems

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