ML20072F261

RPV Surveillance Matls Testing

ML20072F261
Person / Time
Site:	Brunswick
Issue date:	05/24/1994
From:	Contreras G, Stevens G GENERAL ELECTRIC CO.
To:
Shared Package
ML20072F244	List: BSEP-94-0316, Forwards Reactor Vessel Matl Surveillance Specimen Test Results,Per 10CFR50,App H ML20072F250 ML20072F261 ML20072F266 ML20072F271 ML20072F286 ML20072F290
References
GE-NE-523-23-02, GE-NE-523-23-0294, GE-NE-523-23-2, GE-NE-523-23-294, NUDOCS 9408230265
Download: ML20072F261 (35)

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Technical Senices Business 3-1 General Electric Company,175 Curtner Avenue, San Jose, CA 95125 4-Gk D1 M

4-4-l 5- BRUNSWICK UNIT 1 6-RPV SURVEILLANCE MATERIALS TESTING 7

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G. W. Contreras, Senior Engineer l 4

RPV integrity 5

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G. L. _

Structural Mechanics l

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GE NE-52 i-2.i-u294 Revision 0 DRF 137-0010 7 A13STRACT The surveillance capsule at the 300 vessel azimuth location was removed from the Brunswick Unit I reactor during the Summer of 1993. The capsule contained flux wires for l

neutron fluence measurement and Charpy and tensile test specimens for material property

' evaluation. The flux wires were evaluated to determine the specific activity of each wire V-Notch impact testing and uniaxial tensile testing were performed to establish the i

the irradiated surveillance materials.

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GE-NE-523-23 02W Revision 0 DRF 137 0010-7 ACKNOWLEDGMENTS The author gratefully acknowledges the efforts of other people towards completion of the l i

contents of this report Charpy testing was completed by G. P. Wozadio and G. E Dunning Tensile specimen  !

testing was done by S. B. Wisner and G. E. Dunning, and chemical composition analysis was 8 performed by C. R. Judd. Flux wire testing was performed by G. C. Martin.

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a GE NE-523-23-0294 Revision 0 DRF 137-0010-7

1. INTRODUCTION Part of the efrort to assure reactor vesselintegrity involves evaluation of the fracture toughness of the vessel ferritic materials. The key values which characterize a material's fracture toughness are the reference temperature of nil ductility transition (RTNDT) and the upper shelf energy (USE). These are referenced in 10CFR50 Appendix G (1) and in Appendix G of the ASME Boiler and Pressure Vessel Code,Section XI (2], and defmed in ASTM E185.

The first vessel surveillance specimen capsule was removed from Unit I during the Summer of 1993. The irradiated capsule was sent to the GE Vallecitos Nuclear Center (VNC) for testing. The surveillance capsule contained flux wires for neutron flux monitoring and Charpy V-Notch impact test specimens and uniaxial tensile test specimens fabricated using materials from the vessel nearest the core (beltline). The impact and tensile specimens were tested to establish properties for the irradiated materials. The results of the surveillance specimen testing are presented in this report, as required per 10CFR50 Appendices G and H [l & 3].

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GE-NE-523-23 02W l Revision 0 DRF 137-0010-7 I

2. SUS 151ARY OF RESULTS l

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The 300 vessel azimuth surveillance capsule was removed and shipped to VNC. The aux wires, Charpy V-Notch and tensile test specimens removed from the capsule were tested according to ASTM E185-82 [6]. The methods and results of the testing are presented in this report as follows:

a. Section 3: Surveillance Capsule Disassembly

b. Section 4: Charpy V-Notch Impact Testing

c. Section 5: Tensile Testing

d. Section 6: Special Chemical Composition

e. Section 7: Flux Wire Analysis The significant results of the evaluation are below; a.

The 300 vessel azimuth position capsule was removed from the reactor. The capsule contained 6 flux wires: 2 copper (Cu),2 iron (Fe), and 2 nickel (Ni).

There were 24 Charpy V-Notch specimens in the capsule: 8 each of plate material, weld material and heat affected zone (HAZ) material. The 6 tensile specimens removed consisted of 2 plate,2 weld and 2 HAZ metal specimens.

b. The purpose of the Dux wire testing was to determine the neutron Cux at the surveillance capsule location. This may be derived using the measured aux wire activity listed in Table 7-1,

c. The surveillance Charpy V-Notch specimens were impact tested at temperatures selected to define the transition of the fracture toughness curves of the plate, weld, and HAZ materials. Measurements were taken of absorbed energy, lateral expansion and percentage shear. From absorbed energy and lateral expansion curve-fit results, the values of USE and ofindex temperature for 30 ft-lb,50 fl-lb and 35 mils lateral expansion (AfLE) were obtained (see Table 4-3). Fracture GE-NE-523 234)244 Revision 0 DRF 137 0010 7 surface photographs of each specimen are presented in Appendix A l

d. The irradiated tensile specimens were tested at room temperature (70 F), and reactor. operating temperature (550 F). The results were tabulated (see Table 5-1) for each specimen including yield and ultimate tensile strength, uniform and total 1

elongation, and reduction of area. 1

e. Chemical composition analysis was performed on several samples of both the base and weld specimens. The results show good agreement with the corresponding l

data from GE QA records l l

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GE-NE-523-23 02W Revision 0 DRF 137 0010-7

3. SURVEILLANCE PROGRAM BACKGROUND 3.1 CAPSULE RECOVERY The reactor pressure vessel (RPV) originally contained three surveillance capsules at 30 ,

120 , and 300 azimuths at the core midplane. The specimen capsules are held against the RPV inside surface by a spring loaded specimen holder. Each capsule receives equal irradiation because of core symmetry. During the Summer 1993 outage, the 300 positioned capsule was removed. The capsule was cut from its holder assembly and shipped by cask to the GE Vallecito Nuclear Center (VNC), where testing was performed.

Upon arrival at VNC, the capsules were examined for identification. The reactor code number,38, and basket group number,1, was marked in binary on opposite sides of the basket.

Also, the basket part number,117C4020Gl as specified in GE drawing i17C4761 and 921DS72 and master parts list 238X111BC, was stamped on the basket, providing positive identification the Brunswick Unit 1300 surveillance capsule materials. The general condition of the basket as received is shown in Figure 3-1, The capsule contained two impact (Charpy) specimen capsules and three tensile specimen capsules. The identification numbers for these capsules are shown Figure 3-2. Each tensile specimen capsule contained two tensile specimens. Each Charpy specimen capsule contained 12 Charpy specimens and 3 flux wires (one iron, one cop nickel)in a sealed helium environment. The specimen locations within the basket / capsules a shown in Figure 3-3.

3.2 RPV MATERIALS AND FABRICATION BACKGROUND The Brunswick i RPV is a 218 inch diameter BWR/4 design. Construction was performed by Chicago Bridge and Iron (CB&l) to the Summer 1967 Addenda of the 1 of the ASME Code. The vessel plates were heat treated prior to welding in two steps:

austenitized at 1650"F for I hour minimum per inch thickness, followed by water quenching and tempered at 1220 F for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> minimum per inch thickness, followed by air cooling. The str relief was typically 1/2 hour minimum per inch thickness at a temperature of i 150*F, follow air cooling. The identification of plates and welds in the beltline region are listed in Table 3 l.

f Material certification records were retrieved from GE Quality Assurance (QA) records to determine chemical properties of the beltline materials. Table 3-1 shows the chemistry data fo the beltline materials.

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GL-NE-52.4 2.4-0294 Revision 0 I DRF 137-0010-7 Table 3-1: Chemical Composition of Vessel Deltline Material Description Pinte llent C Mn P S Cu Si Ni Mo Lower Shell 201 C4535-2 0.23 1.28 0.012 0.015 0.12 0.24 0.58 0.54 251 C4550-1 0.22 1.35 0.010 0.014 0.11 0.21 0.60 0.56 Lower Inter. Shell 301 C4487-la 0.23 1.50 0.010 0.015 0.12 0.27 0.56 0.57 351 B8496-1 0.22 1.45 0.013 0.016 0.19 0.24 0.58 0.55 Nozzles N16A/B N16A/B Q2QlVW 0.21 0.75 0.010 0.015 N/R 0.23 0.80 0.69 Ladle 0.219 0.63 0.006 0.025 N/R 0.24 0.84 0.72 Check ,

C Mn P S Cu Si Ni Mo Wehl Descrip. Ilent Lot No.

Coated Electrodes - Type E8018G/NM 649T273 1726A27A 0.048 1.12 0.017 0.023 0.02 0.52 1.00 0.59 601221 E916A27A 0.041 1.05 0.018 0.015 0.03 0.35 0.88 0.49 88E081 F920A27A 0.06 110 0.017 0.014 0.02 027 093 0.51 977987 3802A27A 0.042 1.04 0.016 0.022 0.03 0.47 1.04 0.59 08T401 F821A27A 0.047 0 93 0.016 0.025 0.02 0.38 0.90 0.52 654W539 S823A27A 0.041 0.95 0.015 0.020 0.04 0.38 1.09 0.58 662A746 H013A27A 0.060 0.96 0.021 0.017 0.03 0.38 0.88 0.52 421 A6811 H010A27A 0.057 1.16 0.020 0.016 0.03 0.50 0.89 0.46 411 A3531 H004 A27A 0.066 1.I3 0.018 0.017 0.02 0.51 0.96 0.47 401Z9711 A022A27A 0.057 1.15 0.021 0,017 0.02 0.39 0.83 0.48 650X006 3807A27A 0.052 0.95 0.020 0.023 0.03 0.40 0.96 0.56 Flux Electrode Combinations - Adcom/INMM Type Linde 124 S3986 3876 Run 934a 0.080 1.42 0.019 0.016 0.05 0.36 0.96 0.52 1P4218 3929 Run 989 0.085 1,43 0.010 0.015 0.06 0.39 0.87 0.45 i'

Nozzle to Vessel Overlay Seam - Type E309-15 W73594 3A922H5C 0.05 1.79 0.020 0.011 N/R 0.54 12.8 N/R i i

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GE-SE 53-D-02W (

Revision 0 DRF 137 0010-7 l l

4. CilARPY V-NOTCil IMPACT TESTING The 24 Charpy specimens recovered from the surveillance capsule were impact tested at l J

temperatures selected to establish the toughness transition and upper shelf of the irradiated materials. Testing was conducted in accordance with ASTM E23-88 [7].

4.1 IMPACT TEST PROCEDURE The Vallecitos testing machine used for irradiated specimens was a Riehle Model PL-2 impact machine, serial number R-89916. The pendulum has a maximum velocity of 15.44 R and a maximum available hammer energy of 240 f1-lb.

The test apparatus and operator were qualified using NIST standard reference material specimens. The standards consist of sets of high and low energy specimens, each desig at a specified energy at the standard test temperature of-40 F. According to ASTM E23-88 the test apparatus averaged results must reproduce the NIST standard values within an accuracy of 5% or 11.0 ft-lb, whichever is greater. The qualification of the Riehle machine and operator is summarized in Table 4-1.

Charpy V-Notch tests were conducted at temperatures between -80 F and 300 F. The cooling fluid used for irradiated specimens tested at temperatures below 70 F was methanol.

temperatures between 70 F and 200 F, water was used as the temperature conditioning fluid The specimens were heated in silicon oil above 200 F. Cooling of the conditioning fluids was done by heat exchange with liquid nitrogen; heating was done by an immersion heater. The b of fluid was mechanically stirred to maintain uniform temperatures. The fluid temperature was measured with a calibrated thermocouple. Once. at test temperature, the specimens were manually transferred with centering tongs to the Charpy test machine and impacted within 5 seconds.

For each Charpy V-Notch specimen the test temperature, energy absorbed, lateral expansion, and percent shear were evaluated. In addition, for the irradiated specimens, photographs were taken of fracture surfaces. Lateral expansion and percent shear were according to specified methods [7]. Percent shear was determined using method number 1 o Subsection 11.2.4.3 of ASTM E23-88 [7], which involves measuring the length and width of the cleavage surface and determining the percent shear value from Tables I or 2 of ASTM E23-88

[7].

GE SE-523 23-02c Revision 0 DRF 137-0010-7 4.2 IMPACT TEST RESULTS Eight Charpy V-Notch specimens each ofirradiated base, weld, and HAZ material were tested at temperatures (-80 F to 300 F) selected to defme the toughness transition and upp ponions of the fracture toughness curves. The absorbed energy, lateral expansion, and per shear data are listed for each materialin Table 4-2. Plots of absorbed energy data for base, weld and HAZ materials are presented in Figures 4-1,4-3, and 4-5, respectively. Lateral expansion plots for base, weld and HAZ materials are presented in Figures 4-2,4-4, and 4-6, respec The irradiated curves are plotted along with their corresponding unirradiated curve. The fracture surface photographs and a summary of the test results for each specimen are contained in Appendix A.

The Charpy data sets were fit with the hyperbolic tangent function developed by Old6 e for the EPRI 1rradiated Steel Handbook [9].

Y = A + B

• TANH [( T - To )/C],

where Y = impact energy or lateral expansion T = test temperature, and A, B, To and C are determined by non-linear regression The TMI function is one of the few continuous functions with a shape characteristic oflow alloy steel fracture toughness transition curves Typically the curve 6ts were generated by s both shelves free.

The TANH curve fits for the irradiated Charpy V-notch data were used to determine the values given in Table 4-3: 30 ft lb,50 f1-lb, and 35 MLE index temperatures, and the USE.

GE NE-52.b23 0294 Revision 0 DRF 137 0010-7 Table 4-1 VALLECITOS QUALIFICATION TEST RESULTS USING

, NIST STANDARD REFERENCE SI'ECISIENS Test Energy Acceptable Bath Temperature Absorbed Range Specimen

( F) (ft-lb) (ft-lb)

Identification Medium HH-40 321 Methanol -40 74.0 Vallecitos 74.5 llH-40 507 Methanol -40 Richte Machine 71.5 Hil-40 933 Methanol -40 (tested 2/17/93) -40 75 0 HH-401042 Methano!

HH-401198 Methanol -40 75 0 Average 74.0 74.9 2 3.7 pass Methanol -40 13.5 LL-39 087 LL-39195 Methanol -40 13.5 LL-39 793 Methanol -40 13.0 Methanol -40 13.5 LL-39 849 LL-391102 Methanol -40 13_5 Average 13.4 13.2 : 1.0 pass l

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L E. w .52.;.2.;-v; u Revision 0 DRF 137-0010-7 Table 4-2 IRRADIATED CII ARPY V-NOTCII IMPACT TEST RESULTS Test Fracture Lateral Percent Shear Temperature Energy Expansion (Method 1)

Specimen

( F) _(R-lk). (mils) (%)

identification

-40 9.0 8.5 2 Base: 2LB 10 2KB 10 22.5 22.0 Heat C4487-1 18.5 20.0 14 Longitudinal 2KU 30 50 37.0 32.5 24 2M1 60 67.5 54.0 30 2LA 47 100 78.5 58.0 2L6 100 2K6 200 141.5 93.0 146.5 85.0 100 2KY 300

-40 26.0 22.5 28 Weld: 2TL

-20 26.0 25.0 19 Heat S3986 Lot 3876 2UD 39 10 28.5 28.5 Run 934 2U3 42.5 38.0 33 2TE 30 60 66.5 53.5 59 2PP 100 73.5 60.0 66 2UL 100 200 95.0 82 5 2UA 100 300 99.5 84.0 2TP

-80 6.0 8.0 3 IIAZ: 32D 42

-40 35.5 30.0 31B 7

-20 10.0 13.5 2YD 28 l

10 17.5 18.0 321 30 48.5 44.0 51 325 61 60 78.0 65.0 32C 71 100 108.0 79.0 32K 100 200 97.5 77.0 32B

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GE-NE-523 23 029 t Revision 0 DRF 137-0010-7 Table 4-3 SIGNIFICANT RESULTS OF 1RRADIATED CilARPY V-NOTCil DATA l

Index Index Temperature Temperature Index Upper ShelP Temperature Energy

( F) ( F)

E=30 0-lb E=50 0-lb MLE=35 mils (ft-lM Material 60.0 46.9 148.6/96.6 PLATE: Heat C4487-1, 30.6 Longitudinal ~

43.7 20.5 97.5 WELD: Heat S3986 -4.4 i Lot 3876, Run 934 )

34.4 24.8 102.6 IIAZ: 18.8 4

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a USE values from Longitudinal / Transverse oriented Charpies; values are equal for weld metal.

Transverse plate USE is taken as 65% of the longitudinal USE, per USNRC MTED 5-2 [10]

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GE NE-53-23-02W

. Revision 0 DRF 137-0010 7 l

5. TENSILE TESTING j

Six round bar tensile specimens were recovered from the surveillance capsule. Uniaxial tensile tests were conducted in air at room temperature (70 F), and RPV operating ternperature (550 F). No extra specimens were available for testing at the onset to upper shelf energy. The t

tests were conducted in accordance with ASTM ES-89 [8]

i 5.1 PROCEDURE All tests were conducted using a screw-driven Instron test frame equipped with a 20-kip load cell and special pull bars and grips. Heating was done with a Satec resistance clamshell furnace centered around the specimen load train. The test temperature was monitored and controlled by a chromel-alumel thermocouple spot-welded to an inconel clip that was friction-clipped to the surface of the specimen at its midline. Before the elevated temperature tests, a profile of the furnace was conducted at the test temperature ofinterest using an unirradiated ste specimen of the same geometry. Thermocouples were spot-welded to the top, middle, and bottom of a central 1 inch gage of this specimen. In addition, the clip on thermocouple was attached to the midline of the specimen. When the target temperatures of the three thermocouples were within i5 F of each other, the temperature of the clip-on thermocouple was noted and subsequently used as the target temperature for the irradiated specimens.

All tests were conducted at a calibrated crosshead speed of 0.005 in/ min until well past yield, at which time the speed was increased to 0.05 inch / min until fracture. Crosshead displacement was used to monitor specimen extension during the test.

The test specimens were machined with a minimum diameter of 0.250 inch at the center of the gage length. The yield strength (YS) and ultimate tensile strength (UTS) were calculated

> by dividing the nominal area (0.04912 in )into the 0.2% offset load and into the maximum test load, respectively. The values listed for the uniform and total elongations were obtained from plots that recorded load versus specimen extension and are based on a 1.5 inch gage length.

Reduction of area (RA) values were detennined from post test measurements of the necked l

specimen diameters using a calibrated blade micrometer and employing the following formula:

RA = 100% * (Ao - Ar)/Ao After testing, each broken specimen was photographed end-on, showing the fracture surface, and GE NE-523 23 u2W Revision 0 DRF 137-0010 7 lengthwise, showing the fracture location and local necking behavior.

5.2 RESULTS Irradiated tensile test properties of Yield Strength (YS), Ultimate Tensile Strength (UTS), Reduction of Area (RA), Uniform Elongation (UE), and Total Elongation (TE) are presented in Table 5-1. As can be seen from the figures, the surveillance materials generally follow the trend of decreasing properties with increasing temperature. A stress-strain curve for a 550 F base metalirradiated specimen is shown in Figure 5-1. This curve is typical of the stress-strain characteristics of all the tested specimens. Photographs of the fracture surfaces and necking behavior are given in Figures 5-2 through 5-4.

Table 5-1: TENSILE TEST RESULTS FOR 1RRADIATED RPV MATERIALS Ultimate Uniform Total Reduction Test Yielda Specimen Temp. Strength Strength Elongation Elongation of Area (ksi) (%) (%) (%)

Number ( F) (ksi) __

90.9 10.6 20.4 71.2 Base: 333 RT 69.0 S5.6 S.7 17.3 62.6 33E 550 62.2 92.0 10 7 21.6 67.3 Weld: 34E RT 76.0 85.2 9.9 17.3 61.2 345 550 66.5 91.8 10.6 20.0 65.9 HAZ: 35C RT 70.1 86 3 8.0 15.7 64.0 353 550 65.5 a Yield Strength is determined by 0.2% offset.

I 9

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Figure 5 2. Fracture Location, Necking Behavior and Fracture Appearance for 1rradiated Base Metal Tensile Specimens

! Revismn o GL SE 523-23-0294 DRF 137 0010-7 f

U 34E RT

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! Figure 5-3. Fracture Location, Necking Behavior and Fracture Appearance

^

for Irradiated Weld Metal Tensile Specimens i

I l

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- - - , - - , , - - . - , , _ .,- l

Revision 0 GE NE-523 23 02%

DRF 137-0010 7 j

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} Figure 5-4. Fracture Location, Necking Behavior and Fracture Appearance for Irradiated HAZ Metal Tensile Specimens

GE NE 523 23 0294 Revision 0 DRF 137 0010 7

6. SPECIS1EN CIIE511 CAL C051 POSITION Samples were taken from the surveillance plate and weld tensile specimens after they were f

tested. Chemical analyses were performed using a Spectraspan til plasma emission spectrometer.

' Each : ample was dissolved in an acid solution to a concentration of 40 mg steel per mi solution.

The spectrometer was calibrated for determination of Mn, Ni, Mo and Cu by diluting National Institute of Standards and Technology (NIST) Spectrometric Standard Solutions. The phosphorus calibration involved analysis of four reference materials from NIST with known phosphorus levels. Analysis accuracies are 10.003% (absolute) of reponed value for phosphorus, 10% (relative) of reported value for silicon, and 5% (relative) of reported value for other elements. The chemical composition results are given in Table 6-1 for the surveillance plate and weld materials.

The results show good agreement with corresponding data from fabrication records in Table 3-1.

Table 6-1 CIIEMICAL COMPOSITION OF IRRADIATED SURVEILLANCE SPECIMENS Composition by Weicht Percent C Mn P S Si Ni Mo Cu Identification PLATII: 0.53 0.59 0.099 1.45 0.008 -- 0.26 Tensile 333 (RT) --

0.53 0.59 0.099 1.46 0.009 -- 0.27 Tensile 33E (550 F) --

0.23 1.50 0.010 0.015 0.27 0.56 0.57 0.12 C4487-la WELD:

1.55 0.017 -- 0.36 0.96 0.58 0.055 Tensile 34E (RT) --

0.98 0.59 0.051 1.44 0.015 -- 0.39 Tensile 345 (550 F) --

0.019 0.016 0.36 0.96 0.52 0.05 S3986 Lot 3876 Run 934a 0.080 1.42

! a Beltline specimen data from Table 3-1 has been added for comparison.

i

GE-NE.52.i 2.$-02W Revision 0 DRF 137 0010 7

7. FLl!X WIRE ANALYSIS Flux wires removed from the 300 capsule were analyzed, as described in Section 7.1.

7.1 Procedure The surveillance capsule contained 6 flux wires: 2 iron,2 copper and 2 nickel. Each wire was removed from the capsule, cleaned with dilute acid, weighed, mounted on a counting card, and analyzed for its radioactivity content by gamma spectrometry. Each iron wire was analyzed for Mn-54 content, each nickel wire for Co-58 and each copper wire for Co-60 at a calibrated 4-cm or 10-cm source-to-detector distance with 100-cc and 80-cc Ge(Li) detector systems. These measurements were taken in accordance with ASTM E263-88, E264-87, and E523-87.

7.2 Results The measured activity for the 300 surveillance capsule is given in Table 7-1. The ,

accuracies of the values in Tables 7-1 for a 2c deviation are estimated to be 15% for dps/g (disintegrations per second per gram) for copper and iron, and i7% for nickel Tnble 7-1 FLUX WIRE ACTIVITY RESULTS dps/g Element Wire (Element) (at end ofirradiation)

Copper 1.46x104 Copper 1.40x104 Iron 1.02x105 Iron 1.00x105 8 Nickel 1.61x106

,I Nickel 1.57x106 7

9 l

+ ,

Revision 0 Gb NE-52.4 23 0294 DRF 137-0010-7 8, REFERENCES

[1] " Fracture Toughness Requirements," Appendix G to Part 50 of Title 10 of the Code of Federal Regulations, July 1983.

[2] " Protection Against Non-Ductile Failure," Appendix G to Section XI of the 1992 ASME Boiler & Pressure Vessel Code

[3] " Reactor Vessel Material Surveillance Program Requirements," Appendix H to Part 50 of Title 10 of tbc Code of Federal Regulations May 1983.

[4] Dele!cd.

4

[5] Deleted.

[6] " Conducting Surveillance Tests for Light Water Cooled Nuclear Power Reactor Vessels," Annual Book of ASTM Standards, E185-S2, July 1982

[7] " Standard Methods for Notched Bar impact Testing of Metallic Materials " Annual Book of ASTM Standards, E23-88

[8] " Standard Methods ofTension Testing of Metallic Materials." Annual Book of ASTM Standards, ES-89.

[9] " Nuclear Plant Irradiated Steel Handbook," EPRI Report NP-4797, September 1986.

[10] " Fracture Toughness Requirements," USNRC Branch Technical Position MTEB 5-2, Revision 1, July 19S1.

l 1

l GE .NL 523 2.i-u244 Revision 0 l DRF B7-0010-7 APPENDIX A l CIIARPY SPECIMEN FRACTURE SURFACE PilOTOGRAPilS 1

l Photographs of each Charpy specimen fracture surface were taken per the requirements of ASTM E185-82. The following pages show the fracture surface photographs along with a summary of the Charpy test results for each irradiated specimen. The pictures are arranged in the order of base, weld, and HAZ materials.

1 1

I l

i i

l 1

4 1

Revi.sion 0 GE-NE 523 23 0294 l DRF 137-0010-7

,y ~2.L L, Mu BASE: 2KY 4  ! 1,. q BASE: 2L6 Temp: 300 F ,7 5 (M i.i@' Temp: 100 *F Energy: 146.5 n-lb 'T Energy: 78.5 n lb

.e

($@8 MLE: 850 mils ".  ;~ " h.

MLE: 58.0 mils Shear: 100 % - .- s Shear: 47 %

B ASE: 2K6 . .. i. -w BASE: 2LA

'2h

~

Temp: 200 "F  ; Temp: 60 F l f

Energy: 141.5 n-lb f Energy: 67.5 R-Ib

{ hfLE: 54.0 mils MLE: 93.0 mils -

T; p' ' "

Shear: 100 % -

Shear: 30 %

g g-6 2LA -

7_M i 2.K6 Mut BASE: 2KB B ASE: 2M1 g.7

~~~ '

~' ] -

Temp: 10 F Temp: 50.F Energy: 37.0 R-lb

{ {-l Energy: 22.5 R-lb

, (,? l

• MLE: 22.0 mils MLE: 32.5 mits .: .

Shear: 24 % ,

-- ]- Shear: 10 %

B ASE: 2KU -

. . . l.. _ '

• BASE: 2LB l

30 F Temp: -40 F Temp: y;g Tf#O21 Energy: 18.5 n-lb j;QF hhf, -

Energy: 9.0 ft-lb l MLE: 20.0 mils '/ MLE: 8.5 mils l

' p;;-

. 4 Ssea,: 14 % .qg S8 ear: 2%

L i

Revi.sion 0 GL-NE 5:3 23 0244 DRF 137 0010 7 l

i 1TP 2dL f>A I

s .-

WELD: 2TP 1 WELD: 2UL Temp: 300 F

• Temp; 100'F Energy: 99.5 R-Ib 4 *3 Energy. 73.5 6-lb l hiLE: 84.0 mils MLE: 60.0 mils

- ~

Shear: 100 % e Shear: 66 %

l WELD: 2UA -

WELD: 2PP Temp: 200 F }, .. , Temp: 60 F l Energy: 95.0 R-Ib l5T <r ,.j$, I) '

Energy: 66.5 R-lb a

MLE: 82.5 mils . "" ; ?

• l MLE: 53.5 mils Shear: 100 % ,

Shear: 59 %

2uA tPP 1T6 TdD YW O'

WELD: 2TE ,),; WELD: 2UD l Temp: 30 F '/ l' -

Temp: -20 F Energy: 42.5 ft-lb i Energy: 26.0 R-lb MLE: 38.0 mils h ~

f4 MLE: 25.0 mits Shear: 33 %

77 Qg -.g.4 Shear: 19 %

l WELD: 2U3 +4h ..M,, WELD: 2TL Temp: 10 F j Temp: -40 F Energy: 28.5 R-lb Energy; 26.0 n-lb

l. .

ip MLE: 28.5 mils MLE: 22.5 mils Shear: 39 % '

l Shear: 28 %

1 ML a

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Res i.wn O GE NE 52.4 2.i.0294 DRF 137 0010-7 l l

'92. G. N St.@

HAZ: 32B - , HAZ: 32C

' ^ * [,], ,' '\, Temp: 60*F Temp: 200#F . .c. ,

Energy: 97.5 R-lb , ,, jJr .

.g. ,7 ,. , .

Energy: 78 0 0-lb h1LE- 77.0 mils YV.7" c l,p ., $,, ;? 5'. hiLE- 65.0 mils 6" -

61 %

Shear:

Shear: 100 % ,.

HAZ: 32K -

- HAZ: 325 Temp. 100 F ,

Temp: 30 F Energy: 108 0 ft-lb  :]Si' i Energy: 48.5 0 Ib

'{ '

I hiLE: 79.0 mils ll

• f jl; J hiLE: 44.0 mils Shear: 71 %

l .

Shear: 51 %

32. V, SLC .

3\6 ($l g(

HAZ: 321 HAZ: 31B 4

Temp: 10.F Temp: -40 F Energy: 17.5 R-lb fj .

Energy: 35.5 R-lb htLE: 18.0 mils '.8 . :e "' g,._ h1LE: 30.0 mils Shear: 28 % '

. ec.u. deg 6 T Shear: 42 %

HAZ: 2YD _._l.......- .. HAZ: 32D

-20 F + Temp: -80 *F Temp: ..

g -

3 Energy: 10.0 n-lb Energy: 6.0 0-lb

hfLE

13.5 mils p :. ,, J m:.g. g

- h1LE: 8.0 mils y

Shear: 7% i _ lGd .Ny ~

Shear: 3%

.p 4

t a

,- -- -1 er -e-tr ,