ML050840329

Enclosure 2, WCAP-16382-NP, Rev. 0, Analysis of Capsule W from the Southern Nuclear Operating Company, Vogtle Unit 2 Reactor Vessel Radiation Surveillance Program.

ML050840329
Person / Time
Site:	Vogtle
Issue date:	01/31/2005
From:	Burton C, Ghergurovich J, Hagler R, Laubham T Westinghouse
To:	Office of Nuclear Reactor Regulation
References
WCAP-16382-NP, Rev 0
Download: ML050840329 (257)

Text

Enclosure 2 Vogtle Electric Generating Plant WCAP-16382-NP, Rev. 0

Westinghouse Non-Proprietary Class 3 WCAP-16382-NP January 2005 Revision 0 Analysis of Capsule W from the Southern Nuclear Operating Company, Vogtle Unit 2 Reactor Vessel Radiation Surveillance Program Westinghouse

WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-16382-NP, Revision 0 Analysis of Capsule W from the Southern Nuclear Operating Company, Vogtle Unit 2 Reactor Vessel Radiation Surveillance Program I

T. J. Laubham R.J. Hagler January 2005 Approved: (;)

Ghergurovi , Manager Reactor Component Design & Analysis Westinghouse Electric Company LLC Energy Systems P.O. Box 355 Pittsburgh, PA 15230-0355 02005 Westinghouse Electric Company LLC All Rights Reserved

WCAP- I 6382 *iii PREFACE This report has been technically reviewed and verified by:

Reviewer: C.M. Burton & (l

WCAP-16382 iv TABLE OF CONTENTS PREFACE .................... iii LIST OF TABLES ................... v LIST OF FIGURES ................... vii EXECUTIVE

SUMMARY

................... ix I

SUMMARY

OF RESULTS .1-1 2 INTRODUCTION .2-1 3 BACKGROUND .3-1 4 DESCRIPTION OF PROGRAM .4-1 5 TESTING OF SPECIMENS FROM CAPSULE W .. 5-5.1 OVERVIEW .5-1 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS .5-3 5.3 TENSILE TEST RESULTS .5-4 5.4 1/2T COMPACT TENSION SPECIMEN TESTS .5-5 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY . .6-1

6.1 INTRODUCTION

.6-1 6.2 DISCRETE ORDINATES ANALYSIS .6-2 6.3 NEUTRON DOSIMETRY .64 6.4 CALCULATIONAL UNCERTAINTIES .6-5 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE .7-1 8 REFERENCES .8-1 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS .A-0 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS .B-0 APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING HYPERBOLIC TANGENT CURVE-FITTING METHOD .C-0 APPENDIX D VOGTLE UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION . D-0

WCAP-16382 v LIST OF TABLES Table 4-1 Chemical Composition (wt %) of the Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 ........................................................ 4-3 Table 4-2 Chemical Composition (wt %) of the Unirradiated Vogtle Unit 2 Reactor Vessel Beltline Region Weld Materials .4-4 Table 4-3 Heat Treatment of the Vogtle Unit 2 Reactor Vessel Surveillance Material .4-5 Table 5-1 Charpy V-Notch Data for the Vogtle Unit 2 Lower Shell Plate B8628-1 Irradiated to a Fluence of 2.98 x 1019 n/cm2 (E > 1.0 MeV)

(Longitudinal Orientation)................. 5-6 Table 5-2 Charpy V-notch Data for the Vogtle Unit 2 Lower Shell Plate B8628-1 Irradiated to a Fluence of 2.98 x 1019 n/cm 2 (E> 1.0 MeV)

(Transverse Orientation)................ 5-7 Table 5-3 Charpy V-notch Data for the Vogtle Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 2.98 x 1019 n/cm2 (E > 1.0 MeV) ........................................ 5-8 Table 5-4 Charpy V-notch Data for the Vogtle Unit 2 Heat Affected Zone Material Irradiated to a Fluence of 2.98 x 109 n/cm2 (E > 1.0 MeV) ............................. 5-9 Table 5-5 Instrumented Charpy Impact Test Results for the Vogtle Unit 2 Lower Shell Plate B8628-1 Irradiated to a Fluence of 2.98 x 1019 n/cm 2 (E > 1.0 MeV)

(Longitudinal Orientation)................. 5-10 Table 5-6 Instrumented Charpy Impact Test Results for the Vogtle Unit 2 Lower Shell Plate B8628-1 Irradiated to a Fluence of 2.98 x 1019 n/cm 2 (E > 1.0 MeV)

(Transverse Orientation)................ 5-11 Table 5-7 Instrumented Charpy Impact Test Results for the Vogtle Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 2.98 x 10' 9 n/cm2 (E > 1.OMeV) ....................... 5-12 Table 5-8 Instrumented Charpy Impact Test Results for the Vogtle Unit 2 Heat-Affected-Zone (HAZ) Metal Irradiated to a Fluence of 2.98 x I019 n/cm 2 (E > I.OMeV) ..................... 5-13 Table 5-9 Effect of Irradiation to 2.98 x 10'9 n/cm 2 (E > 1.0 MeV) on the Notch Toughness Properties of the Vogtle Unit 2 Reactor Vessel Surveillance Materials ...... 5-14 Table 5-10 Comparison of the Vogtle Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions .................. 5-15

WCAP-16382 vi vi WCAP-16382 LIST OF TABLES (Cont.)

Table 5-11 Tensile Properties of the Vogtle Unit 2 Reactor Vessel Surveillance Materials Irradiated to 2.98 x IO"1 n/cm2 (E > 1.0MeV) .................................................. 5-16 Table 6-1 Calculated Fast Neutron Exposure Rates and Integrated Exposures at the Surveillance Capsule Center .................. 6-11 Table 6-2 Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface ........................................ 6-15 Table 6-3 Relative Radial Distribution of Neutron Fluence (E > 1.0 MeV) Within the Reactor Vessel Wall ...... 6-19 Table 6-4 Relative Radial Distribution of Iron Atom Displacements (dpa) Within the Reactor Vessel Wall ............ 6-19 Table 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Alvin W. Vogtle Unit 2.6-20 Table 6-6 Calculated Surveillance Capsule Lead Factors .6-20 Table 7-1 Vogtle Unit 2 Reactor Vessel Surveillance Capsule Withdrawal Schedule .7-1

WCAP-16382 vii "ii WCAP-16382 LIST OF FIGURES Figure 4-1 Arrangement of Surveillance Capsules in the Vogtle Unit 2 Reactor Vessel .................. 4-6 Figure 4-2 Capsule W Diagram Showing the Location of Specimens, Thermal Monitors, and Dosimeters .4-7 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Longitudinal Orientation). 5-17 1

Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Longitudinal Orientation). 5-18 Figure 5-3 Charpy V-Notch Percent Shear vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Longitudinal Orientation). 5-19 Figure 54 Charpy V-Notch Impact Energy vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transverse Orientation). 5-20 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transverse Orientation).5-21 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transverse Orientation). 5-22 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Vogtle Unit 2 Reactor Vessel Weld Metal . 5-23 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Vogtle Unit 2 Reactor Vessel Weld Metal . 5-24 Figure 5-9 Charpy V-Notch Percent Shear vs. Temperature for Vogtle Unit 2 Reactor Vessel Weld Metal . 5-25 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Vogtle Unit 2 Reactor Vessel Heat-Affected-Zone Material . 5-26 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Vogtle Unit 2 Reactor Vessel Heat-Affected-Zone Material . 5-27 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Vogtle Unit 2 Reactor Vessel Heat-Affected-Zone Material . 5-28

WCAP-16382 Viii LIST OF FIGURES (Cont.)

Figure 5-13 Charpy Impact Specimen Fracture Surfaces for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Longitudinal Orientation).................................... 5-29 Figure 5-14 Charpy Impact Specimen Fracture Surfaces for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transverse Orientation)........................................5-30 Figure 5-15 Charpy Impact Specimen Fracture Surfaces for Vogtle Unit 2 Reactor Vessel Weld Metal .................................................. 5-31 Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Vogtle Unit 2 Reactor Vessel Heat-Affected-Zone Metal .................................................. 5-32 Figure 5-17 Tensile Properties for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Longitudinal Orientation) .................................................. 5-33 Figure 5-18 Tensile Properties for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transverse Orientation) .................................................. 5-34 Figure 5-19 Tensile Properties for Vogtle Unit 2 Reactor Vessel Weld Metal .................................. 5-35 Figure 5-20 Fractured Tensile Specimens from Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (LongitudinalOrientation)................................................ 5-36 Figure 5-21 Fractured Tensile Specimens from Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transverse Orientation).................................................. 5-37 Figure 5-22 Fractured Tensile Specimens from Vogtle Unit 2 Reactor Vessel Weld Metal .................................................. 5-38 Figure 5-23 Engineering Stress-Strain Curves for Lower Shell Plate B8628-1 Tensile Specimens BL7, BL8 and BL9 (Longitudinal Orientation).......................................... 5-39 Figure 5-24 Engineering Stress-Strain Curves for Lower Shell Plate B8628-1 Tensile Specimen BT7, BT8 and BT9 (Transverse Orientation)............................................... 540 Figure 5-25 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens BW7, BW8 and BW9 .................................................. 541 Figure 6-1 Alvin W.Vogtle Unit 2 r,0 Reactor Geometry .................................................. 6-7 Figure 6-2 Alvin W. Vogtle Unit 2 rz Reactor Geometry with Neutron Pad .................................. 6-10

WCAP-1 6382 ix EXECUTIVE

SUMMARY

The purpose of this report is to document the results of the testing of surveillance Capsule W from Vogtle Unit 2. Capsule W was removed at 13.29 EFPY and post irradiation mechanical tests of the Charpy V-notch and tensile specimens were performed. A fluence evaluation utilizing the recently released neutron transport and dosimetry cross-section libraries was derived from the ENDF/B-VI data-base. Capsule W received a fluence of 2.98 x 10' 9 n/cm2 (E > 1.0 MeV) after irradiation to 13.29 EFPY. The peak clad/base metal interface vessel fluence after 13.29 EFPY of plant operation was 7.20 x 1018 n/cm 2 (E >

1.0 MeV).

.4.

This evaluation lead to the following conclusions: 1) The measured 30 ft-lb transition temperature shift value for the lower shell plate B8628-1 (longitudinalorientation) is less than the Regulatory Guide 1.99, Revision 2, prediction.. 2) The measured 30 ft-lb transition temperature shift value for the lower shell plate B8628-1 (transverseorientation) is greater than the Regulatory Guide 1.99, Revision 2, prediction.

However, the shift value is less than the two sigma allowance by the Regulatory Guide 1.99, Revision 2, when calculating adjusted reference temperatures. 3) The measured 30 ft-lb transition temperature shift value for the surveillance weld metal is less than the Regulatory Guide 1.99, Revision 2, prediction.

4) The measured percent decrease in upper shelf energy for all the surveillance materials of Capsules W contained in the Vogtle Unit 2 surveillance program are less than the Regulatory Guide 1.99, Revision 2 predictions. 5) All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the current license (36 EFPY) and a potential license renewal date of 54 EFPY as required by I OCFR50, Appendix G I']. 6) The Vogtle Unit 2 surveillance plate and weld data is credible. This evaluation can be found in Appendix D. 7) The PT Curves from WCAP-15161, Revision 3 are still acceptable for 26 EFPY and 36 EFPY.

Lastly, a brief summary of the Charpy V-notch testing can be found in Section 1. All Charpy V-notch data was plotted using a symmetric hyperbolic tangent curve fitting program.

WCAP-16382 1 -I I

SUMMARY

OF RESULTS The analysis of the reactor vessel materials contained in surveillance capsule W, the fourth capsule to be removed from the Vogtle Electric Generating Plant Unit 2 reactor pressure vessel, led to the following conclusions:

• The Capsule W results presented in this report were generated using CVGRAPH, Version 5.0.2, which is a hyperbolic tangent curve-fitting program. Appendix C presents the Capsule W CVGRAPH, Version 5.0.2, Charpy V-notch plots and the program input data.

• Capsule W received an average fast neutron fluence (E> 1.0 MeV) of 2.98 x 1019 n/cm2 after 13.29 effective full power years (EFPY) of plant operation.

• Irradiation of the reactor vessel lower shell plate B8628-1 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major rolling direction (Longitudinal orientation),to 2.98 x 109 n/cm 2 (E> I.OMeV) resulted in a 30 ft-lb transition temperature increase of 39IF and a 50 fl-lb transition temperature increase of 43.6 0 F. This results in an irradiated 30 ft-lb transition temperature of 47.81F and an irradiated 50 ft-lb transition temperature of 89.00 F for the Longitudinal oriented specimens.

• Irradiation of the reactor vessel lower shell plate B8628-1 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major rolling direction of the plate (Transverse orientation),to 2.98 x 1019 n/cm2 (E> 1.0 MeV) resulted in a 30 ft-lb transition temperature increase of 45.51F and a 50 fl-lb transition temperature increase of 63.10 F. This results in an irradiated 30 ft-lb transition temperature of 74.1 IF and an irradiated 50 fi-lb transition temperature of 133.2 0 F for Transverse oriented specimens.

• Irradiation of the weld metal Charpy specimens to 2.98 x 1019 n/cm 2 (E> I.OMeV) resulted in a 30 fl-lb transition temperature increase of 31.40 F and a 50 ft-lb transition temperature increase of 47.90 F. This results in an irradiated 30 fl-lb transition temperature of 12.20 F and an irradiated 50 ft-lb transition temperature of 59.0°F.

• Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens to 2.98 x 10'9 n/cm 2 (E> 1.0 MeV) resulted in a 30 ft-lb transition temperature increase of 3.2°F and a 50 ft-lb transition temperature decrease of 4.6°F. This results in an irradiated 30 ft-lb transition temperature of-80.5°F and an irradiated 50 ft-lb transition temperature of-57 0F.

• The average upper shelf energy of the lower shell plate B8628-1 (Longitudinalorientation) resulted in an average energy decrease of 5 ft-lb after irradiation to 2.98 x 1019 n/cm 2 (E> 1.0 MeV). This results in an irradiated average upper shelf energy of 84 fl-lb for the Longitudinal oriented specimens.

Summary of Results

WCAP-16382 1I 1-2 WCAP-1 6382

• The average upper shelf energy of the lower shell plate B8628-1 (Transverse orientation) resulted in an average energy decrease of I ft-lb after irradiation to 2.98 x 1019 n/cm 2 (E> 1.0 MeV). Hence, this results in an irradiated average upper shelf energy of 69 ft-lb for the Transverse oriented specimens.

• The average upper shelf energy of the weld metal Charpy specimens resulted an average energy decrease of 5 ft-lb after irradiation to 2.98 x 1019 n/cm 2 (E> 1.0 MeV). Hence, this results in an irradiated average upper shelf energy of 87 ft-lb for the weld metal specimens.

• The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 6 ft-lb after irradiation to 2.98 x 1019 n/cm 2 (E> I.OMeV). This results in an irradiated average upper shelf energy of 100 ft-lb for the weld HAZ metal.

• A comparison of the Vogtle Electric Generating Plant Unit 2 reactor vessel beltline material test results with the Regulatory Guide 1.99, Revision 211] predictions led to the following conclusions:

- The measured 30 ft-lb transition temperature shift value for the lower shell plate B8628-1 (Longitudinal orientation)is less than the Regulatory Guide 1.99, Revision 2, prediction.

- The measured 30 ft-lb transition temperature shift value for the lower shell plate B8628-1 (Transverse orientation) is greater than the Regulatory Guide 1.99, Revision 2, prediction.

However, the shift value is less than the two sigma allowance by the Regulatory Guide 1.99, Revision 2, when calculating adjusted reference temperatures.

- The measured 30 ft-lb transition temperature shift value for the surveillance weld metal is less than the Regulatory Guide 1.99, Revision 2, prediction.

- The measured percent decrease in upper shelf energy for all the surveillance materials for Capsule "W" is less than the Regulatory Guide 1.99, Revision 2, predictions.

• The credibility evaluation of the Vogtle Electric Generating Plant Unit 2 surveillance program presented in Appendix D of this report indicates that the surveillance results are credible.

• All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the end of the current license (36 EFPY) and a potential license renewal (54 EFPY) as required by 10CFRSO, Appendix G '2k Summary of Results

WCAP-16382 11-3

-3 WCAP-16382

• The calculated and best estimate end-of-license (36 EFPY) and 54 EFPY neutron fluence neutron fluence (E> 1.0 MeV) at the core midplane for the Vogtle Electric Generating Plant Unit 2 reactor vessel using the Regulatory Guide 1.99, Revision 2 attenuation formula (ie. Equation # 3) is as follows:

Calculated (36 EFPY): Vessel inner radius* = 1.91 x 1019 n/cm2 Vessel 1/4 thickness = 1.14 x 1019 n/cm 2 Vessel 3/4 thickness = 4.04 x I018 n/cm 2 Calculated (54 EFPY): Vessel inner radius* = 2.86 x 1019 n/cm 2 Vessel 1/4 thickness = 1.70 x 0'9n/cm 2 Vessel 3/4 thickness = 6.06 x lO'8 n/cm 2 Summary of Results

WCAP-1 6382 2-1 VCAP-I 6382 2-I 2 INTRODUCTION This report presents the results of the examination of Capsule W, the fourth capsule removed from the reactor in the continuing surveillance program which monitors the effects of neutron irradiation on Southern Nuclear Vogtle Electric Generating Plant Unit 2 reactor pressure vessel materials under actual operating conditions.

The surveillance program for Southern Nuclear Vogtle Electric Generating Plant Unit 2 reactor pressure vessel materials was designed and recommended by the Westinghouse Electric Company. A description of the surveillance program and the pre-irradiation mechanical properties of the reactor vessel materials is presented in WCAP-11381, "Georgia Power Company Alvin W. Vogtle Unit No. 2 Reactor Vessel Radiation Surveillance Program[ 31. The surveillance program was planned to cover the 40-year design life of the reactor pressure vessel and was based on ASTM El 85-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Reactor Vessels"E8 1. Capsule W was removed from the reactor after 13.29 EFPY of exposure and shipped to the Westinghouse Science and Technology Center Hot Cell Facility, where the post-irradiation mechanical testing of the Charpy V-notch impact and tensile surveillance specimens was performed.

This report summarizes the testing of and the post-irradiation data obtained from surveillance capsule W removed from the Southern Nuclear Vogtle Electric Generating Plant Unit 2 reactor vessel and discusses the analysis of the data.

Introduction

WCAP-16382 3-1 3 BACKGROUND The ability of the large steel pressure vessel containing the reactor core and its primary coolant to resist fracture constitutes an important factor in ensuring safety in the nuclear industry. The beltline region of the reactor pressure vessel is the most critical region of the vessel because it is subjected to significant fast neutron bombardment. The overall effects of fast neutron irradiation on the mechanical properties of low alloy, ferritic pressure vessel steels such as A533 Grade B Class I (base material of the Vogtle Electric Generating Plant Unit 2 reactor pressure vessel beltline) are well documented in the literature.

Generally, low alloy ferritic materials show an increase in hardness and tensile properties and a decrease in ductility and toughness during high-energy irradiation.

A method for ensuring the integrity of reactor pressure vessels has been presented in "Fracture Toughness Criteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler and Pressure Vessel Codets. The method uses fracture mechanics concepts and is based on the reference nil-ductility transition temperature (RTNDT).

RTNDT is defined as the greater of either the drop weight nil-ductility transition temperature (NDTT per ASTM E-208[ 21") or the temperature 607F less than the 50 ft-lb (and 35-mil lateral expansion) temperature as determined from Charpy specimens oriented perpendicular (transverse) to the major working direction of the plate. The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (K1 , curve) which appears in Appendix G to the ASME Code[']. The K1, curve is a lower bound of static fracture toughness results obtained from several heats of pressure vessel steel. When a given material is indexed to the K1, curve, allowable stress intensity factors can be obtained for this material as a function of temperature. Allowable operating limits can then be determined using these allowable stress intensity factors.

RTNDT and, in turn, the operating limits of nuclear power plants can be adjusted to account for the effects of radiation on the reactor vessel material properties. The changes in mechanical properties of a given reactor pressure vessel steel, due to irradiation, can be monitored by a reactor vessel surveillance program, such as the Vogtle Unit 2 reactor vessel radiation surveillance program , in which a surveillance capsule is periodically removed from the operating nuclear reactor and the encapsulated specimens tested. The increase in the average Charpy V-notch 30 ft-lb temperature (ARTNDT) due to irradiation is added to the initial RTNDT, along with a margin (M) to cover uncertainties, to adjust the RTNDT (ART) for radiation embrittlement. This ART (RTNDT initial + M + ARTNDT) is used to index the material to the K1 , curve and, in turn, to set operating limits for the nuclear power plant that take into account the effects of irradiation on the reactor vessel materials.

Background

WCAP-16382 4-1 WCAP-16382 4-1 4 DESCRIPTION OF PROGRAM Six surveillance capsules for monitoring the effects of neutron exposure on the Vogtle Unit 2 reactor pressure vessel core region (beltline) materials were inserted in the reactor vessel prior to initial plant start-up. The six capsules were positioned in the reactor vessel between the neutron pads and the vessel wall as shown in Figure 4-1. The vertical center of the capsules is opposite the vertical center of the core. The capsules contain specimens made from lower shell plate B8628-1 (Heat No. C3500-2), weld metal fabricated with 3/1 6-inch Mil B4 weld filler wire, heat number 87005 Linde 124 flux, lot number 1061, which is identical to that used in the actual fabrication of the intermediate to lower shell girth weld.

Capsule W was removed after 13.29 effective full power years (EFPY) of plant operation. This capsule contained Charpy V-notch, tensile, and 1/2T-CT fracture mechanics specimens made from lower shell plate B8628-1 and submerged arc weld metal identical to the closing girth seams. In addition, this capsule contained Charpy V-notch specimens from the weld Heat-Affected-Zone (HAZ) of lower shell plate B8628-1.

Test material obtained from lower shell plate (after the thermal heat treatment and forming of the plate) was taken at least one plate thickness from the quenched ends of the plate. All test specimens were machined from the 1/4 and 3/4 thickness locations of the plate after performing a simulated post-weld stress-relieving treatment on the test material. Specimens from weld metal and heat-affected-zone metal were machined from a stress-relieved weldment joining lower shell plate B8628-1 and adjacent lower shell plate B8825-1. All heat-affected-zone specimens were obtained from the weld heat-affected-zone of lower shell plate B8628-1.

Charpy V-notch impact specimens from lower shell plate B8628-1 were machined both in the longitudinal orientation (longitudinal axis of the specimen parallel to the major rolling direction) and transverse orientation (longitudinal axis of the specimen perpendicular to the major rolling direction).

The core region weld Charpy impact specimens were machined from the weldment such that the long dimension of each Charpy specimen was perpendicular to the weld direction. The notch of the weld metal Charpy specimens were machined such that the direction of crack propagation in the specimen was in the welding direction.

Tensile specimens from lower shell plate B8628-1 were machined in both the longitudinal and transverse orientation. Tensile specimens from the weld metal were oriented with the long dimension of the specimen perpendicular to the weld direction.

Compact tension test specimens from plate B8628-1 were machined in both the longitudinal and transverse orientations. Compact tension test specimens from the weld metal were machined perpendicular to the weld direction with the notch oriented in the direction of the weld. All specimens were fatigue pre-cracked according to ASTM E399.

The chemical composition and heat treatment of the surveillance material is presented in Tables 4-1 through 4-3. The chemical analysis reported in Table 4-1 was obtained from unirradiated material used in the surveillance program[ 31 and irradiated material from capsules U14 ] and yl51 .

Description of Program

WCAP-I 6382 4-2 Capsule W contained dosimeter wires of pure copper, iron, nickel, and aluminum 0.15 weight percent cobalt (cadmium-shielded and unshielded). In addition, cadmium shielded dosimeters of neptunium (Np2 3 7 ) and uranium (U238) were placed in the capsule to measure the integrated flux at specific neutron energy levels The capsule contained thermal monitors made from two low-melting-point eutectic alloys and sealed in Pyrex tubes. These thermal monitors were used to define the maximum temperature attained by the test specimens during irradiation. The composition of the two eutectic alloys and their melting points are as follows:

2.5% Ag, 97.5% Pb Melting Point: 5791F (3041C) 1.5% Ag, 1.0% Sn, 97.5% Pb Melting Point: 590'F (3100 C)

The arrangement of the various mechanical specimens, dosimeters and thermal monitors contained in Capsule W is shown in Figure 4-2.

Description of Program

WCAP-16382 4-3 Table 4-1 Chemical Composition (wt%) of the Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1(')

Element CE Analysis Westinghouse Capsule Y(')

l Analysis Analysis (BI-62)

C 0.24 0.23 0.233 Mn 1.34 1.30 1.168 P 0.007 0.007 0.008 S 0.016 0.014 0.009 Si 0.25 0.23 0.185 Ni 0.59 0.59 0.549 Mo 0.59 0.50 0.51 Cr 0.02 0.07 0.064 Cu 0.05 0.05 0.049 Al 0.029 0.034 0.032 Co 0.004 0.008 0.008 Pb not detected <0.07 W <0.01 <0.05 --

Ti <0.01 0.005 <0.002 Zr <0.001 <0.03 <0.01 V 0.004 <0.005 <0.004 Sn 0.017 0.007 <0.01 As 0.007 0.008 <0.02 Cb <0.01 <0.05 N2 0.008 0.007 B <0.001 0.008 0.009 Notes:

a. Reprinted from Tables 4-2 and 4-4 of WCAP-14532.

Description of Program

WCAP-16382 4-4 Table 4-2(') Chemical Composition (wt%) of the Unirradiated Vogtle Unit 2 Reactor Vessel Beltline Region Weld Materials Element. Inter. & Lower Circ. Weld(') Circ Weld(d) Capsule Y Capsule Y Capsule Y Shell Long. (CE Analysis) (Westinghouse Analysis Analysis Analysis Welds(b) Analysis) (BW-61) (BW-63) (BW-72)

C 0.15 0.075 0.099 0.084 0.089 0.097 Mn 1.34 1.27 1.25 1.046 0.983 1.110 P 0.007 0.007 0.008 0.010 0.008 0.011 S 0.011 0.010 0.013 0.006 0.006 0.008 Si 0.13 0.50 0.43 0.448 0.447 0.429 Ni 0.13 0.12 0.17 0.127 0.118 0.137 Mo 0.55 0.52 0.47 0.47 0.44 0.48 Cr - 0.07 0.061 0.056 0.052 0.056 Cu 0.07 0.006 0.040 0.039 0.037 0.040 Al _ 0.015 <0.02 <0.02 <0.02 Co _ 0.002 0.008 0.008 0.009 Pb _ <0.01 -- - -

W _ _ <0.01 -- -- -

Ti _ <0.001 <0.002 <0.002 <0.002 Zr -- - <0.01 <0.01 <0.01 <0.01 V 0.005 0.004 <0.004 <0.004 <0.004 <0.004 Sn -- - <0.001 <0.01 <0.01 <0.01 As 0.003 <0.02 <0.02 <0.02 Cb _ <0.002 -- - -

l N 0.002 -- _-- --

B _ 0.009 0.009 0.008 0.008 Notes:

(a) Reprinted from Tables 4-3 and 4-4 of WCAP-1 4532. Note: the NIST Standards are Not reprinted herein.

(b) Weld Wire Heat # 87005, Linde 0091 Flux, Lot # 0145.

(c) Weld Wire Heat # 87005, Linde 124 Flux, Lot # 1061.

(d) Westinghouse Analysis of surveillance program test plate "D", identical to the inter. to lower shell circ. weld.

Description of Program

WCAP-16382 4-5 4-5 WCAP-I 6382 Table 4-3 Heat Treatment of the Vogtle Unit 2 Reactor Vessel Surveillance Materiall'I Material Temperature ( 0F) Time (hrs.) Coolant Intermediate Shell Plates Austenitizing: 4 Water-quenched R4-1, R4-2 and R4-3 1600 +/- 25 (87 10C)

Tempered: 1225 +/- 25 4 Air Cooled (6630 C)

Stress Relief:(b) 16.5(b) Furnace Cooled 1150+/- 50 (621 0 C)

Lower Shell Plates Austenitizing: 4 Water-quenched B8825-1, R8-1 and B8628-1 1600 +/-25 (8710 C)

Tempered: 1225 +/- 25 4 Air Cooled (663°C)

Stress Relief: l2.0(b) Furnace Cooled 1150+/- 50 (621 0 C)

Intermediate Shell Longitudinal Stress Relief: 16.5(b) Furnace Cooled Seam Welds 1150+/- 50 (621 0C)

Lower Shell Longitudinal Seam 12.0 b) Furnace Cooled Welds Intermediate Shell to Lower Shell Local Stress Relief: 5.0 Furnace Cooled Girth Weld 1150+/- 50 (6210 C)

Surveillance Program Weldment Post Weld Stress Relief: 6.0(') Furnace Cooled Test Plate "D" (Representative of 1150 +/- 50 (621 0C)

Closing Girth Seam)

(a) This Table wvas reprinted from Table 4-1 of WCAP-14532 and originally documented in WCAP-1 13811'3 k (b) Stress Relief includes the intermediate to lower shell closing girth seam post-weld heat treatment (c) The stress relief heat treatment received by the surveillance test plate and weldment has been simulated.

Description of Program

II-WCAP-16382 4-6 0o (301.5') Z PSULE U (58.5-)

V (aO )

270 - - s0' (241 ') y 1238.5') x W (121.5*)

REACTOR VESSEL 180t PLN VIEW VESSEL

' WALL ASSEMSMY

-RCORE

-MOPLANE

-NEU`i PAD

-CORE BA ELEVATON VIEW Figure 4-1 Arrangement of Surveillance Capsules in the Vogtle Unit 2 Reactor Vessel Description of Program

WCAP-16382 4-7 WCAP-16382 4-7 LEGEND: B3L - LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

BT - LOWER SHELL PLATE B8628-1 (TRANSVERSE) CU I,II Al-.lsCo BW - WELD METAL 1311 - HEAT-AFFECTED-ZONE MATERIAL S79- i if " -Al..151C@ (Cd)

MmTR 1:II N W Spacer Tensile Compact Compact Charpy Charpy Charpy Compact Block ,

BW9 _ BW45 45 w42 lBH42 [W39 111139 nws BW12 BWII BWIBW9 BW44 71144 4 1141 BH38 BL12 BLII BW7 _ J IJ BW43 B1143l BW40 lB140 BW3 _B37 TOP OF VESSEL < CENTER Npzr U23M Compact Charpy Charpy Charpy Charpy 7 BW36 I 11136 BW33 lB1133 BT45 l L4 42 13L1O BL9 BW35 BH35 llBW3 lB4 lB4I BT41 O V SL BW34 H34\ BH31 I.

CENTER -_\ -B IOTTOM OF VESSEL Cu Al-..ISo Cv-...F ro ijg ------- o-r Al ;u.lAllstco ( Cd I - * .......

lflr' 579-F

-AA1-.%CG AI..sIC (CE) gI CC@1(Cd) harpy C harpy harpy Compact Compact Tensile

• Original Specimens BTI I &

BT39 l BL39 l BT36 BL36 \ BT3 L33 [ T9 BTI2 were yielded during pre-B385 L35 BT32 BL32 lBT26*tlT25t l TI0l T9 BT8 BT37 BL37 BT34 D 1BL34 DBT31 l BL31 Dl l lJl l ll cracking and these specimens used as substitutes.

Figure 4-2 Capsule W Diagram Showing the Location of Specimens, Thermal Monitors, and Dosimeters Description of Program

WCAP-16382 5-1 VCAP-l6382 5-1 5 TESTING OF SPECIMENS FROM CAPSULE W 5.1 OVERVIEW The post-irradiation mechanical testing of the Charpy V-notch impact specimens and tensile specimens was performed in the Remote Metallographic Facility (RMF) at the Westinghouse Research and Technology Park. Testing was performed in accordance with I OCFR50, Appendices G and H12l, ASTM Specification El 85-82181, and Westinghouse Procedure RMF 840219J Revision 2 as modified by Westinghouse RMF Procedures 8102110], Revision 3, and 81031"], Revision 2.

Upon receipt of the capsule at the hot cell laboratory was opened per Procedure RMF 8804112]. The specimens and spacer blocks were carefully removed, inspected for identification number, and checked against the master list in WCAP-11381131. No discrepancies were found.

Examination of the two low-melting point 5790 F (304'C) and 590'F (310 0 C) eutectic alloys indicated no melting of either type of thermal monitor. Based on this examination, the maximum temperature to which the test specimens were exposed was less than 579 0 F (304'C).

The Charpy impact tests were performed per ASTM Specification E23-02a 1 3] and Procedure RMF 8103 on a Tinius-Olsen Model 74, 358J machine. The tup (striker) of the Charpy machine is instrumented with an Instron Dynatup Impulse instrumentation system, feeding information into an IBM compatible computer. With this system, load-time and energy-time signals can be recorded in addition to the standard measurement of Charpy energy (ED). From the load-time curve, the load of general yielding (PGY), the time to general yielding (TGy), the maximum load (PM), and the time to maximum load (T.,)

can be determined. Under some test conditions, a sharp drop in load indicative of fast fracture was observed. The load at which fast fracture was initiated is identified as the fast fracture load (PF). If the fast load drop terminates well above zero load, the termination load is identified as the arrest load (PA)-

The energy at maximum load (ENr) was determined by comparing the energy-time record and the load-time record. The energy at maximum load is approximately equivalent to the energy required to initiate a crack in the specimen. Therefore, the propagation energy for the crack (Ep) is the difference between the total energy to fracture (ED) and the energy at maximum load (EM).

The yield stress (sr) was calculated from the three-point bend formula having the following expression:

ay ='GY B L-a2 (1)

B(WY - a)'C (

where L = distance between the specimen supports in the impact testing machine; B = the width of the specimen measured parallel to the notch; W = height of the specimen, measured perpendicularly to the notch; a = notch depth. The constant C is dependent on the notch flank angle (y), notch root radius (p) and the type of loading (i.e., pure bending or three-point bending). In three-point bending, for a Charpy specimen in which q)= 450 and p = 0.010 in., Equation I is valid with C = 1.21.

Testing of Specimens from Capsule W

IL_

WCAP- 16382 5-2 Therefore, (for L = 4W),

B( IV -a)2 1.2 1 X, \V -G)IV For the Charpy specimen, B = 0.394 in., W = 0.394 in., and a = 0.079 in. Equation 2 then reduces to 33 Cy = .3PGY (3) where sy is in units of psi and PGY is in units of lbs. The flow stress was calculated from the average of the yield and maximum loads, also using the three-point bend formula.

Symbol 'A' in columns 4, 5, and 6 of Tables 5-5 through 5-8 is the cross-section area under the notch of the Charpy specimens:

A=B(lV-a)=0.1241 sq.in. (4)

Percent shear was determined from post-fracture photographs using the ratio-of-areas niethods in compliance with ASTM E23-02atI31 and A370-03at 14 1 . The lateral expansion was measured using a dial gage rig similar to that shown in the same specifications.

Tensile tests were performed on a 20,000 pound Instron, split console test machine (MIodel 11 15) pVI ASTMI Specification E8-04t1 5 1 and E21-03atI 6 J and Procedure RMF 8102"'('.

Extension measurements were made with a linear variable displacement transducer (LVI)TI extensometer. The extensometer gage length was 1.00 inch.

Elevated test temperatures were obtained with a three-zone electric resistance split-tube furnace with a 9-inch hot zone. All tests were conducted in air.

The yield load, ultimate load, fracture load, total elongation and uniform elongation were determined directly from the load-extension curve. The yield strength, ultimate strength and fracture strength were calculated using the original cross-sectional area. The final diameter and final gage length were determined from post-fracture photographs. The fracture area used to calculate the fracture stress (true stress at fracture) and percent reduction in area were computed using the final diameter measurement.

Testing of'Specimens from Capsule W

WCAP-16382 5-3 WCAP-16382 5-3 5.2 CHARPY V-NOTCH IMPACT TEST RESULTS The results of the Charpy V-notch impact tests performed on the various materials contained in capsule W, which received a fluence of 2.98 x I01 n/cm2 (E> 1.0 MeV) in 13.29 EFPY of operation, are presented in Tables 5-1 through 5-8 and are compared with unirradiated results 13 1 as shown in Figures 5-1 through 5-12.

The transition temperature increases and upper shelf energy decreases for the capsule W materials are summarized in Table 5-9. These results led to the following conclusions:

• Irradiation of the reactor vessel lower shell plate B8628-1 Charpy specimens, oriented with the longitudinal axis of the specimen parallel to the major rolling direction (Longitudinal orientation),to 2.98 x I o19 n/cm 2 (E> I.OMeV) resulted in a 30 ft-lb transition temperature increase of 391F and a 50 ft-lb transition temperature increase of 43.60 F. This results in an irradiated 30 ft-lb transition temperature of 47.81F and an irradiated 50 ft-lb transition temperature of 89.00 F for the Longitudinal oriented specimens.

• Irradiation of the reactor vessel lower shell plate B8628-1 Charpy specimens, oriented with the longitudinal axis of the specimen perpendicular to the major rolling direction of the plate (Transverse orientation),to 2.98 x 1019 n/cm2 (E> 1.0 MeV) resulted in a 30 ft-lb transition temperature increase of 45.50 F and a 50 ft-lb transition temperature increase of 63.10I F. This results in an irradiated 30 ft-lb transition temperature of 74.1 'F and an irradiated 50 ft-lb transition temperature of 133.2 0 F for Transverse oriented specimens.

• Irradiation of the weld metal Charpy specimens to 2.98 x 1O'9 n/cm 2 (E> 1.OMeV) resulted in a 30 ft-lb transition temperature increase of 31.4°F and a 50 ft-lb transition temperature increase of 47.9°F. This results in an irradiated 30 ft-lb transition temperature of 12.2°F and an irradiated 50 ft-lb transition temperature of 59.0°F.

• Irradiation of the weld Heat-Affected-Zone (HAZ) metal Charpy specimens to 2.98 x 1O'9 n/cm2 (E> 1.0 MeV) resulted in a 30 ft-lb transition temperature increase of 3.2°F and a 50 ft-lb transition temperature decrease of 4.6°F. This results in an irradiated 30 ft-lb transition temperature of-80.5°F and an irradiated 50 ft-lb transition temperature of-57°F.

• The average upper shelf energy of the lower shell plate B8628-1 (Longitudinalorientation) resulted in an average energy decrease of 5 ft-lb after irradiation to 2.98 x 1019 n/cm2 (E> 1.0 MeV). This results in an irradiated average upper shelf energy of 84 ft-lb for the Longitudinal oriented specimens.

Testing of Specimens from Capsule W

It WCAP-16382 54

• The average upper shelf energy of the lower shell plate B8628-1 (Transverse orientation) resulted in an average energy decrease of I ft-lb after irradiation to 2.98 x 1O' 9 n/cm2 (E> 1.0 MeV). Hence, this results in an irradiated average upper shelf energy of 69 ft-lb for tile Transverse oriented specimens.

• The average upper shelf energy of the weld metal Charpy specimens resulted an average energy decrease of 5 ft-lb after irradiation to 2.98 x 109 n/cm 2 (E> 1.0 MeV). Hence, this results in an irradiated average upper shelf energy of 87 ft-lb for the weld metal specimens.

• The average upper shelf energy of the weld HAZ metal Charpy specimens resulted in an average energy decrease of 6 ft-lb after irradiation to 2.98 x 1019 n/cm 2 (E> I.OMeV). This results in an irradiated average upper shelf energy of 100 ft-lb for the weld HAZ metal.

• A comparison of the Vogtle Electric Generating Plant Unit 2 reactor vessel beltline material test results with the Regulatory Guide 1.99, Revision 2111 predictions led to the following conclusions:

- The measured 30 ft-lb transition temperature shift value for the lower shell plate B8628-l (Longitudinal orientation) is less than the Regulatory Guide 1.99, Revision 2, prediction.

- The measured 30 ft-lb transition temperature shift value for the lower shell plate B8628-l (Transverse orientation) is greater than the Regulatory Guide 1.99, Revision 2, prediction.

However, the shift value is less than the two sigma allowance by the Regulatory Guide 1.99, Revision 2, when calculating adjusted reference temperatures.

- The measured 30 ft-lb transition temperature shift value for the surveillance weld metal is less than the Regulatory Guide 1.99, Revision 2, prediction.

- The measured percent decrease in upper shelf energy for all the surveillance materials for Capsule "W" is less than the Regulatory Guide 1.99, Revision 2, predictions.

All beltline materials exhibit a more than adequate upper shelf energy level for continued safe plant operation and are predicted to maintain an upper shelf energy greater than 50 ft-lb throughout the end of the current license (36 EFPY) and a potential license renewal (54 EFPY) as required by IOCFR50, Appendix G [2J The fracture appearance of each irradiated Charpy specimen from the various surveillance capsule W materials is shown in Figures 5-13 through 5-16 and shows an increasingly ductile or tougher appearance with increasing test temperature.

The load-time records for individual instrumented Charpy specimen tests are shown in Appendix B.

Testing of Specimens from Capsule W

WCAP-16382 5-5 5.3 TENSILE TEST RESULTS The results of the tensile tests performed on the various materials contained in Capsule W irradiated to 2.98 x 1019 n/cm2 (E> 1.0 MeV) are presented in Table 5-11 and are compared with unirradiated results1 3 1 as shown in Figures 5-17 through 5-19.

The results of the tensile tests performed on the lower shell plate B8628-1 (Longitudinalorientation) indicated that irradiation to 2.98 x 109 n/cm 2 (E> 1.0 MeV) caused approximately a 3 to I I ksi increase in the 0.2 percent offset yield strength and approximately a 5 to 10 ksi increase in the ultimate tensile strength when compared to unirradiated data131 (Figure 5-17).

The results of the tensile tests performed on the lower shell plate B8628-1 (Transverse orientation) indicated that irradiation to 2.98 x i '9 n/cm2 (E> 1.0 MeV) caused an approximate increase of 4 to 12 ksi in the 0.2 percent offset yield strength and approximately a 4 to 9 ksi increase in the ultimate tensile strength when compared to unirradiated dataW31 (Figure 5-18).

The results of the tensile tests performed on the surveillance weld metal indicated that irradiation to 2.98 x 10'9 n/cm 2 (E> 1.0 MeV) caused approximately a 8 to I I ksi increase in the 0.2 percent offset yield strength and approximately a 3 to 7 ksi increase in the ultimate tensile strength when compared to unirradiated data1 31 (Figure 5-19).

The fractured tensile specimens for the lower shell plate B8628-1 material are shown in Figures 5-20 and 5-21, while the fractured tensile specimens for the surveillance weld metal are shown in Figure 5-22.

The engineering stress-strain curves for the tensile tests are shown in Figures 5-23 through 5-25.

5.4 1/2T COMPACT TENSION SPECIMEN TESTS Per the surveillance capsule testing contract, the 1/2T Compact Tension Specimens were not tested and are being stored at the Westinghouse Science and Technology Center Hot Cell facility.

Testing of Specimens from Capsule W

WCAP- 16382 5-6

\VCAP- 16382 5-6 Table 5-1 Charpy V-notch Data for the Vogtle Unit 2 Lower Shell Plate B8628-I Irradiated to a Fluence of 2.98 x 10"9 n/cm 2 (E> 1.0 WeV) (LongitudinalOrientation)

Sample Temperature Impact Energy Lateral Expansion Shear Number OF l C ft-lbsmils mm  %

BL31 -50 -46 7 9 6 0.15 2 BL34 -25 -32 11 15 8 0.20 5 BL40 0 -18 21 28 15 0.38 10 BL42 25 -4 15 20 l I 0.28 15 BL44 40 4 27 37 24 0.61 20 BL33 50 10 42 57 39 0.99 25 BL39 50 10 22 30 17 0.43 20 BL38 75 24 42 57 30 0.76 40 BL32 100 38 52 71 45 1.14 60 BL41 125 52 61 83 52 1.32 75 BL36 150 66 BL45 150 66 77 104 61 1.55 90 BL43 175 79 85 115 65 1.65 100 BL35 200 93 81 110 65 1.65 100 BL37 225 107 85 115 64 1.63 100

• No Data Testing of Specimens from Capsule W

WCAP- 16382 5>-7 Table 5-2 Charpy V-notch Data for the Vogtle Unit 2 Lower Shell Plate B8628-1 Irradiated to a Fluence of 2.98 x 1019 n/cm 2 (E> 1.0 MNe) (Transverse Oricntation)

Sample Temperature Impact Energy Lateral Expansion Shear Number OF T c ft-lbs Joules mi l mm  %

BT32 -75 -59 5 7 4 0.10 2 BT41 -25 -32 8 11 5 0.13 5 BT44 0 -18 10 14 10 0.25 10 BT42 25 -4 21 28 18 0.46 15 BT43 50 10 26 35 23 0.58 20 BT37 75 24 29 39 28 0.71 30 BT36 75 24 24 33 23 0.58 25 BT40 100 38 40 54 37 0.94 5(

BT33 125 52 42 57 42 1.07 65 BT39 150 66 60 81 52 1.32 9(

BT38 200 93 61 83 45 1.14 95 BT45 225 107 72 98 56 1.42 10(

BT31 250 121 74 100 61 1.55 100 BT35 275 135 61 83 53 1.35 10 BT34 275 135 70 95 52 1.32 1(0 Testing of Specimcns from Capsule: W

WCAP-1I6(382 5-X WCAP- 16382 5-8 Table 5-3 Charpy V-notch Data for the Vogtle Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 2.98 x 1019 nlcm 2 (E> 1.0 MeV)

Sample Temperature Impact Energy Lateral Expansion Shear Number F l °C ft-bs lJoules mils l m I  %

BW333 -50 46 5 7. 5 0.13 5 BW42 -25 -32 14 19 11 0.28 5 BW36 0 -18 36 49 28 0.71 15 BW35 0 -18 31 42 25 0.64 20 BW45 25 -4 22 30 22 0.56 25 BW41 50 10 38 52 34 0.86 30 BW37 75 24 71 96 47 1.19 55 BW40 75 24 64 87 49 1.24 50 BW31 100 38 64 87 52 1.32 65 BW34 140 60 71 96 57 1.45 80 BW38 175 79 73 99 63 1.60 90 BW32 200 93 77 104 61 1.55 95 BW39 225 107 88 119 74 1.88 100 BW43 250 121 79 107 67 1.70 100 BW44 250 121 93 126 72 1.83 100 Testing of Specimens from Capsule W

W\CAP-1I6382 5-9 Table 5-4 Charpy '-notch Data for the Vogtle Unit 2 Heat Affected Zone Material Irradiated to a Fluence of 2.98 x 1019 n/cm 2 (E> 1.0 MeV)

Sample Temperature Impact Energy Lateral Expansion Shear Number F l C ft-lbs lJoules mils l mm  %

BH44 -175 -115 3 4 2 0.05 2 BH3l -125 -87 17 23 8 0.20 5 BH33 -90 -68 31 42 19 0.48 15 BH43 -75 -59 43 58 25 0.64 20 BH42 -75 -59 17 23 12 0.30 15 BH38 -50 -46 57 77 32 0.81 55 BH37 -50 -46 57 77 34 0.86 60 BH34 -25 -32 67 91 36 0.91 50 BH32 0 -18 101 137 71 1.80 90 1141 0 -18 92 125 59 1.50 70 BH39 25 -4 98 133 58 1.47 100 BH40 50 10 99 134 60 1.52 85 BH45 75 24 105 142 65 1.65 95 BH36 125 52 107 145 68 1.73 100 BH35 150 66 93 126 70 1.78 100 Testing of Specimncns from Capsule W

WCAP-1638ls 5-I{}

Table 5.5 Instruntented Chlarpy Inmpact Test Results for the Vogtle Unit 2 Lower Shell Plate 118628-1 Irradiated to a Fluence of 2.98 x 10I9 n/cn 2 (1E>l.O MeX') (Loigituldinial Orienjtalioni)

Normalized Energies ft-lb/in Charpy Yield Time to Fast Test Energy Load Yield Max. Timc to Fract. Arrest Yield Flow Sample Temp. Ep Charpy Max. Prop. P(;G tcG Load Max. t,%t Load PF Load PA Stress Stress No. ('F) tt-lb) EJA E^,/A EA (lb) (msec) P3% (lb) (nmsec) (lb) (lb) Sy (ksi) (ksi)

BL31 -50 7 56 31 26 3196 0.13 3352 0.15 3352 0 106 109 BL34 -25 II 89 46 43 3274 0.14 3856 0.18 3856 0 109 119 BL40 0 21 169 72 97 3450 0.15 4249 0.23 4249 0 115 128 BL42 25 IS 121 61 60 2885 0.13 3955 0.21 3942 0 96 114 BL44 40 27 218 131 87 2984 0.14 4194 0.35 4194 194 99 120 BL33 50 42 338 238 100 3368 0.14 4534 0.53 4488 182 112 132 BL39 50 22 177 66 III 3249 0.14 4070 0.22 4031 383 108 122 BL38 75 42 338 221 117 3290 0.15 4534 0.50 4523 725 110 130 BL32 100 52 419 216 203 2911 0.14 4259 0.52 4152 1035 97 119 BL41 125 61 491 225 267 3130 0.14 4278 0.52 4143 2047 104 123 BL36 150 *

• _

BL45 150 77 620 300 320 3100 0.15 4356 0.67 3864 2023 103 124 BL43 175 85 685 224 461 2954 0.14 4296 0.53 n/a n/a 98 121 BL35 200 81 653 282 370 2998 0.15 4159 0.65 n/a n/a 100 119 BL37 225 85 685 209 476 2872 0.13 4157 0.51 n/a n/a 96 117

• No Data Testing of Specimens from Capsule W F

WCAP. 16382 l WCAP. 16382 5-Il 5-l Table 5.6 Instrumcnted Cliarpy Impact Test Results for the Vogtic Unit 2 l,ower Sell Platc 8628-1 Irradiated to a Fluence of 2.98 x 1019 n/cm2 (E>1.0 WcV) (Transversc Orienitation)

Normalized Energies 2

)

j

_(ft-lb/in Charpy Yield Time to Fast Test Energy Loand Yield INlax. Time to IFracl. Arrest Yicldl Flowv Sample Temp. El) Cbarpy Max. Prop. PGN. t;. Load Mlax. t%, Load Pl' Load Stress Stress No. (OF) (ft-lb) Er/A E.%/A E/A (Ib) (mnsee) P., (11) (msec) (ll) PA (Ih) S. (ksi) (ksi)

BT32 -75 5 40 21 19 2455 0.12 2491 0.13 2491 0 82 82 BT41 -25 8 64 33 31 3428 0.15 3485 0.16 3485 0 114 115 BT44 0 10 81 45 36 3578 0.15 3920 0.18 3920 0 119 125 BT42 25 21 169 109 60 3083 0.13 4170 0.3 4147 0 103 121 BT43 50 26 209 138 71 3195 0.14 4249 0.35 4239 155 106 124 BT37 75 29 234 133 101 2898 0.13 4140 0.35 4137 607 97 117 BT36 75 24 193 110 83 3210 0.14 4194 0.3 4176 452 107 123 BT40 100 40 322 196 127 3186 0.14 4251 0.46 4228 1388 106 124 BT33 125 42 338 155 184 2910 0.14 4117 0.4 4057 1704 97 117 BT39 150 60 483 207 277 3221 0.14 4317 0.48 3748 2644 107 126 BT38 200 61 491 186 305 2925 0.14 3987 0.47 2478 2021 97 115 BT45 225 72 580 224 356 3119 0.15 4362 0.52 n/a n/a 104 125 BT31 250 74 596 190 407 2715 0.13 4216 0.47 n/a n/a 90 115 BT35 275 61 491 158 333 2930 0.14 3892 0.42 n/a n/a 98 114 BT34 275 70 564 183 381 2912 0.14 4166 0.46 n/a l n/a 97 118 Testing of Specimcns from Capsuic W

WCAP-1I6382 5-12 5-12 WCAP- 16382 Table 5-7 Instrumented Charpy Impact Test Results for the Vogtle Unit 2 Surveillance Weld Metal Irradiated to a Fluence of 2.98 x 10' 9 n/cm2 (E>l.O IMV)

Normalized Energies 2

(ft-lb/in ) .

Charpy Yield Time to Fast Test Energy Load Yield Nlax. \Time to Fract. Arrest Yield Flow Samplc Tcmp. Ens Charpy M\ax. Prop. PG;V t;w Load Nlax. t,%, Load PF Load Stress Stress No. (OF) (ft-lb) EI/A Ex,/A EdA (lb) (nisec) IN (lb) (msec) (lb) PA (Ib) Sy (ksi) (kS;)

BW33 -50 5 40 18 22 2042 0.1 2248 0.13 2248 0 68 71 BW42 -25 14 113 71 41 3119 0.13 4229 0.23 4229 0 104 122 BW36 0 36 290 232 58 3440 0.14 4527 0.51 4521 0 115 133 BW35 0 31 250 192 57 3379 0.14 4413 0.44 4387 0 113 130 BW45 25 22 177 113 64 2879 0.13 4002 0.31 3987 268 96 115 BW41 50 38 306 236 70 3151 0.14 4443 0.53 4419 182 105 126 BW37 75 71 572 237 335 3222 0.14 4639 0.52 3997 640 107 131 BW40 75. 64 516 241 274 3160 0.14 4632 0.52 4261 1060 105 130 BW31 100 64 516 223 293 3031 0.14 4227 0.52 3970 1400 101 121 BW34 140 71 572 301 271 3113 0.14 4205 0.67 3703 2063 104 122 BW38 175 73 588 217 371 2960 0.14 4075 0.53 3549 1984 99 117 BW32 200 77 620 293 328 3002 0.15 4107 0.67 3320 2532 100 118 BW39 225 88 709 295 414 3043 0.14 4198 0.67 n/a n/a 101 121 BW43 250 79 637 205 432 2764 0.14 3968 0.52 n/a n/a 92 112 BW44 250 93 749 218 532 2899 0.14 4211 0.52 n/a n/a 97 118 Testing of Specimcns from Capsule W

WCAP- 16382 5-13 WCAP- 16382 5-13 Table 5-8 Instrumented Charpy Impact Test Results for the Vogtle Unit 2 lleat-Affected-Zone (HAZ) NIetal Irradiated to a Fluence of 2.98 x 101 n/cm 2 (E>1.0 WeV)

Normalized Energies 2

(ft.lb/in )

Charpy Yield Time to Fast Test Energy Load Yield Max. Time to Fract. Arrest Yield Flow Sample Temp. ED Charpy Max. Prop. PGY tcy Load Max. tN, Load PF Load Stress S St ress No. (OF) (ft-lb) ED/A EI1/A EW/A (lb) (msec) P\, (Ih) (mSeC) (11 P1, (Ib) (ksi) (ksi)

BH44 -175 3 24 II 13 1198 0.08 1418 0.11 1418 0 40 44 BH31 -125 17 137 86 51 4299 0.15 5233 0.23 5227 0 143 159 BH33 -90 31 250 195 55 3472 0.14 4982 0.42 4963 0 116 141 BH43 -75 43 346 261 86 4027 0.15 5032 0.51 5026 637 134 151 BH42 -75 17 137 80 57 3659 0.14 4647 0.23 4647 0 122 138 BH38 -50 57 459 248 211 3482 0.14 4906 0.51 4655 551 116 140 ,:;

B[137 -50 57 459 253 207 3538 0.14 4930 0.52 4735 1176 118 141 BH34 -25 67 540 346 194 3592 0.14 4836 0.68 4683 1660 120 140 BH32 0 101 814 351 463 3778 0.15 4838 0.69 3417 1712 126 143 BH41 0 92 741 338 403 3572 0.15 4802 0.67 2625 602 119 139 BH39 25 98 790 255 534 3542 0.14 4717 0.54 n/a n/a 118 138 BH40 50 99 798 337 461 3437 0.14 4701 0.68 3271 1683 114 135 BH45 75 105 846 325 521 3181 0.14 4640 0.68 3401 1915 106 130 BH36 125 107 862 235 627 3226 0.14 4501 0.52 n/a n/a 107 129 BH35 150 93 749 322 428 3307 0.14 4486 0.68 n/a n/a 110 130 Testing of Specimcns from Capsule W

WCAP-16382 5-14 5-14 WCAP-16382 Table 5-9 Effect of Irradiation to 2.98 x iO' 9 n/cm2 (E>I.0 MeV) on the Notch Toughness Properties of the Vogtle Unit 2 Reactor Vessel Surveillance Materials Average 30 (ft-lb)(a) Average 35 mil Lateralib) Average 50 ft-lb0) Average Energy Absorption(a)

Material Transition Temperature ( 0 F) Expansion Temperature (0 F) Transition Tcmperature (IF) at Full Shear (ft-lb)

Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AT Unirradiated Irradiated AE Lower Shell 8.8 47.8 39.0 36.4 74.7 38.3 45.4 89.0 43.6 89 84 -5 Plate B8628-1 (Lon gitudinal) _ .-

Lower Shell 28.6 74.1 45.5 44.0 97.1 53.1 70.1 133.2 63.1 70 69 -1 Plate B8628-1 (Transverse)

Weld Metal -19.2 12.2 31.4 -1.0 45.0 46.0 11.1 59.0 47.9 92 87 -5 HAZ Metal -83.7 -80.5 3.2 46.9 -46.5 0.4 -52.4 -57.0 4.6 106 100 -6

a. "Average" is defined as the value read from the curve fit through the data points of the Charpy tests (see Figures 5-1, 5-4, 5-7 and 5-10).

b. "Average" is defined as the value read from the curve fit through the data points of the Charpy tests (see Figures 5-2, 5-5, 5-8 and 5-11)

Testing of Specimens from Capsule W

WCAP-16382 5-15 Table 5-10 Comparison of the Vogtle Unit 2 Surveillance Material 30 ft-lb Transition Temperature Shifts and Upper Shelf Energy Decreases with Regulatory Guide 1.99, Revision 2, Predictions 30 ft-lb Transition Upper Shelf Energy Temperature Shift Decrease Material Capsule Fluence Predicted Measured Predicted Measured 2

(X 1019 n/cm ) (OF) (a) (OF) (b) (%) (a) (%/0)(C)

Lower Shell U 0.356 22.2 2.0 15 0 Plate B8628-1 Y 1.12 31.9 5.8 19.5 0 (Longitudinal) X 1.78 36.0 29.4 22 3 W 2.98 40.0 39.0 25 6 Lower Shell U 0.356 22.2 0 . 0 (d) 15 0 Plate B8628-1 Y 1.12 31.9 1.9 19.5 0 (Transverse) X 1.78 36.0 29.8 22 7 W 2.98 40.0 45.5 25 1 Weld Metal U 0.356 26.0 0 . 0 0 (d) 15 0 Y 1.12 37.5 18.7 19.5 7 X 1.78 42.2 19.9 22 7 W 2.98 47.0 31.4 25 5 HAZ Metal U 0.356 -. 0 0 0 d) --- 0 Y 1.12 --- 0.00( ) - 0 X 1.78 --- 0.0 0 (d) --- 7 W 2.98 3.2 6 Notes:

(a) Based on Regulatory Guide 1.99, Revision 2, methodology using the mean weight percent values of copper and nickel of the surveillance material.

(b) Calculated using measured Charpy data plotted using CVGRAPH, Version 5.0.2 (See Appendix C)

(c) Values are based on the definition of upper shelf energy given in ASTM E185-82.

(d) Actual values for ARTNDT are -7.1 (Plate), -17.3 (Weld), -24.3 (HAZ Cap. U), -10.1 (HAZ Cap. Y) and -2.5 (HAZ Cap. X). This physically should not occur, therefore for conservatism a value of zero will be reported (i.e. No Change in T30).

Testing of Specimens from Capsule W

WCAP-16382 5-16 5-16 WCAP-16382 Table 5-11 Tensile Properties of the Vogtle Unit 2 Reactor Vessel Surveillance Materials Irradiated to 2.98 x 10"19 n/cm2 (E > 1.0 McV)

Material Sample Test 0.2% Ultimate Fracture Fracture Fracture Uniform Total Reduction Number Temp. Yield Strength Load Stress (ksi) Strength Elongation Elongation in Area (%)

(OF) Strength (ksi) (kip) (ksi) (%) (%)

_ _ _ __ _ _ ~~~~(ksi) _ _ _ _ _ __ _ _

Lower BL-7 75 76.2 96.8 3.20 174.9 65.1 10.5 24.4 63 Plate B8628-1 BL-8 150 73.6 93.4 2.92 176.5 59.4 11.3 26.4 66 (Longitudinal) BL-9 550 64.2 92.4 3.13 151.9 63.8 10.5 21.5 58 Lower BT-7 75 73.3 95.5 3.34 127.5 67.9 12.0 22.5 47 Plate B8628-1 BT-8 150 73.8 91.7 3.21 141.4 65.4 11.3 21.6 54 (Transverse) BT-9 550 66.2 91.6 3.63 135.3 73.9 10.5 18.6 45 BW-7 75 73.5 90.0 2.90 181.8 59.1 12.0 26.7 68 Wcld Metal BW-8 175 73.2 85.2 2.76 193.1 56.3 11.0 24.6 71 BW-9 550 71.0 86.4 3.18 154.0 64.7 12.0 21.3 58 Testing of Specimens from Capsulc W

WCAP- 16382 5-17 WCAP- 16382 5-17 LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:15 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. lleat #

1 Vogtle 2 UNIRR SA533B1 LT C3500-2 2 Vogtle 2 U SA533B 1 LT C3500-2 3 Vogtle 2 y SA533B I LT C3500-2 4 Vogtle 2 x SA533B 1 LT C3500-2 5 Vogtle 2 w SA533B I LT C3500-2 300 -

250 -

, 200 -

I 0

0 U-p 150 -

C z

> 100-50 -

0-

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F 0 Set I a Set 2 0 Set 3 a Set 4 v Set 5 Results Curve Fluence 1SE USE d-USE T @30 d-T @30 T @50 d-T @50

2. 2 89.0 .0 8. 8 .0 45.4 .0 2 2. 2 99.0 10.0 . 10.8 2.0 54. 9 9.5 3 2. 2 100.0 11.0 14.6 5.8 50. 5 5. 1 4 2. 2 86. 0 -3.0 38.2 29.4 75.6 30. 2 5 2.2 84. 0 -5.0 47. 8 39.0 89. 0 43.6 Figure 5-1 Charpy V-Notch Impact Energy vs. Temperature for Vogtle Unit 2 Reactor Vessel Louwer Shell Plate B8628-1 (Longitudinal Orientation)

Testing of Specimens from Capsule W

WCAP- 16382 5-lP8 VCAP- 16382 5-18 LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 02:31 PM Data Set(s) Plotted Curve Plant Capsule Material Or. [feat #

I Vogtle 2 UNIRR SA533BI LT C3500-2 2 Vogtle 2 U SA533B I LT C3500-2 3 Vogtle 2 y SA533B I LT C3500-2 4 Vogtle 2 X SA533BI LT C3500-2 5 Vogtle 2 W SA533B I LT C3500-2 200 150 E

0 a 100 fa 50 0 4-

-300 0 300 600 Temperature In Deg F 0 Set I a Set 2 O Set 3 & Set 4 v Set5 Results Curve Fluence LSE USE d-USE T @35 d-T @35

.0 75.9 .0 36.4 .0 2 .0 70.6 -5.3 45. 8 9. 4 3 .0 68.9 - 7. 1 46. 8 10.4 4 .0 64.6 -11.4 90.0 53.6 5 .0 69.4 -6.6 74.7 38.3 Figure 5-2 Charpy V-Notch Lateral Expansion vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (LongitudinalOrientation)

Tcsting of Specimens from Capsule W

WCAP- 16382 5-19 VCAP- 16382 5-] 9 LOWER SHELL PLATE 8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:36 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #

1 Vogtle 2 UNIRR SA533B I LT C3500-2 2 Vogtle 2 U SA533B 1 LT C3500-2

3. Vogtle 2 Y SA533B 1 LT C3500-2 4 Vogtle 2 x SA533B 1 LT C3500-2 5 Vogtle 2 w SA533B I LT C3500-2 125 100 0

a 75 a,

a-

a. 50 25:

O--

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F o Set 1 a Set 2 0 Set 3 a Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @50 d-T @50

.0 100.0 .0 65.0 .0 2 .0 100.0 .0 62.2 -2.8 3 .0 100.0 .0 77.8 12. 8 4 .0 100.0 .0 69.3 4. 3 5 .0 100.0 .0 86.5 21.5 Figure 5-3 Charpy V-Notch Pcrcent Shear vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (LongitudinalOrientation)

Testing of Specimens from Capsule W

WCAP- I 6382 5-2()

WCAP- 16382 5-2()

LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 01:11 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Hleat #

I Vogtle 2 UNIRR SA533B1I TL C3500-2 2 Vogtle 2 U SA533B I TL C3500-2 3 Vogtle 2 Y SA533BI TL C3500-2 4 Vogtle 2 x SA533B I TL C3500-2 5 Vogtle 2 w SA533B I TL C3500-2 300 250 w

- 200 06 0

C wEl 100 z

> 100 8 ----- ---------

50 0

_d<-I .-, ...4

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F 0 Set I a Set 2 o Set 3 a Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50 2.2 70. 0 .0 28. 6 .0 70. 1 .0 2 2. 2 79. 0 .9.0 21.5 -7. 1 82.6 12.5 3 2.2 73.0 3.0 30. 5 1.9 87.0 16.9 4 2.2 65. 0 -5.0 58. 4 29. 8 113.5 43. 4 5 2.2 69. 0 -1.0 74. 1 45. 5 133.2 63. 1 Figure 5-4 Charpy V-Notch Impact Energy vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transverse Orientation)

Tesiing of Specimens from Capsule W

WCAP- 16382 5_21 WCAP- 16382 5-21 LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 12/01/2004 01:44 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #

1 Vogtle 2 UTNIRR SA533B I TL C3500-2 2 Vogtle 2 U SA533B I TL C3500-2 3 Vogtle 2 y SA533B I TL C3500-2 4 Vogtle 2 XI SA533B I TL C3500-2 5 Vogtle 2 W SA533B I TL C3500-2 200 150 2

E C

.2 in

& 100 a

9 50 o +-

-300 0 300 600 Temperature in Deg F 0 Set 1 a Set 2 O Set 3  % Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @35 d.T @35

.0 65.3 .0 44.0 .0 2 .0 57. 1 - 8.2 53. 1 9. 1 3 .0 63.8 -1.5 62.9 18.9 4 .0 52.4 -12.9 94.3 50.3 5 .0 55.8 -9.5 97.1 53.1 Figure 5-5 Charpy V-Notch Lateral Expansion vs. Temperature for Vogtle Unit 2 Reactor Vessel Low er Shell Plate B8628-1 (Transverse Orientation)

Testing of Specimens from Capsule W

WCAP- 16382 5-22

\VCAP- 16382 5-22 LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:32 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Heat #

4 Vogtle 2 UNIRR SAS33B 1 TL C3500-2 2 Vogtle 2 U SA533BI TL C3500-2 3 Vogtle 2 y SA533B1 TL C3500-2 4 Vogtle 2 x SA533B1 TL C3500-2 5 Vogtle 2 w SA533BI TL C3500-2 125 100 I- 75 a

Ca en 0)

C) 50 25 -

0-

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F o Set I o Set 2 0 Set 3 A Set 4 v Set 5 Resulls Curve Fluence LSE USE d-USE T @50 d-T @50

.0 100.0 .0 66. 5 .0 2 .0 100.0 .0 65.5 - 1. 0 3 .0 100.0 .0 83.0 16.5 4 .0 100.0 .0 66. 2 -. 3 5 .0 100.0 .0 100.4 33.9 Figure 5-6 Charpy V-Notch Percent Shear vs. Temperature for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transverse Orientation)

Testin- of Specimens from Capsule W

WCAP- 16382 5-23 SURVEILLANCE PROGRAM WELD MATERIAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 01:23 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Hleat #

1 Vogtle 2 UJNIRR SMAW NA 87005 2 Vogtle 2 U SMAW NA 87005 3 Vogtle 2 y SMAW NA 87005 4 Vogtle 2 x SMAW NA 87005 5 Vogtle 2 X SMAW NA 87005 300 250 in D, 200 0

LL Bi150 0

w z

100 50 -

O-.~

-300 -200 -100 0 100 200 300 400 500 600 Temperature In Deg F 0 Set 1 a Set 2 0 Set 3 A Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50

2. 2 92. 0 .0 - 19.2 .0 11.1 .0 2 2. 2 98.0 6.0 - 36.5 - 17.3 .0 -11.1 3 2. 2 86.0 -6.0 -.5 18.7 32.0 20.9 4 2. 2 87.0 -6.0 .7 19.9 34.5 23.4 5 2. 2 87.0 -5.0 12.2 31.4 59. 0 47. 9 Figure 5-7 Charpy V-Notch Impact Energy vs. Temperature for Vogtle Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule W

WCAP- I 6382 5-24 VCAP- 16382 5-24 SURVEILLANCE PROGRAM WELD MATERIAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 04:17 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. [feat #

Vogtle 2 UNIRR SMAW NA 87005 2 Vogtle 2 U SMAW NA 87005 3 Vogtle 2 y SMAW NA 87005 4 Vogtle 2 SMAW NA 87005 5 Vogtle 2 w SMAW NA 87005 200 150 A

Eu) c0 a 100 0

50 0 _-

-300 0 300 600 Temperature In Deg F 0 set I a Set 2 O Set 3 A Set4 v Set 5 Results Curve Fluence LSE USE d-USE T @35 d-T @35

.0 80. 4 .0 -1.0 .0 2 .0 72. 6 -7.9 -. 3 .7 3 .0 71.0 -9.4 16.2 17.2 4 .0 71. 2 -9.2 28. 1 29. 1 5 .0 70. 0 -10.5 45.0 46. 0 Figure 5-8 Charpy V-Notch Lateral Expansion vs. Temperature for Vogtle Unit 2 Reactor Vessel Weld Metal Tesfing ol Specimens from Capsule W

WCAP- 1638S2 5-25 WCAP 16382 5-25 SURVEILLANCE PROGRAM WELD MATERIAL CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11119/2004 03:51 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Ileat #

1 Vogtle 2 UNIRR SMAW NA 87005 2 Vogtle 2 U SMAW NA 87005 3 Vogtle 2 Y SMAW NA 87005 4 Vogtle 2 x SMAW NA 87005 5 Vogtle 2 w SMAW NA 87005 125 100 75 co CL

.2

0. 50 25 -

0-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set 1 a Set 2 0 Set 3 a Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @50 d-T @50

.0 100.0 .0 28. 1 .0 2 .0 100.0 .0 -4. 1 - 32.2 3 .0 100.0 .0 27.3 -. 8 4 .0 100.0 .0 29.7 1.6 5 .0 100.0 .0 74.5 46.4 Figure 5-9 Charpy V-Notch Percent Shear vs Temperature for Vogtle Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule W

WCAP- I 6.382 5-26 WCAP- 16382 5-26 HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:21 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. HIeat #

Vogtle 2 UNIRR SA533B I NA C3500-2 2 Vogile 2 U SA533B I NA C3500-2 3 Vogtle 2 y SA533B I NA C3500-2 4 Vogtle 2 x SA533B I NA C3500-2 5 Vogtle 2 W SA533BI NA C3500-2 300 250 D0 0 200 0

IL.

w z

- 150 a,

> 100

. VY =S--0Zo. S.,.

.S..bS

°............ ..........

50 A

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set I a Set 2 o Set 3 A Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @30 d-T @30 T @50 d-T @50

2. 2 106.0 .0 - 83. 7 .0 -52.4 .0 2 2. 2 122.0 16.0 - 108.0 - 24. 3 - 80. 2 -27.8 3 2. 2 114.0 8.0 - 93. 8 - 10. 1 - 63. 9 -11.5 4 2. 2 99. 0 -7.0 - 86. 2 -2.5 - 53. 2 -.8 S 2. 2 100.0 -6.0 - 80. 5 3. 2 - 57.0 -4.6 Figure 5-10 Charpy V-Notch Impact Energy vs. Temperature for Vogtle Unit 2 Reactor Vessel

}leat-Affected-Zone Miaterial Testing of Specimens from Capsule W

WCAP- 163X2 5- 27 WCAP- 16382 527 HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/2212004 12:26 PM Data Set(s) Plotted Curve Plant Capsule Material Ori. Ileat #

1 Vogtle 2 UNIRR SA533BI NA C3500-2 2 Vogtle 2 U SA533BI NA C3500-2 3 Vogtle 2 y SA533B I NA C3500-2 4 Vogtle 2 x SA533BI NA C3500-2 5 Vogtle 2 w SA533BI NA C3500-2 200 150

'A i

C 0

(n C

8 100 50 O +-

-300 0 300 600 Temperature In Deg F o Set 1 o Set 2 o Set 3 A Set 4 v Set 5 Results Curve Fluence LSE USE d-USE T @35 d-T @35

.0 72.4 .0 - 46.9 .0 2 .0 65.9 -6.5 - 67.7 -20.8 3 .0 70. 6 -1.9 - 53.4 -6.5 4 .0 69.4 -3.0 -35. 4 11.5 5 .0 68. 0 -4.4 -46. 5 .4 Figure 5-11 Charpy V-Notch Lateral Expansion vs. Temperature for Vogtle Unit 2 Reactor Vessel Heat-Affected-Zone Material Testing of Specimens from Capsule W

IL-WCAP- 16382 5-28 HEAT AFFECTED ZONE CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:36 AM Data Set(s) Plotted Curve Plant Capsule Material Ori. lleat #

1 Vogtle 2 UNIRR SA533BI NA C3500-2 2 Vogtle 2 U SA533B I NA C3500-2 3 Vogtle 2 y SA533BI NA C3500-2 4 Vogtle 2 x SA533B I NA C3500-2 5 Vogtle 2 w SA533B I NA C3500-2 125 100 n-75 M

0

'U co 0)

P I..

0L 50 25 -

0 -

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F 0 Set 1 o Set 2 0 Set 3 a Set 4 v Set 5 Results Curve Fluence LSE USE d.USE T @50 d-T @50

.0 100.0 .0 -34.6 .0 2 .0 100.0 .0 -74.4 - 39. 8 3 .0 100.0 .0 - 49. 3 - 14. 7 4 .0 100.0 .0 -40.2 -5. 6 5 .0 100.0 .0 -42.8 -8.2 Figure 5-12 Charpy V-Notch Percent Shear vs. Temperature for Vogtle Unit 2 Reactor Vessel Hleat-Affected-Zone Material Testing of Specimens from Capsule W

INvCAP- I16382 5-29 WCAP- 16382 5-29 Ril3-l -5 0 F BT40n noF RI 42. 25 0F BL41, 1250 F BL45, 1500 F BL43,175-F BL35, 2UU0 F bL37, 2251F Figure 5-13 Charp Impact Specimen Fracture Surfaces for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Longiludinal Orieuntation)

Testing of Specimens from Capsule W

it WCAP-16382 5-30 BT44- fop RT42 25PF RT43. 5MOF BT36, 750 F M1U4, 100UF L51-69, 15UUF BT38, 200-F BT45, 225 0F BT31, 250 0F BT35, 275 0F 8T34, 275-F Figure 5-14 Cliarpy Impact Specimen Fracture Surfaces for Vogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transverse Orienitation)

Testing of Specimens from Capsule W

WCAP-16382 5-31 WCAP-16382 53 I PWJJ -5fO° TnwU MP RIVA45 15O 1E)ITA Inor BW37. 750 F BW40. 750 F BW31. 100WF BW34. 1401F BWi8, I /rj. BW32, 200 0 F BW39, 225 0 F BW43, 2()FU BW44, 250WF Figure 5-15 Cliarpf Impact Specimen Fracture Surfaces for Vogtlc Unit 2 Reactor 'essel W'eld Metal Testing of Specimens from Capsule W

if WCAP-1 6382 5-32 WCAP-1 6382 5-32 BH38. -500 F BH39, 250 F BH40, 50 0F BH45, 75 0F Uwoi, 1ZI-P BH35, 150 0F Figure 5-16 Charpy Impact Specimen Fracture Surfaces for Vogtle Unit 2 Reactor Vessel Heat-Affected-Zone Metal Testing of Specimens from Capsule W

WCA\P- 16382 5 -33 120 -

100 - ULTIMATE TENSILE STRENGTH 80 -

-n'60 a: 0.2% YIELD STRENGTH I.-

40 20 -

0 I I 0 100 200 300 400 500 600 TEMPERATURE( F)

Legend: A and 0 are Unirradiated Aand

• are Irradiated to 2.98 x 1019 n/cm 2 (E > 1.0 McV) 70 60 -

REDUCTION IN AREA 50 -

I7-40 -

-j 30 - TOTAL ELONGATION 0 20 -

10 -

UNIFORM ELONGATION 0

0 100 200 300 400 500 600 TEMPERATURE ( F)

Figiure 5.-17 Tensile Properties for Vogtle Unit 2 Reactor Vessel Lower Sil il P'late B8628-1 (Lonrgitudinal Orientationi)

Tcstinig of Specilens from Caipsule NV

WCA P-16I 67-34 120 -

100 - ULTIMATE TENSILE STRENGTH

{,,80 - * *-_

U. 60- -

e4 0.2% YIELD STRENGTH 20 -

0 100 200 300 400 500 600 TEMPERATURE( F)

Le-end: A and o are Unirradiated Aand

• are Irradiated to 2.98 x 1019 n/C112 (E > 1.0 MeV) 70 -- * -- _ _

REDUCTION IN AREA 60 - K

_ 50 -

> 40

_ 30 TOTAL ELONGATION a20 10 I ~* -

0 UNIFORM UNIFORM 0 100 200 300 400 500 600 TEMPERATURE ( F)

Figure 5-13 Tensile Properties for Vogtle Unit 2 Reactor Vessel Lower Shell Plate 1B8628-1 (Transverse Orienratiau,)

I'Tein. ol'SpLeci'

~ ens rromii Capsile NV

WCA\P-I1632 5-35R WCAP- 16382 5-35 100 -.

80.~ -ULTIMATE TENSILE STRENGTH 80 Xoo60 - A co 0.2% YIELD STRENGTH ar 40 Cn 20 -

O- , _ , _ - ,-,

0 100 200 300 400 500 600 TEMPERATURE( F)

Legend: A andl o are Unirradliatled A and

• arc Irradiated to 2.98 x 0'9 n/cm 2 (E > 1.0 MeV) 7 80;- ---- - ---

70 -

60 - REDUCTION IN AREA I7- 50 -

I-- 40 -

30 - TOTAL ELONGATION C) 20 -

10 -

UNIFORM ELONGATION 0-0 100 200 300 400 500 600 TEMPERATURE ( F)

Fi-ure 5-19 Tensile 1Properties for Vogtle Unit 2 Reactor Vessel Weld Mletal esting a 'Specimens from Capsule NV

WNCAP-16382 5-36 5-36 WCAP-1 6382 Specimen BL-7 Tested at 750 F Specimen BL-8 Tested at 150'F Specimen BL-9 Tested at 550'F Figure 5-20 Fractured Tensile Specimens from Vogtle Unit 2 Reactor Vessel Lowver Shell Plate B8628-1 (Longitudinal Orientation)

Testing of Specimens from Capsule W

IL-WCAP-16382 5-37 5-37 WCAP- 16382 Specimen BT-7 Tested at 750 F Specimen BT-8 Tested at 150'F Specimen BT-9 Tested at 5500 F Figure 5-21 Fractured Tensile Specimens fronm Nogtle Unit 2 Reactor Vessel Lower Shell Plate B8628-1 (Transvwerse Orienstationi)

Testing of Specimens from Capsule W

WCAP- 16382 5-38 Specimen BW-7 Tested at 75'F Specimen BW-8 Tested at 1750 F Specimen BW-9 Tested at 550'F Figure 5-22 Fractured Tensile Specimens from Vogtle Unit 2 Reactor Vessel Weld Metal Testing of Specimens from Capsule '"

it WCAP- 16382 5-39 VOGTLE UNIT #2

'W CAPSULE 100 80

'i 60 (n

w 1-U, 40 BL-7 75 F 20 0

0 05 0.1 0.15 0.2 0.25 0.3 STRAIN. INAN VOGTLE UNIT a2

• W CAPSULE 100 80 60 40 BL-8 150 F 20 o I-- . - -- .--- .- .

0 005 01 0.15 02 025 0.3 STRAIN. IN/IN VOGTLE UNIT H2 W" CAPSULE 100 80 (iI 60 U)

In .0 BL -9 550 F O -. - -. - - --- ___ _.

G OS 0' O'5 0.2 0.25 03 ST!:AN IN.AN Figure 5-23 Enineerimy Stress-Strain Curves ror Lower Shell Plate 118628.- Tensile Specimens 111,7, lRL8 and 1B9 (Lon-irtudifal( Oriecntation)

Tesclill or sccilliells rrolil Capqsilk \W

WCAP- I 6382 5-40 VOGTLE UNIT F 2

'W' CAPSULE 100 fo 40 BT-7 75 F 20 0

0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. INAN VOGTLE UNIT f2

'W' CAPSULE 100 8o S

60 40 BT-8 150 F 20 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, IN/IN VOGTLE UNIT #2 W CAPSULE 100 eo rh 80 c26 60 40 BT-9 550 F 20 0 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN, INIIN Figure 5-24 Engineering Stress-Strain Curves for Lower Shell Plate B8628-1 Tensile Specimens BT7, BT8 and BT9 (Transverse Orientation)

Testing of Specimens from Capsule W

12_

WCAxP- 16382 5-41 WCAP- 16382 5-4' VOGTLE UNIT #2

• W CAPSULE 100 60 60 40 20 0

a 0.05 0.1 0.15 0.2 0.25 0.3 STRAIN. NIN VOGTLE UNIT X 2 W CAPSULE i

4 I

0 0.05 0.1 0.15 02 025 03 STRAIN. IN/IN VOGTLE UNIT #2

'W CAPSULE BW.9 550 F 0 0.05 0.1 0.15 02 025 0.3 STRAIN. INIIN Figure 5-25 Engineering Stress-Strain Curves for Weld Metal Tensile Specimens BW7, BW8 and BW9 Testing of Specimens from Capsule W

WCAP- 16382 6-1 6 RADIATION ANALYSIS AND NEUTRON DOSIMETRY

6.1 INTRODUCTION

This section describes a discrete ordinates Sn, transport analysis performed for the Alvin NV. Vogtle Unit 2 reactor to determine the neutron radiation environment within the reactor pressure vessel and surveillance capsules. In this analysis, fast neutron exposure parameters in terms of fast neutron fluence (E > 1.0 MeV) and iron atom displacements (dpa) were established on a plant and fuel cycle specific basis. An evaluation of the most recent dosimetry sensor set from Capsule W, withdrawn at the end of the tenth plant operating cycle, is provided. In addition, to provide an up-to-date data base applicable to the Alvin NV. Vogtle Unit 2 reactor, the sensor sets from the previously withdrawn capsules (U, Y,and X) were re-analyzed using the current dosimetry evaluation methodology. These dosimetry updates are presented in Appendix A of this report. Comparisons of the results from these dosimetry evaluations with the analytical predictions served to validate the plant specific neutron transport calculations. These validated calculations subsequently formed the basis for providing projections of the neutron exposure of the reactor pressure vessel for operating periods extending to 54 Effective Full Power Years (EFPY).

The use of fast neutron fluence (E > 1.0 MeV) to correlate measured material property changes to the neutron exposure of the material has traditionally been accepted for the development of damage trend curves as well as for the implementation of trend curve data to assess the condition of the vessel. In recent years, however, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves and improved accuracy in the evaluation of damage gradients through the reactor vessel wall.

Because of this potential shift away from a threshold fluence toward an energy dependent damage function for data correlation, ASTM Standard Practice E853, "Analysis and Interpretation of Light-Water Reactor Surveillance Results," recommends reporting displacements per iron atom (dpa) along with fluence (E > 1.0 MeV) to provide a database for future reference. The energy dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693, "Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements per Atom." The application of the dpa parameter to the assessment of embrittlement gradients through the thickness of the reactor vessel wall has already been promulgated in Revision 2 to Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials."

All of the calculations and dosimetry evaluations described in this section and in Appendix A were based on the latest available nuclear cross-section data derived from ENDF/B-VI and made use of the latest available calculational tools. Furthermore, the neutron transport and dosimetry evaluation methodologies follow the guidance and meet the requirements of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence.t 71 Additionally, the methods used to develop the calculated pressure vessel fluence are consistent with the NRC approved methodology described in WCAP-14040-NP-A, 'Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," May 2004.1t8]

Radiation Analysis and Neutron Dosimetry

WVCAP- 16382 6-2 6.2 DISCRETE ORDINATES ANALYSIS A plan view of the Alvin NV. Vfogtle Unit 2 reactor Geometry at the core midplane isshown in Figure 4-1.

Six irradiation capsules attached to the neutron pad are included in the reactor design that constitutes the reactor vessel surveillance program. The capsules are located at azimuthal angles of 58.50, 61", 121.50, 238.50, 2410, and 301.50 as shown in Figure 4-1. These full core positions correspond to the following octant symmetric locations represented in Figure 6-1: 290 from the core cardinal axes (for the 610 and 2410 dual surveillance capsule holder locations) and 31.5° from the core cardinal axes (for the 121.50 and 301.50 single surveillance capsule holder locations, and for the 58.50 and the 238.50 dual surveillance capsule holder locations). The stainless steel specimen containers are 1.182-inch by I -inch and are approximately 56 inches in height. The containers are positioned axially such that the test specimens are centered on the core midjlane, thus spanning the central 5 feet of the 12-foot high reactor core.

From aneutronic standpoint, the surveillance capsules and associated support structures are significant.

The presence of these materials has a marked effect on both the spatial distribution of neutron flux and the neutron energy spectrum in the water annulus between the neutron pads and the reactor vessel. In order to determine the neutron environment at the test specimen location, the capsules themselves must he included in the analytical model.

In performing the fast neutron exposure evaluations for the Alvin W. Vogtle Unit 2 reactor vessel and surveillance capsules, a series of fuel cycle specific forward transport calculations were carried out using the following three-dimensional flux synthesis technique:

b(r,9,z) = 5(r,9)* 0(r,z) where 0(r,O.z) is the synthesized three-dimensional neutron flux distribution, ¢(rO) is the transport solution in rO geometry, O(r,z) is the two-dimensional solution for a cylindrical reactor model using the acitual axial core power distribution, and¢(r) is the one-dimensional solution for a cylindrical reactor model using the same source per unit height as that used in the r,O two-dimensional calculation. This synthesis procedure was carried out for each operating cycle at Alvin W. Vogtle Unit 2.

For the Alvin WV. Vogtle Unit 2 transport calculations, the rO models depicted in Figure 6-1 were utilized since, with the exception of the neutron pads, the reactor is octant symmetric. These rO models include the core, the reactor internals, the neutron pads - including explicit representations of octants not containing surveillance capsules and octants with surveillance capsules at 290 and 31.50, the pressure vessel cladding and vessel wall, the insulation external to the pressure vessel, and the primary biological shield wall. These models formed the basis for the calculated results and enabled making comparisons to the surveillance capsule dosimetry evaluations. In developing these analytical models, nominal design dimensions were employed for the various structural components. Likewise, water temperatures, and hence, coolant densities in the reactor core and downcomer regions of the reactor were taken to be representative of full power operating conditions. The coolant densities were treated on a fuel cycle specific basis. The reactor core itself was treated as a homogeneous mixture of fuel, cladding, water, and miscellaneous core structures such as fuel assembly grids, guide tubes, et cetera. The geometric mesh description of the rO reactor models consisted of 183 radial by 99 azimuthal intervals. Mesh sizes were Radiation Analysis and Neutron Dosimetry

WCAP-1I6f382 (l-3 XVCAP- 16382 6-3 chosen to assure that proper convergence of the inner iterations was achie'ved on a pointwise basis. The pointwise inner iteration flux convergence criterion utilized in the r,0 calculations was set at a value of 0.001.

The r,z model used for the Alvin W. Vogtle Unit 2 calculations is shown in Figure 6-2 and extends radially from the centerline of the reactor core out to a location interior to the primary biological shield and over an axial span from an elevation below the lower core plate to above the upper core plate. As in the case of the rO models, nominal design dimensions and full power coolant densities were employed in the calculations. In this case, the homogenous core region was treated as an equivalent cylinder with a volume equal to that of the active core zone. The stainless steel former plates located between the core baffle and core barrel regions were also explicitly included in the model. The r.z geometric mesh description of these reactor models consisted of 153 radial by 188 axial intervals. As in the case of the r,0 calculations, mesh sizes were chosen to assure that proper convergence of the inner iterations was achieved on a point-wise basis. The point-wise inner iteration flux convergence criterion utilized in the r,z calculations was also set at a value of 0.001.

The one-dimensional radial models used in the synthesis procedure consisted of the same 153 radial mesh intervals included in the r,z models. Thus, radial synthesis factors could be determined on a meshwise basis throughout the entire geometry.

The core power distributions used in the plant specific transport analysis were provided by Southern Nuclear Co and the Nuclear Fuels Division of Westinghouse. for each of the first eleven fuel cycles at Alvin NV. Vogtle Unit 2. Specifically, the data utilized included cycle dependent fuel assembly initial enrichments, burn-ups, and axial power distributions. This information was used to develop spatial and energy dependent core source distributions averaged over each individual fuel cycle. Therefore, the results from the neutron transport calculations provided data in terms of fuel cycle averaged neutron flux, which-h when multiplied by the appropriate fuel cycle length, generated the incremental fast neutron exposure for each fuel cycle. In constructing these core source distributions, the energy distribution of the source was based on an appropriate fission split for uranium and plutonium isotopes based on the initial enrichment and burn-up history of individual fuel assemblies. From these assembly dependent fission splits, composite values of energy release per fission, neutron yield per fission, and fission spectrum were determined.

All of the transport calculations supporting this analysis were carried out using the DORT discrete ordinates code Version 3.11191 and the BUGLE-96 cross-section library.' 2 01 The BUGLE-96 library provides a 67 group coupled neutron-gamma ray cross-section data set produced specifically for light water reactor (LWR) applications. In these analyses, anisotropic scattering was treated with a P5 legendre expansion and angular discretization was modeled with an S16 order of angular quadrature.

Energy and space dependent core power distributions, as well as system operating temperatures, were treated on a fuel cycle specific basis.

Selected results from the neutron transport analyses are provided in Tables 6-1 through 6-6. In Table 6-1, the calculated exposure rates and integrated exposures, expressed in terms of both neutron fluence (E > 1.0 MeV) and dpa, are given at the radial and azimuthal center of the octant symmetric surveillance capsule positions, i.e., for the 290 dual capsule, 31.50 dual capsule, and 31.50 single capsule. These results, representative of the axial midplane of the active core, establish the calculated exposure of the Radiation Analysis and Neutron Dosimetry

WCAP- 16382 6 -4 surveillance capsules withdrawn to date as well as projected into the future. Similar information is provided in Table 6-2 for the reactor vessel inner radius at four azimuthal locations. The vessel data given in Table 6-2 were taken at the cladibase metal interface, and thus, represent maximum calculated exposure levels on the vessel.

Both calculated fluence (E > 1.0 MeV) and dpa data are provided in Table 6-1 and Table 6-2. These data tabulations include both plant and fuel cycle specific calculated neutron exposures at the end of the tenth fuel cycle as well as future projections to 20, 24, 32, 40, 48, and 54 EFPY. The calculations for Cycle 4 account for an uprate from 3411 MWt to 3565 MWt. The projections were based on tile assumption that the core power distributions and associated plant operating characteristics from Cycle I I were representative of future plant operation. The future projections are also based on the current reactor power level of 3565 MWt.

Radial gradient information applicable to fast (E > 1.0 MeV) neutron fluence and dpa are given in Tables 6-3 and 64, respectively. The data, based on the cumulative integrated exposures from Cycles I through 10, are presented on a relative basis for each exposure parameter at several azimuthal locations.

Exposure distributions through the vessel wall may be obtained by multiplying the calculated exposure at the vessel inner radius by the gradient data listed in Tables 6-3 and 6-4.

The calculated fast neutron exposures for the four surveillance capsules withdrawn from the Alvin W.

Vogtle Unit 2 reactor are provided in Table 6-5. These assigned neutron exposure levels are based on the plant and fuel cycle specific neutron transport calculations performed for the Alvin NV. Vogtle Unit 2 reactor.

Updated lead factors for the Alvin W. Vogtle Unit 2 surveillance capsules are provided in Table 6-6. The capsule lead factor is defined as the ratio of the calculated fluence (E > 1.0 MeV) at the geometric center of the surveillance capsule to the corresponding maximum calculated fluence at the pressure vessel clad/base metal interface. In Table 6-6, the lead factors for capsules that have been withdrawn from the reactor (U, Y,X and W) were based on the calculated fluence values for the irradiation period corresponding to the time of withdrawal for the individual capsules. For the capsules remaining in the reactor (V and Z), the lead factor corresponds to the calculated fluence values at the end of Cycle I I, the last completed fuel cycle forAlvin W. Vogtle Unit 2.

6.3 NEUTRON DOSINIETRY The validity of the calculated neutron exposures previously reported in Section 6.2 is demonstrated by a direct comparison against the measured sensor reaction rates and via a least squares evaluation performed for each of the capsule dosimetry sets. However, since the neutron dosimetry measurement data merely serves to validate the calculated results, only the direct comparison of measured-to-calculated results for the most recent surveillance capsule removed from service is provided in this section of the report. For completeness, the assessment of all measured dosimetry removed to date, based on both direct and least squares evaluation comparisons, is documented in Appendix A.

Radiation Analysis and Neutron Dosimetry

WCAP-16382 6-5 6-5 WCAP-16382 The direct comparison of measured versus calculated fast neutron threshold reaction rates for the sensors from Capsule W, that was withdrawn from Alvin W. Vogtle Unit 2 at the end of the tenth fuel cycle, is summarized below.

Reaction Rates (rps/atom) M/C Reaction Measured Calculated Ratio 63Cu(n,a)6WCo 4.21 E-17 3.94E-17 1.07 14Fe(np)4 Mn 4.15E-15 4.29E-15 0.97 5

"Ni(n,p)"Co 6.11E-15 6.00E-15 1.02 238U(n p)137Cs (Cd) 2.70E-14 2.27E-14 1.19 237Np(nf) 37Cs (Cd) 2.35E-13 2.21E-13 1.06 Average: 1.06

% Standard Deviation: 8.2 The measured-to-calculated (M/C) reaction rate ratios for the Capsule W threshold reactions range from 0.97 to 1.19, and the average M/C ratio is 1.06 +/- 8.2% (Ic). This direct comparison falls well within the

+/- 20% criterion specified in Regulatory Guide 1.190; furthermore, it is consistent with the full set of comparisons given in Appendix A for all measured dosimetry removed to date from the Alvin W. Vogtle Unit 2 reactor. These comparisons validate the current analytical results described in Section 6.2; therefore, the calculations are deemed applicable for Alvin W. Vogtle Unit 2.

6.4 CALCULATIONAL UNCERTAINTIES The uncertainty associated with the calculated neutron exposure of the Alvin W.Vogtle Unit 2 surveillance capsule and reactor pressure vessel is based on the recommended approach provided in Regulatory Guide 1.190. In particular, the qualification of the methodology was carried out in the following four stages:

I - Comparison of calculations with benchmark measurements from the Pool Critical Assembly (PCA) simulator at the Oak Ridge National Laboratory (ORNL).

2 - Comparisons of calculations with surveillance capsule and reactor cavity measurements from the H. B. Robinson power reactor benchmark experiment.

3 - An analytical sensitivity study addressing the uncertainty components resulting from important input parameters applicable to the plant specific transport calculations used in the neutron exposure assessments.

4 - Comparisons of the plant specific calculations with all available dosimetry results from the Alvin W. Vogtle Unit 2 surveillance program.

Radiation Analysis and Neutron Dosimetry

WCAP- I 63RS2 6-6 XVCAP- 16382 6-6 The first phase of the methods qualification (PCA comparisons) addressed the adequacy of basic transport calculation and dosimetry evaluation techniques and associated cross-sections. This phase, however, did not test the accuracy of commercial core neutron source calculations nor did it address uncertainties in operational or geometric variables that impact power reactor calculations. The second phase of the qualification (H. B. Robinson comparisons) addressed uncertainties in these additional areas that are primarily methods related and would tend to apply generically to all fast neutron exposure evaluations. The third phase of the qualification (analytical sensitivity study) identified the potential uncertainties introduced into the overall evaluation due to calculational methods approximations as well as to a lack of knowledge relative to various plant specific input parameters. The overall calculational uncertainty applicable to the Alvin NV. Vogtle Unit 2 analysis was established from results of these three phases of the methods qualification.

The fourth phase of the uncertainty assessment (comparisons with Alvin W. Vogtle Unit 2 measurements) was used solely to demonstrate the validity of the transport calculations and to confirm the uncertainty estimates associated with the analytical results. The comparison was used only as a check and was not used in any way to modify the calculated surveillance capsule and pressure vessel neutron exposures previously described in Section 6.2. As such, the validation of the Alvin NV. Vogtle Unit 2 analytical model based on the measured plant dosimetry is completely described in Appendix A.

The following summarizes the uncertainties developed from the first three phases of the methodology qualification. Additional information pertinent to these evaluations is provided in Reference 18.

Capsule Vessel IR PCA Comparisons 3% 3%

H. B. Robinson Comparisons 3% 3%

Analytical Sensitivity Studies 10% 11%

Additional Uncertainty for Factors not Explicitly Evaluated 5% 5%

Net Calculational Uncertainty 12% 13%

The net calculational uncertainty was determined by combining the individual components in quadrature.

Therefore, the resultant uncertainty was treated as random and no systematic bias was applied to the analytical results.

The plant specific measurement comparisons described in Appendix A support these uncertainty assessments for Alvin W. Vogtle Unit 2.

Radiation Analysis and Neutron Dosimctry

WN'CAP- 16382 6-7 Figure 6-1 Alvin W. Vogtle Unit 2 rO Reactor Geometry with a 12.50 Neutron Pad at the Core Midplane 240-1 80 Mn x 120 60O-0 - I 0 75 150 225 300 R Axis (cm)

Radiation Analysis and Neutron Dosimetry

WCAP-1l6382 6-X WCAP- 16382 6-8 Figure 6-1 (continued)

Alvin NV. Vogtle Unit 2 rO Reactor Geometry with a 20.00 Neutron Pad at the Core Midplane 240 -

1 80 VI) 0-0 75 150 225 300 R Axis (cm)

Radiation Analysis and Neutron Dosimetry

WCAP-1I6382 6-99 6-X\'CAP- 16382 Figure 6-1 (continued)

Alvin NV. Vogtle Unit 2 rO Reactor Geometry with a 22.50 Neutron Pad at the Core Midplane 240-1 80

. 1 20 60 0-0 75 150 225 300 R Axis (cm)

Radiation Analysis and Neutron Dosimetry

WCAP- 16382 6-10 Figure 6-2 Alvin WV. Votlde Unit 2 rz Reactor Geometry with Neutron Pad 1 - T -. n- r~

300 -

200 100 E 0-r-gJ

.Ix

- 10 0-It

-200 -

-300 -

________________________ .5.

-400 _

I I. I.I--- I- I -I - I I I I I I 0 75 150 225 300 R Axis (cm)

Radiation Analysis and Ncutron Dosimetry

WCAP- 16382 6-11 II Table 6-1 Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center Cumulative Cumulative Neutron Flux (E > 1.0 AleN')

Cycle Irradiation Irradiation In/cmn2sl Length Time Time Dual Dual Single Cycle [EFPS] lEFPS] IEFPYI 29° 31.50 31.50 I 3.78E+07 3.78E+07 1.20 8.78E+ l 0 9.43E+ l0 9.34E+ 10 2 3.86E+07 7.64E+07 2.42 7.30E+ lIO 7.97E+10 7.89E+ l0 3 4.13E+07 1.I8E+08 3.73 6.32E+10 6.82E+ I0 6.75E+ l O 4 3.96E+07 1.57E+08 4.98 6.08E+ 10 6.63E+ l 0 6.57E+ l O 5 4.47E+07 2.02E+08 6.40 5.63E+ l O 6.17E+ l 0 6.11 E+10 6 4.35E+07 2.45E+08 7.78 6.27E+lO 6.79E+ I() 6.73E+ l 0 7 4.38E+07 2.89E+08 9.17 6.52E+10 7.(XE+ l () 7.01E+l()

8 4.43E+07 3.34E+08 10.57 6.53E+ l 0 7.24 E+ l 0 7.17E+ l 0 9 4.46E+07 3.78E+08 11.98 6.52E+ l 0 6.95E+ l 0 6.88E+ l O 10 4.1I E+07 4.19E+08 13.29 6.411E+lO 7.1(E+I() 7.04E+ I()

Future 4.11 E+07 4.60E+08 14.59 6.04E+ l 0 7.1 ]E+l0 7.04E+ l ()

Future 1.71 E+08 20.00 6.64E+ l0 7.1 IE+I() 7.04E+ l 0 Future 1.26E+08 24.00 6.64E+I 0 7.1 IE+l() 7.04E+ I0 Future 2.52E+08 32.00 6.64E+ I0 7.1 1E+lO 7.04E+ I()

Future 2.52E+08 40.00 6.64E+ l 0 7.1 ]E+I0() 7.04E+ l0 Futurc 2.52E+08 48.00 6.(4E+ I() 7.1 lE+l0( 7.04E+ l 0 Future 1.89E+08 54.00 6.64E+ lO 7.1 IE+l0 7.04E+I0 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

Radiation Analysis and Neutron Dosimetry

'I WCAP- 16382 6-12 Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center Cumulative Cumulative Neutron Fluence (E > 1.0 MeV)

Cycle Irradiation Irradiation [n/cm 2 J Length Time Time Dual Dual Single Cycle [EFPS] [EFPS] [EFPY] 290 31.50 31.50

__ 3.78E+07 3.78E+07 1.20 3.32E+ 18 3.56E+ 18 3.53E+18 2 3.86E+07 7.64E+07 2.42 6.14E+18 6.64E+18 6.58E+ 18 3 4.13E+07 1.18E+08 3.73 8.75E+ 18 9.45E+ 18 9.36E+ 18 4 3.96E+07 1.57E+08 4.98 1.12E+19 1.21E+19 1.20E+ 19 5 4.47E+07 2.02E+08 6.40 1.37E+ 19 1.48E+19 1.47E+ 19 6 4.35E+07 2.45E+08 7.78 1.64E+19 1.78E+19 I.76E+ 19 7 4.38E+07 2.89E+08 9.17 1.93E+19 2.09E+ 19 2.07E+ 19 8 4.43E+07 3.34E+08 10.57 2.22E+ 19 2.41 E+ 19 2.39E+ 19 9 4.46E+07 3.78E+08 11.98 2.51E+19 2.72E+ 19 2.69E+ 19 10 4.11 E+07 4.19E+08 13.29 2.77E+ 19 3.01 E+ 19 2.98E+ 19 11 4.1 I E+07 4.60E+08 14.59 3.04 E+ 19 3.30E+ 19 3.27E+ 19 Future 1.71 E+08 20.00 4.18E+ 19 4.52E+19 4.48E+ 19 Future 1.26E+08 24.00 5.02E+ 19 5.42E+ 19 5.36E+ 19 Future 2.52E+08 32.00 6.69E+ 19 7.21 E+19 7.14E+ 19 Future 2.52E+08 40.00 8.37E+ 19 9.01 E+ 19 8.92E+ 19 Future 2.52E+08 48.00 1.( I E+20 1.08E+20 1.07E+20 Future 1.89E+08 54.00 1.13E+20 1.22E+20 1.20E+20 Note: Neutron exposure values reported for the surveillance capsules are centered at the core rnidplane.

Radiation Analysis and Neutron Dosimetry

WNCAP- 163X2 6-13 WCAP- 16382 6-13 Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation [dpa/s]

Length Time Time Dual Dual Single Cycle [EFPS] [EFPS] [EFPY] 290 31.50 31.50 3.78E+07 3.78E+07 1.20 1.72E- IO 1.84E- 10 1.82E- I0 2 3.86E+07 7.64E+07 2.42 1.42E-10 1.54E-10 1.53E-10 3 4.13E+07 1.18E+08 3.73 1.222- 10 1.32E-10 1.31E-10 4 3.96E+07 1.57E+08 4.98 1.18E-10 1.282-10 1.27E- 10 5 4.47E+07 2.022+08 6.40 1.09E- 10 1.192-10 1.182-10 6 4.35E+07 2.45E+08 7.78 1.222- 10 1.32E-10 1.30E- I0 7 4.38E+07 2.89E+08 9.17 1.262-10 1.372-10 1.36E- 10 8 4.43E+07 3.34E+08 10.57 1.27E-10 1.41E-10 1.392- I0 9 4.46E+07 3.78E+08 11.98 1.27E-10 1.35E-10 1.332- 10 10 4.1 1E+07 4.19E+08 13.29 1.24E- IO 1.38E- I I.37E-1 I0 11 4.11 E+07 4.60E+08 14.59 1.29E-10 I.38E-l0 1.36E-10 Future 1.71 E+08 20.00 1.29E-10 1.38E-10 1.36E-10 Future 1.26E+08 24.00 1.29E- I0 1.382-10 1.36E-10 Future 2.52E+08 32.00 1.29E- 10 1.38E-10 1.36E-10 Future 2.52E+08 40.00 1.29E- 10 1.382-10 1.36E- 10 Future 2.52E+08 48.00 1.29E- 10 1.38E- 10 1.36E- 10 Future 1.89E+08 54.00 1.29E- I0 1.38E-10 1.36E- 10 Note: Neutron exposure values reported for the surveillance capsules are centered at the core midplane.

Radialion Analysis and Neutron Dosimetry

IL_

WCAP- 16382 6-14 WCAP- 16382 6-14 Table 6-1 cont'd Calculated Neutron Exposure Rates And Integrated Exposures At The Surveillance Capsule Center Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation (dpal Length Time Time Dual Dual Single Cycle lEFPS] [EFPS] IEFPY] 290 31.50 31.50 1 3.78E+07 3.78E+07 1.20 6.49E-03 6.97E-03 6.89E-03 2 3.86E+07 7.64E+07 2.42 1.20E-02 1.29E-02 1.28E-02 3 4.13E+07 1.18E+08 3.73 1.70E-02 1.84E-02 1.82E-02 4 3.96E+07 1.57E+08 4.98 2.17E-02 2.35E-02 2.322-02 S 4.47E+07 2.02E+08 6.40 2.66E-02 2.88E-02 2.85E-02 6 4.35E+07 2.45E+08 7.78 3.18E-02 3.45E-02 3.42E-02 7 4.38E+07 2.89E+08 9.17 3.74E-02 4.05E-02 4.01 E-02 8 4.43E+07 3.34E+08 10.57 4.30E-02 4.67E-02 4.63E-02 9 4.46E+07 3.78E+08 11.98 4.86E-02 5.27E-02 5.22E-02 10 4.11 E+07 4.19E+08 13.29 5.37E-02 5.84E-02 5.78E-02 II 4.11 E+07 4.60E+08 14.59 5.902-02 6.41 E-02 6.342-02 Future 1.71 E+08 20.00 8. OE-02 8.76E-02 8.67E-02 Future 1.26E+08 24.00 9.732(-02 1.05E-01 1.04E2-01 Future 2.52E+08 32.00 1.3012-01 1.40E-01 1.38E-01 Future 2.52E+08 40.00 1.62E-01 1.75E-01 1.73E-01 Future 2.52E+08 _ 48.00 1.95E-01 2.09E-01 2.07-01I Future I.89E+08 54.00 2.19E-01 2.35E-01 2.33E-01 Note: Neutron exposure values reported for the surveillance capsules are centered at the core mnidplane.

Radiation Analysis and Neutron Dosimetry

WCAP- 16382 6-15 Table 6-2 Calculated Azimuthal Variation Of Maximum Exposure Rates And Integrated Exposures At The Reactor Vessel Clad/Base Metal Interface Cumulative Cumulativc Neutron Flux (E > 1.0 MeVl)

Cycle Irradiation Irradiation [n/cm 2-s]

Length Time Time Cycle [EFPS] [EFPS] [EFPY] 00 150 300 450 3.78E+07 3.78E+07 1.20 - .311E+10 1.94E+10 2.23E+ 10 2.30E+ 10 2 3.86E+07 7.64E+07 2.42 I.12E+10 1.53E+ 10 1.85E+ I n 1.78E+ 10 3 4.13E+07 1.I 8E+08 3.73 8.95E+09 1.36E+ 10 1.60E+ 10 1.60E+ 10 4 3.96E+07 1.57E+08 4.98 8.39E+09 1.24E+ 10 I.55E+10 l1.58E+10 5 4.47E+07 2.02E+08 6.40 8.45E+09 I.23E+ 10 1.45E+ I0 1.47E+ 10 6 4.35E+07 2.45E+08 7.78 9.69E+09 1.39E+ 10 1.60E+ I0 1.62E+ l0 7 4.38E+07 2.89E+08 9.17 9.50E+09 1.42E+ 10 1.68E+ 10 1.70E+ 10 8 4.43E+07 3.34E+08 10.57 8.85E+09 1.35E+ 10 1.66E+ I( I.84E+ l0 9 4.46E+07 3.78E+08 11.98 9.23E+09 1.40E+ 10 I .64E+10 1.62E+ 10 10 4.1 I E+07 4.19E+08 13.29 9.23E+09 I.34E+ IO I.64E+I0 1.78E+ I0 11 4.11 E+07 4.60E+08 14.59 9.94E+09 1.48E+ 10 1.6XE+ 10 1.66E+ I0 Future 1.71 E+08 20.00 9.94E+09 1.48E+10 1.68E+I() 1.66E+ I0 Future 1.26E+08 24.00 9.94E+09 In 1.48E+10 .68E+ I( 1.66E+ 10 Future 2.52E+08 32.00 9.941E+09 1.48E+ 10 1.68E+ I0 1.66E+ 10 Future 2.5213+08 40.00 9.9413+09 1.48E+10 1.68E+ 10 1.66E+ 10 Future 2.5213+08 48.00 9.94E+09 1.48E+10 1.68E+ I0 1.66E+ lO Future 1.89E+08 54.00 9.94E+09 1.48E+ I ( 1.68E+ I0 1.66E+ (0 Radiation Analysis and Neutron Dosimetry

WCA~P- 16(382 6'l16

\VCAP- 16382 6-16 Table 6-2 cont'd Calculated Azimuthal Variation Of Maximum Exposure Rates And Integrated Exposures At The Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Neutron Fluence (E > 1.0 NleV)

Cycle Irradiation Irradiation [n/cm2 l Length Time Time Cvcle [EFPSI IEFPS] [EFPY1 00 150 300 450 3.78E+07 3.78E+07 1.20 4.93E+ 17 7.31E+17 8.42E+ 17 8.69E+ 17 2 3.86E+07 7.64E+07 2.42 9.26E+ 17 1.32E+18 1.56E+ 18 1.56E+ 18 3 4.13E+07 I. I8E+08 3.73 1.29E+ 18 1.87E+18 2 20E+ 18 2.20E+ 18 4 3.96E+07 1.57E+08 4.98 1.62E+ 18 2.36E+18 2.81 E+ 18 2.83E+ 18 5 4.47E+07 2.02E+08 6.40 1.99E+ 18 2.91 E+ 18 3.46E+ 18 3.48E+ 18 6 4.35E+07 2.45E+08 7.78 2.42E+ 18 3.52E+18 4.15E+ I8 4.19E+ I8 7 4.38E+07 2.89E+08 9.17 2.83E+ 18 4.14E+ 18 4.88E+ 18 4.93E+ 18 8 4.43E+07 3.34E+08 10.57 3.22E+ 18 4.74E+ 18 5.62E+ 18 5.74E+ 18 9 4.46E+07 3.78E+08 11.98 3.63E+ 18 5.36E+ 18 6.35E+18 6.46E+ 18 1O 4.1 I E+07 4.19E+)08 13.29 4.0I E+ 18 5.91 E+ 18 7.02E+ 18 7.20E+ 18 1 4.1 I E+07 4.60E+08 14.59 4.42E+ I 8 6.52E+18 7.70E+ I 8 7.87E+ I8 Future I.71 E+08 20.00 6.10E+18 9.02E+ 18 1.06E+ 19 1.07E+ 19

~uture I.26E+08 24.00 7.35E+ I8 1.09E+ 19 1.27E+ 19 1.28E+ 19 F:uture 2.52E+08 32.00 9.87E+ 18 I.46E+19 1.69E+ 19 1.70E+ 19 Future 2.52E+08 40.00 1.24E+ 19 I.84E+ 19 2.12E+ 19 2.1 IE+19 Future 2.52E3+08 48.00 1.49E+19 2.21E+19 2.54E+ 19 2.53E+ 19 IFulure I.89E+08 54.00 1.68E+19 2.49E+ 19 2.86E+ 19 .85E+ 19 Radiation Analysis and Neutron Dosimetry

WCAI'- 1639X2 6)-17 Table 6-2 cont'd Calculated Azimuthal Variation Of Fast Neutron Exposure Rates And Iron Atom Displacement Rates At The Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Iron Atom Displacement Rate Cycle Irradiation Irradiation [dpa/si Length Time Time Cycle [EFPS] [EFI'S] [EFPYJ 00 I5° 300 450 3.78E+07 3.78E+07 1.20 2.03E-11 2.97E-I 1 3.43E- I1 3.64E- I I 2 3.86E+07 7.642+07 2.42 1.74E-11 2.36E-11 2.85E-I1 2.82E-I I 3 4.13E+07 1.18E+08 3.73 1.39E- I I 2.09E- I1 2.47E- I I 2.52E- I I 4 3.96E+07 1.57E+08 4.98 1.311E-11 1.91 E- 11 2.39E- Il 2.502- I1 5 4.47E+07 2.02E+08 6.40 1.312E- I 1.90E- I I 2.23E- I I 2.322- I I 6 4.35E+07 2.45E+08 7.78 1.511E- 1 2.13E- lI 2.47E-I 1 2.5h6- I1 7 4.38E+07 2.89E+08 9.17 1.48E- I I 2.19E- I1 2.59E- 11 2.69E- I I 8 4.43E+07 3.34E+)08 10.57 1.382-1 I 2.08E- I I 2.56E- I I 2.91' I I 9 4.46E+07 3.78E+08 11.98 1.44E- 11 2.16E- 11 2.52E- lI 2.55E- Il 10 4.11 E+07 4.19E+08 13.29 1.44E- 11 2.06E- 11 2.53E-11 2.X11. I1 l1 4.11 E+07 4.60E+08 14.59 1.55E- Il 2.282- 11 2.59E- I1 2.621.- 11 Future 1.71 E+08 20.00 1.55E-11 2.28E-11 2.59E-I1 2.62h-11 Future 1.26E+08 24.00 1.55E-Il 2.282-11 2.59E-I1 2.62h-11 Future 2.52E2+08 32.00 1.552- 11 2.282- 11 2.592- I1 2.62E-I I Future 2.52E+08 40.00 1.55E- 11 2.282- 11 2.59E- I1 2.621-Il Future 2.52E+08 48.00 1.55E-1 1 2.28E-11 2.59E-Il 2.62E-I I Future 1.892(+08 54.00 1.55E- 11 2.28E- 11 2.59E-Il 2.I21- I Radiation Analysis and Neutron Dosimetry

11 WCAP- 16382 6-18 WCAP.6382 -8 Table 6-2 contd Calculated Azimuthal Variation Of Maximum Exposure Rates And Integrated Exposures At The Reactor Vessel Clad/Base Metal Interface Cumulative Cumulative Iron Atom Displacements Cycle Irradiation Irradiation pd al_

Length Time Time Cycle lEFPS] [EFPS] lEFPY] () 150 300 450 1 3.78E+07 3.78E+07 1.20 7.65E-04 1.12E-03 I.30E-03 1.37E-03 2 3.86E+07 7.64E+07 2.42 1.44E-03 2.04E-03 2.40E-03 2.46E-03 3 4.13E+07 lI.18E+08 3.73 2.OOE-03 2.88E-03 3.39E-03 3.48E-03 4 3.96E+07 1.57E+08 4.98 2.51 E-03 3.64E-03 4.34E-03 4.47E-03 5 4.47E+07 2.02E+08 6.40 3.1 (OE-03 4.48E-03 5.33E-s03 5.50E-03 6 4.35E+07 2.45E+08 7.78 3.75E-03 5.41 E-03 6.40E-03 6.61 E-03 7 4.38E+07 2.89E+08 9.17 4.40E-03 6.37E-03 7.53E-03 7.79E-03 8 4.43E+07 3.34E+08 10.57 5.01 E-03 7.29E-03 8.67E-03 9.07E-03 9 4.46E+07 3.78EE+08 11.98 5.65E-03 8.25E-03 9.79E-03 1.02E-02 10 4.11 E+07 4.19E+08 13.29 6.24E-03 9.1OE-03 I.08E-02 I. 14E-02 I1 4.11 E+07 4.60E+08 14.59 6.87E-03 I.()OE-02 1.19E-02 1.24E-02 Future 1.71 E+08 20.00 9.49E-03 1.39E-02 1.63E-02 1.69E-02 Future 1.26E+08 24.0) 1.14E-02 1.68E-02 1.95E-02 2.02E-02 Future 2.52E+08 32.00 L.53E-02 2.25E-02 2.61 E-02 2.68E-02 Future 2.52E+08 40.00 1..93E-02 2.83E-02 3.26E-02 3.344E-02 Future 2.52E+08 48.00 2.32'E-02 3.40E-02 3.92E-02 4.00E-02 Future 1.89E+08 54.00 2.61 E-02 3.831E-02 4.4 1E-02 4.49E-02 Radiation Analysis and Neutron Dosimetry

WCAP-1638B2 6-19 WCAP-1 6382 6-19

- Table 6-3 Relative Radial Distribution Of Neutron Fluence (E > 1.0 MeV)

Within The Reactor Vessel Wall RADIUS AZIMUTHAL ANGLE (cm) 00 150 300 450 220.11 1.000 1.000 1.000 1.000 225.59 0.571 0.566 0.561 0.557 231.06 0.282 0.277 0.272 0.269 236.54 0.134 0.130 0.127 0.125 242.01 0.064 0.059 0.057 0.056 Note: Base Metal Inner Radius = 220.11 cm Base Metal 1/4T = 225.59 cm Base Metal 1/2T = 231.06 cm Base Metal 3/4T = 236.54 cm Base Metal Outer Radius = 242.01 cm Table 6-4 Relative Radial Distribution Of Iron Atom Displacements (dpa)

Within The Reactor Vessel Wall RADIUS AZIMUTHAL ANGLE (cm) 00 150 300 .450 220.11 1.000 1.000 1.000 1.000 225.59 0.642 0.637 0.635 0.644 231.06 0.389 0.381 0.381 0.392 236.54 0.236 0.226 0.227 0.234 242.01 0.141 0.127 0.127 0.130 Note: Base Metal Inner Radius = 220.11 cm Base Metal 1I4T = 225.59 cm Base Metal 1/2T = 231.06 cm Base Metal 3/4T = 236.54 cm Base Metal Outer Radius = 242.01 cm Radiation Analysis and Neutron Dosimetry

It WCAP- 16382 6-20 Table 6-5 Calculated Fast Neutron Exposure of Surveillance Capsules Withdrawn from Alvin NV. Vogtle Unit 2 Irradiation Time Fluence (E > 1.0 MeV) Iron Displacements Capsule [EFPY1 I [n/cm 2 l [dpal U 1.20 3.56E+ 18 6.97E-03 Y 4.98 1.12E+19 2.17E-02 X 7.78 1.78E+19 3.45E-02 W 13.29 2.98E+ 19 5.78E-02 Table 6-6 Calculated Surveillance Capsule Lead Factors Capsule ID And Location Status Lead Factor U (31.5° Dual) Withdrawn EOC 1 4.10 Y (29.00 Dual) Withdrawn EOC 4 3.95 X (31.50 Dual) Withdrawn EOC 6 4.25 W (31.50 Single) Withdrawn EOC 10 4.14 V (29.00 Dual) In Reactor 3.86 Z (31.5° Single) In Reactor 4.16 Note: Lead factors for capsules remaining in the reactor are based on cycle specific exposure calculations through the last completed fuel cycle, i.e., Cycle I 1.

Radiation Analysis and Neutron Dosimetry

WCAP-16382 . .. 7-1 7 SURVEILLANCE CAPSULE REMOVAL SCHEDULE The following surveillance capsule removal schedule meets the requirements of ASTM El 85-82 and is recommended for future capsules to be removed from the Vogtle Unit 2 reactor vessel. This recommended removal schedule is applicable to 36 EFPY of operation.

Table 7-1 Vogtle Unit 2 Reactor Vessel Surveillance Capsule Withdrawal Schedule Removal Time Fluence Capsule Location Lead Factor(') (EFPY)(b) (n/cm 2,E>1.O MeV)(t' U 58.50 4.10 1.20 3.56 x 10 (c)

Y 2410 3.95 4.98 1.12 x 10'9 (c)

X 238.50 4.25 7.78 1.78 x 10'9 (c)

W 121.50 4.14 13.29 2.98 x 1l'9 (c, d)

Z 301.50 4.16 17 (Standby) 3.82 x 10'9 (e)

V 610 3.86 Standby (f) (f)

Notes:

(a) Updated in Capsule W dosimetry analysis.

(b) Effective Full Power Years (EFPY) from plant startup.

(c) Plant specific evaluation.

(d) This capsule was withdrawn at a fluence not less than once or greater than twice the peak EOL fluence for a standard license term of 40 years (36 EFPY). In addition, this capsule was withdrawn at a fluence not less than once or greater than twice the peak EOL fluence for an additional 20-year license renewal term to 60 years (54 EFPY).

(e) This projected fluence is not less than once or greater than twice the peak EOL fluence for an additional 20-year license renewal term to 80 years.

(f) This capsule will reach an EOL fluence for an additional 20-year license renewal term to 80 years at 18.3 EFPY.

Surveillance Capsule Removal Schedule

WCAP- 16382 X-l 8 REFERENCES

1. Regulatory Guide 1.99, Revision 2, RadiationEmnbriztleinent of Reactor Vessel Materials, U.S. Nuclear Regulatory Commission, May, 1988.

2. Code of Federal Regulations, I OCFR50, Appendix G. FractureToughness Requirements, and Appendix H, Reactor Vessel MaterialSurveillance Programn Requirements, U.S. Nuclear Regulatory Commission, Washington, D.C.

3. WCAP- 11381, "Georgia Power Company Alvin IV Viogtle Unit No. 2 Reactor Vessel Radiation Surveillance Program", L. R. Singer, April, 1986.

4. WCAP- 13007, "Analysis of Capsule U From the Georgia Power Company Vogtle Electric Generating Plant Unit 2 Reactor Vessel Radiation Surveillance Program", Ed Terek, et.al, August, 1991.

5. WCAP-14532, "Analysis of Capsule Y From the Georgia Power Company Vogtle Electric Generating Plant Unit 2 Reactor Vessel Radiation Surveillance Program", P.A. Grendys, et. al, February 1996.

6. WCAP- 15 159, "Analysis of Capsule X From the Southern Nuclear Vogtle Electric Generating Plant Unit 2 Reactor Vessel Radiation Surveillance Program", T.J. Laubham, et.al., March 1999.

7. Section XI of the ASME Boiler and Pressure Vessel Code, Appendix G, FractureToughness CriteriaforProtectionAgainst Failure.

8. ASTM E 185-82, StandardPracticeforConducting Surveillance Testsfor Light- Water Cooled Nuclear Power Reactor Vessels, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA.

9. Procedure RMF 8402, Sunreillance Capsule Testing Program, Revision 2.

10. Procedure RMF 8102, Tensile Testing, Revision 3.

11. Procedure RMF 8103, Charpy Impact Testing, Revision 2.

12. Procedure RMF 8804, Opening of Westinghouse Surveillance Capsules, Revision 2.

13. ASTM E23-02a, StandardTest Methodfor Notched Bar Impact Testing of Metallic Materials, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 2002.

14. ASTM A370-03a, Standard Test Methods and DefinitionsforMechanical Testing of Steel Products, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 2003.

References

WCAP-16382 8-2 8-2 WCAP-1 6382

15. ASTM E8-04, StandardTest Methods for Tension Testing of Metallic Materials,in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 2004.

16. ASTM E21-03 a, Standard Test Methodsfor Elevated Temperature Tension Tests ofMetallic Materials, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA, 2003.

17. Regulatory Guide RG-1.190, Calculationaland Dosimetry Methodsfor DeterminingPressure Vessel Neutron Fluence, U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 2001.

18. WCAP- 14040-NP-A, Revision 4, Methodology Used to Develop Cold OverpressureMitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, May 2004.16.RSICC Computer Code Collection CCC-650, "DOORS 3.1, One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System, Version 3.1 ",August 1996.

19. RSICC Computer Code Collection CCC-650, DOORS 3.1, One, Two- and Three-Dimensional Discrete OrdinatesNeutron/Photon Transport Code System, August 1996.

20. RSIC Data Library Collection DLC-1 85, "BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications," March 1996.

21. ASTM E208, StandardTest Methodfor ConductingDrop-Weight Test to Determine Nil-Ductility Transition Temperature ofFerriticSteels, in ASTM Standards, Section 3, American Society for Testing and Materials, Philadelphia, PA.

References

WCAP-16382 A-0 APPENDIX A VALIDATION OF THE RADIATION TRANSPORT MODELS BASED ON NEUTRON DOSIMETRY MEASUREMENTS Appendix A

WCAP-16382 A-l WCAP-1 6382 A-I A.1 Neutron Dosimetry Comparisons of measured dosimetry results to both the calculated and least squares adjusted values for all surveillance capsules withdrawn from service to date at Alvin W. Vogtle Unit 2 are described herein.

The sensor sets from these capsules have been analyzed in accordance with the current dosimetry evaluation methodology described in Regulatory Guide l.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence.[A-1 One of the main purposes for presenting this material is to demonstrate that the overall measurements agree with the calculated and least squares adjusted values to within +/- 20% as specified by Regulatory Guide 1.190, thus serving to validate the calculated neutron exposures previously reported in Section 6.2 of this report. This information may also be useful in the future, in particular, as least squares adjustment techniques become accepted in the regulatory environment.

A.1.1 Sensor Reaction Rate Determinations In this section, the results of the evaluations of the four neutron sensor sets withdrawn to date as part of the Alvin W. Vogtle Unit 2 Reactor Vessel Materials Surveillance Program are presented. The capsule designation, location within the reactor, and time of withdrawal of each of these dosimetry sets were as follows:

Azimuthal Withdrawal Irradiation Capsule ID Location Time Time IEFPYI U 31.50 Dual End of Cycle 1 1.20 Y 29.0° Dual End of Cycle 4 4.98 X 31.5° Dual End of Cycle 6 7.78 W 31.5° Single End of Cycle 10 13.29 The azimuthal locations included in the above tabulation represent the first octant equivalent azimuthal angle of the geometric center of the respective surveillance capsules.

The passive neutron sensors included in the evaluations of Surveillance Capsules U, Y, V, and X are summarized as follows:

• The cobalt-aluminum measurements for this plant include both bare wire and cadmium-covered sensors.

Appendix A

WCAP-1 6382 A-2 WCAP-l 6382 A-2 Since all of the dosimetry monitors were accommodated within the dosimeter block centered at the radial, azimuthal, and axial center of the material test specimen array, gradient corrections were not required for these reaction rates. Pertinent physical and nuclear characteristics of the passive neutron sensors are listed in Table A-1.

The use of passive monitors such as those listed above does not yield a direct measure of the energy dependent neutron flux at the point of interest. Rather, the activation or fission process is a measure of the integrated effect that the time and energy dependent neutron flux has on the target material over the course of the irradiation period. An accurate assessment of the average neutron flux level incident on the various monitors may be derived from the activation measurements only if the irradiation parameters are well known. In particular, the following variables are of interest:

• the measured specific activity of each monitor,

• the physical characteristics of each monitor,

• the operating history of the reactor,

• the energy response of each monitor, and

• the neutron energy spectrum at the monitor location.

Results from the radiometric counting of the neutron sensors from Capsule U, Y,and X are documented in Reference A-2, A-5, and A-6. The radiometric counting of the sensors from Capsule W was carried out by Pace Analytical Services, Inc., located at the Westinghouse Waltz Mill Site. In all cases, the radiometric counting followed established ASTM procedures. Following sample preparation and weighing, the specific activity of each sensor was determined by means of a high-resolution gamma spectrometer. For the copper, iron, nickel, and cobalt-aluminum sensors, these analyses were performed by direct counting of each of the individual samples. In the case of the uranium and neptunium fission sensors, the analyses were carried out by direct counting preceded by dissolution and chemical separation of cesium from the sensor material.

The irradiation history of the reactor over the irradiation periods experienced by Capsules U, Y,X, and W was based on the monthly power generation of Alvin W.Vogtle Unit 2 from initial reactor criticality through the end of the dosimetry evaluation period. For the sensor sets utilized in the surveillance capsules, the half-lives of the product isotopes are long enough that a monthly histogram describing reactor operation has proven to be an adequate representation for use in radioactive decay corrections for the reactions of interest in the exposure evaluations. The irradiation history applicable to Capsules U, Y, X, and W is given in Table A-2.

Having the measured specific activities, the physical characteristics of the sensors, and the operating history of the reactor, reaction rates referenced to full-power operation were determined from the following equation:

R= A No F Y E pi Cj [I - e"] [eAh]

Prep Appendix A

WCAP-16382 A-3 A-3 WCAP-16382 where:

R = Reaction rate averaged over the irradiation period and referenced to operation at a core power level of Prf (rps/nucleus).

A Measured specific activity (dps/gm).

No Number of target element atoms per gram of sensor.

F Weight fraction of the target isotope in the sensor material.

Y Number of product atoms produced per reaction.

Pj Average core power level during irradiation period j (MW).

P,,f = Maximum or reference power level of the reactor (MW).

Cj Calculated ratio of c(E > 1.0 MeV) during irradiation period j to the time weighted average 4(E > 1.0 MeV) over the entire irradiation period.

X Decay constant of the product isotope (1/sec).

tj = Length of irradiation period j (sec).

td = Decay time following irradiation period j (sec).

and the summation is carried out over the total number of monthly intervals comprising the irradiation period.

In the equation describing the reaction rate calculation, the ratio [Pj]/[Pref] accounts for month-by-month variation of reactor core power level within any given fuel cycle as well as over multiple fuel cycles. The ratio Cj, which was calculated for each fuel cycle using the transport methodology discussed in Section 6.2, accounts for the change in sensor reaction rates caused by variations in flux level induced by changes in core spatial power distributions from fuel cycle to fuel cycle. For a single-cycle irradiation, C, is normally taken to be 1.0. However, for multiple-cycle irradiations, particularly those employing low leakage fuel management, the additional Cj term should be employed. The impact of changing flux levels for constant power operation can be quite significant for sensor sets that have been irradiated for many cycles in a reactor that has transitioned from non-low leakage to low leakage fuel management or for sensor sets contained in surveillance capsules that have been moved from one capsule location to another.

The fuel cycle specific neutron flux values along with the computed values for Cj are listed in Table A-3.

These flux values represent the cycle dependent results at the radial and azimuthal center of the respective capsules at the axial elevation of the active fuel midplane.

Prior to using the measured reaction rates in the least-squares evaluations of the dosimetry sensor sets, additional corrections were made to the 238U measurements to account for the presence of 233U impurities in the sensors as well as to adjust for the build-in of plutonium isotopes over the course of the irradiation.

Corrections were also made to the 238U and " 7Np sensor reaction rates to account for gamma ray induced fission reactions that occurred over the course of the capsule irradiations. The correction factors applied to the Alvin W. Vogtle Unit 2 fission sensor reaction rates are summarized as follows:

Appendix A

1-WCAP-16382 A4 Correction Capsule U Capsule Y Capsule X Capsule W 235U Impurity/Pu Build-in 0.870 0.841 0.817 0.777 238 U(y,f) 0.966 0.968 0.967 0.969 Net 238U Correction 0.841 0.814 0.790 0.753 7 Np(yf) 0.990 0.990 0.990 0.991 These factors were applied in a multiplicative fashion to the decay corrected uranium and neptunium fission sensor reaction rates.

Results of the sensor reaction rate determinations for Capsules U, Y,X, and W are given in Table A4. In Table A4, the measured specific activities, decay corrected saturated specific activities, and computed reaction rates for each sensor indexed to the radial center of the capsule are listed. The fission sensor reaction rates are listed both with and without the applied corrections for 23SU impurities, plutonium build-in, and gamma ray induced fission effects.

A.1.2 Least Squares Evaluation of Sensor Sets Least squares adjustment methods provide the capability of combining the measurement data with the corresponding neutron transport calculations resulting in a Best Estimate neutron energy spectrum with associated uncertainties. Best Estimates for key exposure parameters such as 4(E > 1.0 MeV) or dpa/s along with their uncertainties are then easily obtained from the adjusted spectrum. In general, the least squares methods, as applied to surveillance capsule dosimetry evaluations, act to reconcile the measured sensor reaction rate data, dosimetry reaction cross-sections, and the calculated neutron energy spectrum within their respective uncertainties. For example, R I +/-, = at (aOg +/- we, )((ig +/- S3) g relates a set of measured reaction rates, R,, to a single neutron spectrum, fg, through the multigroup dosimeter reaction cross-section, aig, each with an uncertainty 8. The primary objective of the least squares evaluation is to produce unbiased estimates of the neutron exposure parameters at the location of the measurement.

For the least squares evaluation of the Alvin W.Vogtle Unit 2 surveillance capsule dosimetry, the FERRET code[A3] was employed to combine the results of the plant specific neutron transport calculations and sensor set reaction rate measurements to determine best-estimate values of exposure parameters (4(E > 1.0 MeV) and dpa) along with associated uncertainties for the four in-vessel capsules withdrawn to date.

Appendix A

WCAP-1 6382 A-5 A-5 WCAP-1 6382 The application of the least squares methodology requires the following input:

I - The calculated neutron energy spectrum and associated uncertainties at the measurement location.

2 - The measured reaction rates and associated uncertainty for each sensor contained in the multiple foil set.

3 - The energy dependent dosimetry reaction cross-sections and associated uncertainties for each sensor contained in the multiple foil sensor set.

For the Alvin NV. Vogtle Unit 2 application, the calculated neutron spectrum was obtained from the results of plant specific neutron transport calculations described in Section 6.2 of this report. The sensor reaction rates were derived from the measured specific activities using the procedures described in Section A. 1.1. The dosimetry reaction cross-sections and uncertainties were obtained from the SNLRML dosimetry cross-section library[A 4. The SNLRML library is an evaluated dosimetry reaction cross-section compilation recommended for use in LWR evaluations by ASTM Standard E1018, "Application of ASTM Evaluated Cross-Section Data File, Matrix E 706 (IIB)".

The uncertainties associated with the measured reaction rates, dosimetry cross-sections, and calculated neutron spectrum were input to the least squares procedure in the form of variances and covariances.

The assignment of the input uncertainties followed the guidance provided in ASTM Standard E 944, "Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance."

The following provides a summary of the uncertainties associated with the least squares evaluation of the Alvin W. Vogtle Unit 2 surveillance capsule sensor sets.

Reaction Rate Uncertainties The overall uncertainty associated with the measured reaction rates includes components due to the basic measurement process, irradiation history corrections, and corrections for competing reactions. A high level of accuracy in the reaction rate determinations is assured by utilizing laboratory procedures that conform to the ASTM National Consensus Standards for reaction rate determinations for each sensor type.

After combining all of these uncertainty components, the sensor reaction rates derived from the counting and data evaluation procedures were assigned the following net uncertainties for input to the least squares evaluation:

Reaction l Uncertainty 63 60 Cu(na) Co 5%

"Fe(n,p)"Mn 5%

58 N1(n,p)58 Co 5%

238 U(n,f)' 37 Cs 10%

237 Np(n,f)' 3 7 Cs 10%

59 Co(ny) 60 Co 5% '

These uncertainties are given at the I cr level.

Appendix A

WCAP-1 6382 A-6 A-6 WCAP-l 6332 Dosimetry Cross-Section Uncertainties The reaction rate cross-sections used in the least squares evaluations were taken from the SNLRML library. This data library provides reaction cross-sections and associated uncertainties, including covariances, for 66 dosimetry sensors in common use. Both cross-sections and uncertainties are provided in a fine multigroup structure for use in least squares adjustment applications. These cross-sections were compiled from the most recent cross-section evaluations and they have been tested with respect to their accuracy and consistency for least squares evaluations. Further, the library has been empirically tested for use in fission spectra determination as well as in the fluence and energy characterization of 14 MeV neutron sources.

For sensors included in the Alvin W. Vogtle Unit 2 surveillance program, the following uncertainties in the fission spectrum averaged cross-sections are provided in the SNLRML documentation package.

Reaction Uncertainty 63Cu(n,a)6OCo 4.084.16%

5 Fe(np)S4 Mn 3.05-3.11%

"Ni(n,p) 5"Co 4.494.56%

238U(nf)' 37Cs 0.54-0.64%

23 Np(n,f)137Cs 10.32-10.97%

59 Co(ny)60Co 0.79-3.59%

Thee a iniato oftedsmtycosscin netite anes ablatd roid soitdwt These tabulated ranges provide an indication of the dosimetry cross-section uncertainties associated with the sensor sets used in LWR irradiations.

Calculated Neutron Spectrum The neutron spectra input to the least squares adjustment procedure were obtained directly from the results of plant specific transport calculations for each surveillance capsule irradiation period and location. The spectrum for each capsule was input in an absolute sense (rather than as simply a relative spectral shape). Therefore, within the constraints of the assigned uncertainties, the calculated data were treated equally with the measurements.

While the uncertainties associated with the reaction rates were obtained from the measurement procedures and counting benchmarks and the dosimetry cross-section uncertainties were supplied directly with the SNLRML library, the uncertainty matrix for the calculated spectrum was constructed from the following relationship:

Appendix A

WCAP-16382 A-7 A-7 WCAP-1 6382 MMgB .=R 2

= n +R + RBR *R.P B where R, specifies an overall fractional normalization uncertainty and the fractional uncertainties R. and R,, specify additional random group-wise uncertainties that are correlated with a correlation matrix given by:

Pgg. = [- ]S6gg + 0 eH where (g - g')2 H= 2y The first term in the correlation matrix equation specifies purely random uncertainties, while the second term describes the short-range correlations over a group range y (0 specifies the strength of the latter term). The value of 8 is 1.0 when g = g', and is 0.0 otherwise.

The set of parameters defining the input covariance matrix for the Alvin W.Vogtle Unit 2 calculated spectra was as follows:

Flux Normalization Uncertainty (Rn) 15%

Flux Group Uncertainties (R., Rg.)

(E > 0.0055 MeV) 15%

(0.68 eV < E < 0.0055 MeV) 29%

(E < 0.68 eV) 52%

Short Range Correlation (0)

(E > 0.0055 MeV) 0.9 (0.68 eV < E < 0.0055 MeV) 0.5 (E < 0.68 eV) 0.5 Flux Group Correlation Range (y)

(E > 0.0055 MeV) 6 (0.68 eV < E < 0.0055 MeV) 3 (E < 0.68 eV) 2 Appendix A

it-WCAP-16382 A-8 A.1.3 Comparisons of Measurements and Calculations Results of the least squares evaluations of the dosimetry from the Alvin W. Vogtle Unit 2 surveillance capsules withdrawn to date are provided in Tables A-5 and A-6. In Table A-5, measured, calculated, and best-estimate values for sensor reaction rates are given for each capsule. Also provided in this tabulation are ratios of the measured reaction rates to both the calculated and least squares adjusted reaction rates.

These ratios of M/C and M/BE illustrate the consistency of the fit of the calculated neutron energy spectra to the measured reaction rates both before and after adjustment. In Table A-6, comparison of the calculated and best estimate values of neutron flux (E > 1.0 MeV) and iron atom displacement rate are tabulated along with the BE/C ratios observed for each of the capsules.

The data comparisons provided in Tables A-5 and A-6 show that the adjustments to the calculated spectra are relatively small and well within the assigned uncertainties for the calculated spectra, measured sensor reaction rates, and dosimetry reaction cross-sections. Further, these results indicate that the use of the least squares evaluation results in a reduction in the uncertainties associated with the exposure of the surveillance capsules. From Section 6.4 of this report, it may be noted that the uncertainty associated with the unadjusted calculation of neutron fluence (E > 1.0 MeV) and iron atom displacements at the surveillance capsule locations is specified as 12% at the ls level. From Table A-6, it is noted that the corresponding uncertainties associated with the least squares adjusted exposure parameters have been reduced to 6% for neutron flux (E > 1.0 MeV) and 8% for iron atom displacement rate. Again, the uncertainties from the least squares evaluation are at the la level.

Further comparisons of the measurement results with calculations are given in Tables A-7 and A-8.

These comparisons are given on two levels. In Table A-7, calculations of individual threshold sensor reaction rates are compared directly with the corresponding measurements. These threshold reaction rate comparisons provide a good evaluation of the accuracy of the fast neutron portion of the calculated energy spectra. In Table A-8, calculations of fast neutron exposure rates in terms of 4(E > 1.0 MeV) and dpa/s are compared with the best estimate results obtained from the least squares evaluation of the capsule dosimetry results. These two levels of comparison yield consistent and similar results with all measurement-to-calculation comparisons falling well within the 20% limits specified as the acceptance criteria in Regulatory Guide 1.190.

In the case of the direct comparison of measured and calculated sensor reaction rates, the M/C comparisons for fast neutron reactions range from 0.96 to 1.26 for the 20 samples included in the data set. The overall average M/C ratio for the entire set of Alvin W. Vogtle Unit 2 data is 1.11 with an associated standard deviation of 10.7%.

In the comparisons of best estimate and calculated fast neutron exposure parameters, the corresponding BE/C comparisons for the capsule data sets range from 0.99 to 1.20 for neutron flux (E > 1.0 MeV) and from 1.00 to 1.18 for iron atom displacement rate. The overall average BE/C ratios for neutron flux (E > 1.0 MeV) and iron atom displacement rate are 1.09 with a standard deviation of 7.7% and 1.10 with a standard deviation of 6.7%, respectively.

Based on these comparisons, it is concluded that the calculated fast neutron exposures provided in Section 6.2 of this report are validated for use in the assessment of the condition of the materials comprising the beltline region of the Alvin W. Vogtle Unit 2 reactor pressure vessel.

Appendix A

WCAP-16382 A-9

• ITable A-I Nuclear Parameters Used In The Evaluation Of Neutron Sensors Monitor Reaction of Target 90% Response Product Fission Material Interest Atom Range (MeV) Half-life Yield Fraction (%)

63 Copper Cu (n,a) 0.6917 4.9- 11.9 5.271 y Iron 1 4 Fe (n,p) 0.0585 2.1 - 8.5 312.1 d Nickel "Ni (n,p) 0.6808 - 1.5 - 8.3 70.82 d Uranium-238 238U (nf) 1.0000 1.3 - 6.9 30.07 y 6.02 Neptunium-237 ".Np(n,f) 1.0000 0.3 -3.8 30.07 y 6.17 Cobalt-Aluminum 59 Co (ny) 0.0015 non-threshold 5.271 y Note: The 90% response range is defined such that, in the neutron spectrum characteristic of the Alvin W. Vogtle Unit 2 surveillance capsules, approximately 90% of the sensor response is due to neutrons in the energy range specified with approximately 5% of the total response due to neutrons with energies below the lower limit and 5% of the total response due to neutrons with energies above the upper limit.

Appendix A

it-WCAP- 16382 A-10 WCAP-16382A- 1 Table A-2 Monthly Thermal Generation During The First Eleven Fuel Cycles Of The Alvin W. Vogtle Unit 2 Reactor (Reactor power of 3411 MWt from startup through Cycle 4 (3/13/93) and 3565 MWt from Cycle 5 (4/27/93) through the End of Cycle 11)

Thermal Thermal Thermal Generation Generation Generation Month-Year (M't-hr) Month-Year (MWt-hr) Month-Year (MWt-hr)

Mar-89 0 Mar-92 605707 Mar-95 10688 Apr-89 475504 Apr-92 0 Apr-95 2438900 May-89 617966 May-92 1578601 May-95 2650425 Jun-89 2450888 Jun-92 2447254 Jun-95 2565303 Jul-89 2452023 Jul-92 2532424 Jul-95 2456584 Aug-89 2526703 Aug-92 2534744 Aug-95 2650678 Sep-89 2439109 Sep-92 2452670 Sep-95 2565249 Oct-89 2034639 Oct-92 2539098 Oct-95 2654328 Nov-89 2350213 Nov-92 2451426 Nov-95 2565212 Dec-89 2335572 Dec-92 2052686 Dec-95 2624729 Jan-90 2503482 Jan-93 2536193 Jan-96 2650834 Feb-90 2289775 Feb-93 2291024 Feb-96 2479725 Mar-90 2340854 Mar-93 2536217 Mar-96 2650787 Apr-90 2396650 Apr-93 2450906 Apr-96 2565415 May-90 2424191 May-93 2577663 May-96 2650735 Jun-90 2181332 Jun-93 2406365 Jun-96 2565158 Jul-90 1854770 Jul-93 2629330 Jul-96 2452545 Aug-90 1534544 Aug-93 2559359 Aug-96 2552746 Sep-90 585194 Sep-93 547977 Sep-96 489969 Oct-90 0 Oct-93 903906 Oct-96 1241612 Nov-90 1185372 Nov-93 2564027 Nov-96 2564798 Dec-90 2395968 Dec-93 2588183 Dec-96 2650604 Jan-91 2023180 Jan-94 2429440 Jan-97 2650701 Feb-91 1953887 Feb-94 2393295 Feb-97 2393844 Mar-91 1827085 Mar-94 2639006 Mar-97 2650728 Apr-91 2149993 Apr-94 2533075 Apr-97 2561147 May-91 2276659 May-94 2523585 May-97 2630761 Jun-91 2452835 Jun-94 1262082 Jun-97 2564816 Jul-91 2534141 Jul-94 1926053 Jul-97 2650622 Aug-91 2505776 Aug-94 2341001 Aug-97 2650268 Sep-91 2359978 Sep-94 2564313 Sep-97 2564794 Oct-91 2508529 Oct-94 2653771 Oct-97 2654064 Nov-91 2433457 Nov-94 2564454 Nov-97 2565321 Dec-91 2535003 Dec-94 2649055 Dec-97 2650576 Jan-92 2534130 Jan-95 2649874 Jan-98 2650913 Feb-92 .I. 2299840 Feb-95

.1. ___________________________

2063517 Feb-98 - 2296803 Appendix A

WCAP- 16382 A-11 Table A-2 cont'd Monthly Thermal Generation During The First Eleven Fuel Cycles Of The Alvin W. Vogtle Unit 2 Reactor (Reactor power of 3411 MWt from startup through Cycle 4 (3/13/93) and 3565 MWt from Cycle 5 (4/27/93) through the End of Cycle 11)

TheTherm Thermal Thermal Generation Generation Generation Month-Year (MWt-hr) Month-Year (MWt-hr) Month-Year (MWt-hr)

Mar-98 491140 Mar-01 2626793 Mar-04 2650596 Apr-98 779588 Apr-01 541918 Apr-04 1435551 May-98 2068679 May-01 2212525 Jun-98 2017178 Jun-01 2566207 Jul-98 2630863 Jul-01 2651538 Aug-98 2456507 Aug-01 2651538 Sep-98 2412869 Sep-01 2536586 Oct-98 2607668 Oct-01 2654480 Nov-98 2565406 Nov-01 2564834 Dec-98 2650912 Dec-01 2649576 Jan-99 2650519 Jan-02 2648988 Feb-99 2332866 Feb-02 2392406 Mar-99 2503094 Mar-02 2649969 Apr-99 2561474 Apr-02 2560911 May-99 2650716 May-02 2649576 Jun-99 2501128 Jun-02 2564442 Jul-99 2650519 Jul-02 2649773 Aug-99 2648554 Aug-02 2649969 Sep-99 2508597 Sep-02 2537763 Oct-99 149981 Oct-02 386049 Nov-99 2051716 Nov-02 621071 Dec-99 2300308 Dec-02 1421414 Jan-00 2637192 Jan-03 2651478 Feb-00 2480228 Feb-03 2395041 Mar-00 2632679 Mar-03 2204085 Apr-00 2562046 Apr-03 2562629 May-00 2651123 May-03 2651185 Jun-00 2565774 Jun-03 2565770 Jul-00 2650927 Jul-03 2651185 Aug-00 2650534 Aug-03 1785259 Sep-00 2565185 Sep-03 2246890 Oct-00 2654654 Oct-03 2654326 Nov-00 2565381 Nov-03 2565378 Dec-00 2650338 Dec-03 2650853 Jan-01 2651123 Jan-04 2629328 Feb-01 2394487 Feb-04 2379233 Appendix A

a-WCAP- 16382 A-12 A-I 2 WCAP-16382 Table A-3 Calculated Cj Factors at the Surveillance Capsule Center Core Midplane Elevation Fuel *(E > 1.0 MeV) [n/cm2-sJ Cycle Capsule U Capsule Y Capsule X Capsule W 1 9.43E+I0 8.78E+10 9.43E+I0 9.34E+10 2 7.30E+10 7.97E+10 7.89E+10 3 6.32E+10 6.82E+10 6.75E+10 4 6.08E+10 6.63E+10 6.57E+10 5 6.17E+10 6.11E+I0 6 6.79E+10 6.73E+10 7 7.01E+10 8 7.17E+10 9 6.88E+10 10 7.04E+1 0 Average 9.43E+ 10 7.09E+10 7.25E+10 7.12E+10 Fuel CJ Cycle Capsule U Capsule Y Capsule X Capsule W 1 1.00 1.24 1.30 1.31 2 1.03 1.10 1.11 3 0.89 0.94 0.95 4 0.86 0.92 0.92 5 0.85 0.86 6 0.94 0.95 7 0.99 8 1.01 9 0.97 10 0.99 Average 1.00 1.00 1.00 1.00 Appendix A

WCAP-16382 A-13 A-13 WCAP- 16382 Table A-4 Measured Sensor Activities And Reaction Rates Surveillance Capsule U Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63Cu (naz) 6 0CO Top

? 5.5 1E+04 3.96E+05 3.96E+05 6.04E-1 7 Middle 4.96E+04 3.56E+05 3.56E+05 5.44E-1 7 Bottom 4.86E+04 3.49E+05 3.49E+05 5.33E-1 7 Average 5.60E-17 "Fe (n,p) 14Mn Top 1.88E+06 3.98E+06 3.98E+06 6.3 1E-I5 Middle 1.65E+06 3.49E+06 3.49E+06 5.54E-1 5 Bottom 1.67E+06 3.53E+06 3.53E+06 5.60E-1 5 Average 5.82E-15 "Ni (n,p) 5"Co Top 1.86E+07 5.81E+07 5.81 E+07 8.32E-15 Middle 1.70E+07 5.3 1E+07 5.31 E+07 7.60E-15 Bottom 1.65E+07 5.16E+07 5.16E+07 7.388E-15 Average 7.77E-15 238U (nf) 137Cs (Cd) Middle 1.83E+05 6.78E+06 6.78E+06 4.45E-14 235 39 Pu, and y,fissiion corrections:

23SU (n,f) '"Cs (Cd) Including u, 2 3.74E-14 237Np (nf) 137Cs (Cd) Middle 1.56E+06 I 5.78E+07 I 5.78E+07 3.69E-13 237Np (nf) 137Cs (Cd) Including y,fis!sion correction: 3.65E-13 59 Co (ny) 60 Co Top 1.13E+07 8.12E+07 8.12E+07 5.30E-12 Middle 1.26E+07 9.05E+07 9.05E+07 5.91E-12 Bottom 1.15E+07 8.26E+07 8.26E+07 5.39E-12 Average 5.53E-12 5 9Co (ny) 'OCo (Cd) Top 5.99E+06 4.30E+07 4.30E+07 2.81E-12 Middle 6.21E+06 4.46E+07 4.46E+07 2.91E-12 Bottom 6.19E+06 4.45E+07 4.45E+07 2.90E-12 Average 2.87E-12 Notes: 1) Measured specific activities are indexed to a counting date of 12/12/90.

2) The average 238U (n,f) reaction rate of 3.74E-14 includes a correction factor of 0.870 to account for plutonium build-in and an additional factor of 0.966 to account for photo-fission effects in the sensor.

3) The average 237 Np (n,f) reaction rate of 3.65E-13 includes a correction factor of 0.990 to account for photo-fission effects in the sensor.

Appendix A

a-WCAP-16382 A-14 A-14 WCAP-1 6382 Table A-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule Y Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63 Top CU (n,a) 6Co 1.33E+05 3.14E+05 3.14E+05 4.78E-17 Middle 1.21E+05 2.85E+05 2.85E+05 4.35E-17 Bottom 1.21E+05 2.85E+05 2.85E+05 4.35E-17 Average 4.50E-17 54 Fe (n,p) 54Mn Top 1.54E+06 2.72E+06 2.72E+06 4.32E-15 Middle 1.41 E+06 2.49E+06 2.49E+06 3.95E-15 Bottom 1.42E+06 2.5 1E+06 2.5 1E+06 3.98E-15 Average 4.09E-15 5 Ni (n,p) 5"Co Top 207.32 7.801E+06 4.26E+07 4.261E+07 Middle 207.32 7.18E+06 3.92E+07 3.92E+07 Bottom 207.32 7.03E+06 3.84E+07 3.84E+07 Average 5.73E-15 238U (nf) 137CS (Cd) Middle 4.71E+05 4.45E+06 4.45E+06 2.92E- 14 238U (nf) 137CS Including 235U, 2 39 Pu, and y,fission corrections:

(Cd) 2.38E-14 23 7Np (n,f) 137CS (Cd) Middle 3.78E+06 I 3.57E+07 I 3.57E+07 2.28E-13 237Np (nf) 137CS (Cd) Including y,fission correction: 2.25E-13 59 Co (n,y) 60 Co Top 2.39E+07 5.64E+07 5.64E+07 3.68E-12 Middle 2.37E+07 5.59E+07 5.59E+07 3.65E-12 Bottom 2.38E+07 5.61 E+07 5.61 E+07 3.66E-12 Average 3.66E-12 "Co (n,y) 60Co (Cd) Top 1.22E+07 2.88E+07 2.88E+07 1.88E-12 Middle 1.25E+07 2.95E+07 2.95E+07 1.92E-12 Bottom 1.27E+07 2.99E+07 2.99E+07 1.95E-12 Average 1.92E-12 Notes: 1) Measured specific activities are indexed to a counting date of 8/1/95.

2) The average 23SU (n,f) reaction rate of 2.3 8E-14 includes a correction factor of 0.841 to account for plutonium build-in and an additional factor of 0.968 to account for photo-fission effects in the sensor.

3) The average 237Np (n,f) reaction rate of 2.25E-13 includes a correction factor of 0.990 to account for photo-fission effects in the sensor.

Appendix A

WCAP-16382 A-15

-1 WCAP-l6382 Table A-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule X Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom)

Cu (n,a) 60Co Top 1.96E+05 3.59E+05 3.59E+05 5.47E-1 7 Middle 1.78E+05 3.26E+05 3.26E+05 4.97E-1 7 Bottom 1.74E+05 3.18E+05 3.188E+05 4.86E-17 Average 5.10E-17 Fe (n,p) S4Mn Top 1.78E+06 3.4 1E+06 3.41E+06 5.40E-15 Middle 1.62E+06 3.1 OE+06 3.1 OE+06 4.92E-1 5 Bottom 1.59E+06 3.05E+06 3.05E+06 4.83E-15 Average 5.05E-15 58 Ni (n,p) 58Co Top 4.96E+06 5.50E+07 5.50E+07 7.87E-15 Middle 4.41E+06 4.89E+07 4.89E+07 7.00E-1 5 Bottom 4.44E+06 4.92E+07 4.92E+07 7.04E-1 5 Average 7.30E-15 238U (nf) 137Cs (Cd) Middle 9.OOE+05 5.66E+06 5.66E+06 3.72E-1 4 238U (nf) 137CS (Cd) Including 235U,239Pu, and yfission corrections: 2.94E-14 237 Np 237 Np (nf) 137 CS (Cd)

(n4f) 137Cs (Cd)

Middle 6.84E+06 I 4.30E+07 4.30E+07 2.74E-13 Including y,fiss;ion correction: 2.72E-13 59 Co (n,y) 6 0Co Top Middle 3.70E+07 6.77E+07 6.77E+07 4.42E-12 Bottom 3.66E+07 6.70E+07 6.70E+07 4.37E-12 Average 4.39E-12 "Co (n,y) 60CO (Cd) Top Middle 1.93E+07 3.53E+07 3.53E+07 2.30E-12 Bottom 1.97E+07 3.60E+07 3.60E+07 2.35E-12 Average .1. b 2.33E-12 Notes: 1) Measured specific activities are indexed to a counting date of 11/1/98.

2) The average 2 38 U (n,f) reaction rate of 2.94E-14 includes a correction factor of 0.817 to account for plutonium build-in and an additional factor of 0.967 to account for photo-fission effects in the sensor.

3) The average 237 Np (n,f) reaction rate of 2.72E-13 includes a correction factor of 0.990 to account for photo-fission effects in the sensor.

4) Top monitors for the 59Co sensors were not present at the removal of the capsule.

Appendix A

WCAP-16382 A-16 WCAP-16382 A-16 Table A-4 cont'd Measured Sensor Activities And Reaction Rates Surveillance Capsule W Radially Radially Adjusted Adjusted Measured Saturated Saturated Reaction Activity Activity Activity Rate Reaction Location (dps/g) (dps/g) (dps/g) (rps/atom) 63Cu (n,a) 6Co Top 2.16E+05 2.98E+05 2.981E+05 4.54E-1 7 Middle 1.94E+05 2.67E+05 2.67E+05 4.08E-1 7 Bottom 1.90E+05 2.62E+05 2.62E+05 4.OOE-1 7 Average 4.21E-17 5 Fe (n,p) "Mn Top I.83E+06 2.80E+06 2.80E+06 4.43 E-1 5 Middle I.67E+06 2.55E+06 2.551E+06 4.05E-1 5 Bottom 1.64E+06 2.5 1E+06 2.5 1E+06 3.97E-15 Average 4.15E-15 "Ni (n,p) 5"Co Top 1.OOE+07 4.54E+07 4.54E+07 6.50E-1 5 Middle 9.22E+06 4.18E+07 4.18E+07 5.99E-1 5 Bottom 8.99E+06 4.08E+07 4.08E+07 5.84E-15 Average 6.11E-15 238U (nf) 137CS (Cd) Middle 1.40E+06 I 5.47E+06 5.47E+06 3.59E-1 4 238U (nf) 37CS (Cd) Including 235U, 239Pu, and y,fission corrections: 2.70E-14 237Np (n,f) 3'Cs (Cd) Middle 9.54E+06 I 3.72E+07 I 3.72E+07 2.38E-13 237Np (n,f) 37Cs (Cd) Including y,fiss sion correction: 2.35E-13 59Co (n,y) 60CO Top 4.00E+07 5.5 IE+07 5.5 1E+07 3.60E-12 Middle 4.00E+07 5.5 1E+07 5.51 E+07 3.60E-12 Bottom 4.02E+07 5.54E+07 5.54E+07 3.62E-12 Average 3.60E-12 "Co (n,7) 6Co (Cd) Top 2.28E+07 3.14E+07 3.14E+07 2.05E-12 Middle 2.35E+07 3.24E+07 3.24E+07 2.11lE-12 Bottom 2.291E+07 3.16E+07 3.16E+07 2.06E-1 2 Average 2.08E-12 Notes: 1) Measured specific activities are indexed to a counting date of 9/16/04.

2) The average 238U (n,f) reaction rate of 2.70E-14 includes a correction factor of 0.777 to account for plutonium build-in and an additional factor of 0.969 to account for photo-fission effects in the sensor.

3) The average 237Np (n,f) reaction rate of 2.35E-13 includes a correction factor of 0.991 to account for photo-fission effects in the sensor.

Appendix A

WCAP-16382 A-17 Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule U

__________ _____ _ lReaction Rate [rps/atom] _____ ____

Best Reaction Measured Calculated Estimate M/C M/BE Cu(n,a)fCo 5.60E-17 4.90E-17 5.42E-17 1.14 1.03 54 Fe(n,p) 54Mn 5.82E-15 5.54E-15 5.93E-15 1.05 0.98 58Ni(n,p)5 8Co 7.77E-15 7.78E-15 8.21E-15 1.00 0.94 238U(nf)"3 Cs (Cd) 3.74E-14 3.OOE-14 3.29E-14 1.25 1.14 237 Np(nf)D 37 Cs (Cd) 3.65E-13 2.95E-13 3.47E-13 1.24 1.05 59Co(ny) 60Co 5.53E-12 4.23E-12 5.43E-12 1.31 1.02 59Co(n y)60Co (Cd) 2.87E-12 2.94E-12 2.92E-12 0.98 0.98 Capsule Y Reac ion Rate Irps/ toml Best Reaction Measured Calculated Estimate MWC MI/BE 63 Cu(na)60Co 4.50E-17 3.92E-17 4.28E-17 1.15 1.05 54Fe(n,p) 54Mn 4.09E-15 4.28E-15 4.25E-15 0.96 0.96 58Ni(n,p) 5 Co 5.73E-15 5.98E-15 5.91 E-15 0.96 0.97 238 U(nf)137 Cs (Cd) 2.38E-14 2.27E-14 2.23E-14 1.05 1.06 23'Np(nf) 137Cs (Cd) 2.25E-13 2.20E-13 2.21 E-13 1.02 1.02 59Co(n,y)60Co 3.66E-12 3.06E-12 3.59E-12 1.19 1.02

' 9Co(ny)60Co (Cd) 1.92E-12 2.15E-12 1.95E-12 0.89 0.98 Appendix A

IL-WCAP-I16382 A-18 WCAP-I 6382 A-IS Table A-5 Comparison of Measured, Calculated, and Best Estimate Reaction Rates At The Surveillance Capsule Center Capsule X Reaction Rate Irns/atoml Best Reaction ' Measured Calculated Estimate M/C MIBE 63Cu(n,a)60 Co 5.lOE-17 4.02E-17 4.97E-17 1.27 1.03 54 Fe(n,p)54Mn 5.05E-15 4.38E-15 5.21E-15 1.15 0.97 58 Ni(np)58Co 7.30E-15 6.13E-15 7.33E-15 1.19 1.00 238 U(nf)" 7Cs (Cd) 2.94E-14 2.33E-14 2.77E-14 1.26 1.06 237Np(n f)137Cs (Cd) 2.72E-13 2.25E-13 2.68E-13 1.21 1.01 59Co(n,y)6Co 4.39E-12 3.17E-12 4.31E-12 1.39 1.02 59Co(ny)6oCo (Cd) 2.33E-12 2.20E-12 2.36E-12 1.06 0.99 Capsule W Reac _ion Rate [rps/ tom]

Best Reaction Measured Calculated Estimate M/C M/BE 63 Cu(n,a) 60Co 4.21 E-17 3.94E-17 4.12E-17 1.07 1.02 14Fe(np)4 Mn 4.15E-15 4.29E-15 4.35E-15 0.97 0.95 58Ni(np)5 8Co 6.11E-15 6.OOE-15 6.17E-15 1.02 0.99 8UU(nf)' 7 Cs (Cd) 2.70E-14 2.27E-14 2.38E-14 1.19 1.14 237Np(n f)137Cs (Cd) 2.35E-13 2.21E-13 2.36E-13 1.06 1.00 59Co(ny)6 0Co 3.60E-12 2.83E-12 3.54E-12 1.27 1.02 59 Co(n y)60Co (Cd) 2.072.OOE-12 I 2.10E-12 1.04 0.99 Appendix A

WCAP-1 6382 A-19 I .Table A-6 Comparison of Calculated and Best Estimate Exposure Rates At The Surveillance Capsule Center

• (E > 1.0 MeV) jIn/cm -s2 Best Uncertainty Capsule ID Calculated Estimate (lF) BE/C U 9.43E+10 1.06E+11 6% 1.12 Y 7.09E+10 6.99E+10 6% 0.99 X 7.25E+10 8.67E+10 6% 1.20 W 7.12E+10 7.57E+10 6% 1.06 Note: Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period.

Note: Calculated results are based on the synthesized transport calculations taken at the core midplane following the completion of each respective capsules irradiation period.

Appendix A

WCAP-1 6382 A-20 A-20 WCAP-1 6382 Table A-7 Comparison of Measured/Calculated (M/C) Sensor Reaction Rate Ratios Including all Fast Neutron Threshold Reactions M/C Ratio Reaction Capsule U Capsule Y Capsule X Capsule W 63 Cu(n,a) 60Co 1.14 1.15 1.27 1.07 "Fe(np)4 Mn 1.05 0.96 1.15 0.97 5 Ni(n,p)5 8 Co 1.00 0.96 1.19 1.02 238 U(np)' 3Cs (Cd) 1.25 1.05 1.26 1.19 237Np(nf)137Cs (Cd) 1.24 1.02 1.21 1.06 Average 1.14 1.03 1.22 1.06

% Standard Deviation 11.1 7.9 5.0 8.2 Note: The overall average M/C ratio for the set of 20 sensor measurements is 1.11 with an associated standard deviation of 10.7%.

Table A-8 Comparison of Best Estimate/Calculated (BE/C) Exposure Rate Ratios BE/C Ratio Capsule ID *(E > 1.0 MeV) dpa/s U 1.12 1.13 Y 0.99 1.00 X 1.20 1.18 W 1.06 1.07 Average 1.09 1.10

% Standard Deviation 7.7 6.7 Appendix A

WCAP-16382 A-21 A-2 1 WCAP-I 6382 Appendix A References A-i. Regulatory Guide RG-1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, March 1995.

A-2. WCAP-13007, "Analysis of Capsule U from the Georgia Power Company Vogtle Unit 2 Reactor Vessel Radiation Surveillance Program," January 1991.

A-3. A. Schmittroth, FERRETDataAnalysis Core, HEDL-TME 79-40, Hanford Engineering Development Laboratory, Richland, WA, September 1979.

A-4. RSIC Data Library Collection DLC-178, "SNLRML Recommended Dosimetry Cross-Section Compendium", July 1994.

A-5 WCAP-14532, "Analysis of Capsule Y from the Georgia Power Company Vogtle Electric Generating Plant (VEGP) Unit 2 Reactor Vessel Radiation Surveillance Program,"

February 1996.

A-6 WCAP-15159, "Analysis of Capsule X From the Southern Nuclear Vogtle Electric Generating Plant Unit 2 Reactor Vessel Radiation Surveillance Program," March 1999.

Appendix A

WCAP-16382 B-0 APPENDIX B LOAD-TIME RECORDS FOR CHARPY SPECIMEN TESTS

• Specimen prefix "BL" denotes Lower Plate, Longitudinal Orientation

• Specimen prefix "BT" denotes Lower Plate, Transverse Orientation

• Specimen prefix "BW" denotes Weld Material

• Specimen prefix "BH" denotes Heat-Affected Zone material Appendix B

WCAP-I 6382 B-I 5000. O 4000.00 3000.00

-J 2000.00 1000.00 j

nnn 0.00 1.00 2.00 300 4.00 5.00 Time-I (ms) 5000.00 4W4000.00

.r 3000.00 0

-J 2000.00W 1000.00W 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Trne-I (Ms)

BL34, -25 0 F 5000.001 4000.00I

• 3000.00 2000.00-1000.00-

^ AA nnn 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BL4O, 0°F Appendix B

WCAP-I 6382 B-2 5000.00.

4000.00 a

3000.00 IJ 2000.00 1000.00 n nn. _S 0.0 A.-

1.00 2.00 3.00 4.00 5.00 6.00 Bre42(ms2 BL42, 25°F 5000.00 4000.00 3000.00 2000.00 1000.00 oIl" 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Ttrne- (ms)

BL44, 400 F 5000.ot I -

400.0. I g

3000.oC

-J 2000.OCI I I 000.0cI -

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Trme-1 (ms)

BL33, 50°F Appendix B

WCAP-16382 B-3 SOOO.O0 4000.00

• 3000.00' 3

2000.00 1000.00, 0.00

0. 00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms) 5000.00.

4000.00'

, 3000.00' 6,

-J 2000.00' 1000.00 0.00

0. 00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms) 5000.00 4000.00 a 300.00 C

2.00 3.00 6.00 Time-1 (ms)

BL32, 1000 F Appendix B

WCAP-I 6382 B4 I

5000.00 4000.00 as

,~3000.00 2000.00 1000.00 0.00 ,

0.00 1.00 2 00 3.00 4.00 5.00 6.00

,rime-1 (Ms)

BL41, 1250 F 5000.00 4000.00 x 3000.00 2000.00 1000.00 0.00 r , , ,i 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BL45, 1500 F 5000.00j.

4000.00 a '

n 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-i (Ms)

BL43, 175 0 F Appendix B

WCAP-16382 B-5 5000.00 4000.00 g7 3000.00 2000.00 1 00.00 I [, , , , ,

0.00 1.00 2.00 3.00 4.00 6.00 6.00 Tine-I (ms)

BL35,2000 F 6000.00 4000.00

.o 3000.00 2000.00 1000.00 11 . .

O.W 1.00 2.00 30 4.00 5.00 6.00 Time-i (ms)

BL37, 225°F 5000 .00 4000.00 3000 .00-

-J 2000 .00-1000 .00.

0.00 1 0O 2.00 3.00 4w00 S.00 6.00 Time-i (ms)

BT32, -75°F Appendix B

WCAP-16382 B-6 5000.00 4000.00

,a 3000.00 2000.00 1000.00.

nnn . I , - - -

0.00 1.00 2.00 3.00 4.00 5.00 6.00 rhe-1 (ms)

BT41, -25 0F 500.0_

4000.00 7 3000.00 a

2000.00 1000.00 0.00 - cl, - -

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms) 5000.0 4000.00 I

-6 3000U

.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

BT42, 25 0F Appendix B

WCAP-I 6382 B-7 5000.00 4000.00 3000.00 2000.00 1000.00 U.UU '- -

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tuie-1 (ms)

BT43, 500 F 5000.00' 4000.00 3000.00' 2000.00 1000.00 ultra 1 l r 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BT37, 750 F 5000.00.

4000.001 3000.00' 2000.00' 1000.00'

[X1 11.w I 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BT36, 750 F Appendix B

--- J -

WCAP-I 6382 B-8 5000.0 40W.W00 3000.W0 2000.00 1000.00 O.W0 0.00 1no 2.00 3.00 4.00 5.00 6.W Ttrne-I (ms)

BT40, 1000 F 5000.00 40W.00 '

3000000 2000.W0 1000.00 - , P @ w O.W0 0.00 1.00 2.00 3.00 4.W 5.00 6.00 Time-I Cms)

BT33, 1250 F 5W0.00 4000.00 3000.00 2000.0W 1000.00 1 S _

0.00 0.00 1.00 2.W 3.00 4.00 5.00 6.00 Time-I (ms)

BT39, 1500 F Appendix B

WCAP-1 6382 B-9 5000.00 +

4000.00

-6 3000.00

-j 2000 .00 1 000.00' nnn U.UU - I I I s II . . .

0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tkine-1 (ms)

BT38, 2000 F 4000.00 U

3000.00

-J 2000.00 1000.00 n .0 +

0.00 1.00 2.00 3.00 4.00 5.00 6.00 5000.00-4000.00 3000.00

-J 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.0 Trme-I (ms)

BT31, 250°F Appendix B

WCAP-16382 B-10 Time.1 (ms) 5000.00 4000.00 3000.00 2000.00 1000.00 Time32(ms)

BT34, 275°F 5000.00 4000.00 3000.00 200000 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

BW33, -50 0 F Appendix B

WCAP-16382 B-lI 5000.00 4000.00 I, 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

BW42, -25 0 F 5000.00 4000.00 3000.00 2000 M0 1000.00 , ,

0.00 0.00 1.00 2.00 3.00 4.00 .00 6.00 Time-I (ms)

BW36, 0F 5000.00 4000.00 3000.00 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BW35, 0 0F Appendix B

I-WCAP-I 6382 B-12 5000.00-4000.00 x 3000.00

-J 2000.00 1000 no 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BW45, 25 0 F 5,00.00 4000.00 a

1 3000.00 as 0

-J 2000.00 1000.00 0.00-0.00 1.00 2.00 3.00 4.00 5.00 Time-i (ms)

BW41, 500 F 500.00 4000.00

,', 3000.00 2000.00 1000.00 u-uu 1 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

BW37, 75°F Appendix B

WCAP-16382 B-13 5000.00.

4000.00.

.- 3000.00.

0 1 2000.00.

1000.00 0.00-0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

BW40, 75WF 5000.00 4000.00 a' 3000.00 2000.00 1 000.J00 nnn. _

0,0 0 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BW31, 100WF 5000.00 4000.00 X 3000.00 0

-j 2000.00 1000.00t nn,,

0.00 1 00 2.00 3.00 4.00 5.00 6.00 ITne-4 (ms)

BW34, 140WF Appendix B

WCAP-16382 B-14 5000.00 4000.00 8a, 3000.00 2000.00 1000.00 nnnfi- l l l z s-. l l l l l 0.00 1.00 2.00 3.00 4.00 S.0 6.00 Time-I (Ms) 5000.00 4000.00 3000.00 2000.00 1000.002 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tnme-i (ms)

BW32, 200 0 F 6000.00-4000.0-3000.00-2000.00 1000.00 n Mi 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

BW39, 2250 F Appendix B

WCAP-1 6382 B-15 5000.00o 4000.00

.7 3000.00 C

-J 2000.00-1000.00-0.00 0.j Time-1 (ms) 5000.00.

4000.00

,, 3000.00

-JC 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BW44, 2500 F 5000.00 4000.00 .

• , 3000.00.

2000.00.

1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BH44, -175 0 F Appendix B

1.

WCAP-1 6382 B-16 B- 16 WCAP-1 6382 5000.00 4000.00 ca 3000.00 0

-j 2000.00 Ad 1\

0.00-0.00 1.00 2.00 3.00 4.00 5.00 6.00 ime.1 (ms) soo~fo BH31,-1250 F 4000.00

- 3000.00

-J 2000.00 1000.00 I

a1.00 1.00 2.00 3.00 4.00 5.00 6.00 Trne-1 (ms)

BH33, -90 0 F 5000.00 I 4000.00 II ir 3000.00 II a

01 2000.00 I 1000.00I n rI 0.00 1.00 2.00 3.00 4.00 S5O 6.00 Time-I (ms)

BH43, -750 F Appendix B

WCAP-1 6382 ,, L B-17 5000.00 4000.00 3000.00, a

-J 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4C0 SDO 6.00 Tkne-I (ms) 5000.00 4000.00 aa 3000.00 03

-J 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Tkie-1 (ms) 5000.00S 4000.00-c 3000.00 a

0.00 1.00 2.00 3.00 4.00 5.00 6.00 rBne-1 (ms)

BH37, -50°F Appendix B

IL-WCAP-1 6382 B-i 8 5000.00 4000.00 as 3000.00

-Jwu 2000.00 1000.00 0.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-1 (ms)

BH34, -250 F 5000.00 4000.00 3000.00 2000 .00 1000.00 a 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

BH32, 0F 5000.00-4000.00 3000.00 2000.00 1000.00 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

BH41, 0F Appendix B

WCAP-1 6382 B-19 5000.00 4000.00 0 3000.00 2000.00 1000.00 0.00

0. '0 1.00 2.00 3.00 4.0 5.00 600 Time-I (ms) 01 5000.00I 4000.00 3000.00

-J 2000.00 1000.00 0.00 1.00 2.00 3.00 4D0 5.00 6.00 Time-1 (ms) 4000.00 ha n 3000.00 0

-J 200.00 1000.00 2.00 3.00 6.00 Time-1 (ms)

BH45, 750 F Appendix B

IL-WCAP- 6382 B-20 5000.00*

4000.00 a 3000.00

-j 200000 1000.00-0.00

0. 1.00 2.00 3.00 4.00 s.00 6.00 Time-i (Ms)

BH36, 1250 F 5000.00 4000.00 7 300000 2000.00' 1000.00.

nenI 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Time-I (ms)

BH35, 1500 F Appendix B

WCAP-16382 C-0 WCAP-16382 C-o APPENDIX C CHARPY V-NOTCH PLOTS FOR EACH CAPSULE USING HYPERBOLIC TANGENT CURVE-FITTING METHOD Appendix C

WCAP-16382 C-l C-I WCAP-16382 Contained in Table C-I are the upper shelf energy values used as input for the generation of the Charpy V-notch plots using CVGRAPH, Version 4.1. Lower shelf energy values were fixed at 2.2 ft-lb. The unirradiated and irradiated upper shelf energy values were calculated per the ASTM El 85-82 definition of upper shelf energy.

Table C-1 Upper Shelf Energy Values Fixed in CVGRAPH Material Unirradiated Capsule U Capsule Y Capsule X Capsule W Lower Shell Plate B8628-1 89 fl-lb 99 ft-lb 100 fl-lb 86 fl-lb 84 fl-lb (Longitudinal Orientation)

Lower Shell Plate B8628-1 70 fl-lb 79 fl-lb 73 ft-lb 65 fl-lb 69 fl-lb (Transverse Orientation)

Weld Metal 92 fl-lb 98 fl-lb 86 ft-lb 87 fl-lb 87 ft-lb (Heat # 87005)

HAZ Material 106 fl-lb 122 fl-lb 114 ft-lb 99 fl-lb 100 fl-lb Appendix C

UNIRRADIATED LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:12 AM Page 1 Coefficients of Curve 1 A = 45.6 B = 43.4 C = 76.43 TO = 37.56 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper She]f Energy=89.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=8.8 Deg F Temp@50 ft-lbs=45.4 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: UNIRR Fluence: n/cm^2 300 250 uW

, a 200 0

0 IL

@ 150 z

> 100 50 0 -

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 80. 00 4.00 6.03 -2.03

-80. 00 7.00 6. 03 .97

-30. 00 12.00 14. 86 -2.86

-30. 00 20.00 14. 86 5. 14

-30. 00 26. 00 14. 86 11. 14

.00 24.00 25. 84 - 1. 84

. 00 27.00 25. 84 1. 16

. 00 34.00 25. 84 8. 16

30. 00 30.00 41.32 - 11. 32 C-2

UNIRRADIATED LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B 1 He; at: C3500-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

30. 00 32. 00 41. 32 -9. 32

30. 00 51. 00 41. 32 9.68

60. 00 47.00 57. 99 - 10. 99

60. 00 54.00 57. 99 -3.99

60. 00 58.00 57. 99 .01

80. 00 68.00 67.49 .51

80. 00 71. 00 67.49 3.51

80. 00 70. 00 67.49 2.51 120. 00 81. 00 80. 00 1.00 120. 00 87.00 80. 00 7.00 120. 00 88.00 80. 00 8.00 160. 00 87.00 85. 61 1.39 160. 00 92.00 85. 61 6.39 240. 00 90. 00 88. 57 1.43 240. 00 90. 00 88.57 1.43 240. 00 96. 00 88. 57 7.43 300.00 88. 00 88.91 - .91 300. 00 90. 00 88. 91 1.09 Correlation Coefficient = .982 C-3

UNIRRADIATED LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Pnnted on 11/17/2004 02:29 PM Page 1 Coefficients of Curve I A = 37.97 B = 37.97 C = 82.49 TO = 42.82 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=75.9 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=36.4 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 200 150

'E c

0 8 100 la-50 0 o-

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

-80. 00 1.00 3.68 -2. 68

- 80. 00 3.00 3. 68

-30. 00 10. 00 11. 10 - 1. 8

-30. 00 14.00 11. 10 2.90

-30. 00 18.00 11. 10 6.90

.00 21. 00 19. 86 1.14

.00 21.00 19. 86 1.14

.00 25.00 19. 86 5.14

30. 00 24.00 32. 12 - 8. 12 C-4

UNIRRADIATED LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

30. 00 26. 00 32. 12 - 6. 12

30. 00 40. 00 32. 12 7. 88

60. 00 36. 00 45. 77 -9. 77

60. 00 43. 00 45. 77 -2. 77

60. 00 45. 00 45. 77 -. 77

80. 00 56. 00 54. 01 1. 99

80. 00 54. 00 54. 01 -. 01

80. 00 55. 00 54. 01 .99 120. 00 71.00 65. 81 5. 19 120. 00 70. 00 65.81 4. 19 120. 00 71.00 65. 81 5. 19 160. 00 70. 00 71.75 - 1.75 160. 00 76.00 71.75 4. 25 240. 00 77. 00 75.31 1. 69 240. 00 74.00 75.31 - 1.31 240. 00 69.00 75.31 -6.31 300. 00 74.00 75. 79 - 1.79 300. 00 74.00 75. 79 - 1.79 Correlation Coefficient = .985 C-5

UNIRRADIATED LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:35 AM Page 1 Coefficients of Curve 1 A = 50. B = 50. C = 38.73 TO = 64.93 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 65.0 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: UNIRR Fluence: n/cmr2 125-100 -

S.-

co 75 CD V)

I-

0. 50 -

25-0 - -

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

80. 00 .00 . 06 -. 06

80. 00 . 00 . 06 -. 06

30. 00 5.00 .74 4.26

30. 00 5.00 . 74 4.26

30. 00 5. 00 .74 4.26

.00 10. 00 3. 3 8 6. 62

. 00 10.00 3.38 6.62

.00 10. 00 3.38 6. 62

30. 00 20. 00 14. 14 5. 86 C-6

it UNIRRADIATED LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: LT Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

30. 00 20. 00 14. 14 5.86

30. 00 15.00 14. 14 . 86

60. 00 30.00 43. 67 - 13. 67

60. 00 35.00 43. 67 -8. 67

60. 00 45.00 43. 67 1.33

80. 00 75. 00 68.53 6.47

80. 00 75.00 68.53 6.47

80. 00 65.00 68.53 -3.53 120. 00 100.00 94. 50 5.50 120. 00 100.00 94.50 5.50 120. 00 100.00 94. 50 5.50 160.00 100.00 99. 27 .73 160. 00 100.00 99. 27 .73 240. 00 1 00. 0 0 99. 99 .01 240. 00 1 00. 00 99. 99 .01 240.00 100. 00 99. 99 .01 300. 00 100.00 100. 00 .00 300. 00 100.00 100. 00 .00 Correlation Coefficient = .994 C-7

CAPSULE U LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:13 AM Page 1 Coefficients of Curve 2 A = 50.6 B = 48.4 C = 99.74 TO = 56.04 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=99.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Ternp@30 ft-lbs=l 0.8 Deg F Temp@50 ft-lbs=54.9 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: U Fluence: n/cmA2 300 250

.0U)

,. 200 5

0 0

U-El 150 z

> 100 0

50 .

0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-75.00 5.00 8.72 -3.72

-45.00 14.00 13.48 - .52

-15.00 12. 00 20. 98 - 8.98

.00 36.00 25.95 10.05

15. 00 36.00 31.74 4.26

25. 00 49. 00 36.01 12.99

40. 00 48.00 42. 88 5. 12

50. 00 31. 00 47. 67 - 16.67

65. 00 51.00 54. 94 -3.94 C-8

n-CAPSULE U LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 80.00 54. 00 62. 01 - 8.01 1 0 0. 00 74. 00 70. 65 3.35 125.00 73. 00 79. 58 -6.58 150. 00 102.00 86. 23 15.77 200.00 97. 00 93. 89 3. 11 250. 00 99. 00 97. 06 1.94 Correlation Coefficient = .961 C-9

CAPSULE U LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 02:29 PM Page 1 Coefficients of Curve 2 A = 35.31 B = 35.31 C = 108.65 TO = 46.71 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=70.6 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mils=45.8 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: U Fluence: n/cmA2 200 150 W

E C

0 2 100 a) _ ,,,--D -_____________-

_ o =,

50

_____-'° ,

0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LB. Computed L.E. Differential

-75. 00 5. (00 66.7 9 - 1. 79

-45. 00 10. ( ° 11. 02 - 1.02

- 15.00 9. C00 17. 16 -8. 16

.00 27. C00 21. 00 6. 00 15.00 27. ( 0) 2 5. 2 8 1. 72 25.00 34. (00 2 8. 3 4 5. 66

40. 00 40. C00 33. 13 6. 87

50. 00 32. C00 3 6. 3 7 -4. 37 65.00 36. (00 441.19 -5. 19 C-10

CAPSULE U LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

80. 00 44. 00 45. 80 - 1. 80 100.00 49. 00 51. 36 -2. 36 125. 00 50. 00 57. 10 -7.10 150. 00 74.00 61. 44 12. 56 200. 00 68. 00 66. 65 1. 35 250. 00 65.00 68. 98 -3. 98 Correlation Coefficient = .962 C-11

CAPSULE U LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:35 AM Page 1 Coefficients of Curve 2 A =50. B=50.C=92.4 TO=62.1 D=O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 62.2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: U Fluence: n/cmA2 125 100 M 75 en (3

0)

V.

CD 50 25 0 4-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-75.00 5.00 4. 89 .11

-45.00 10. 00 8.96 1.04

-15.00 10. 00 15. 86 -5. 86

.00 25.00 20. 68 4.32 15.00 25.00 26.51 - 1.51

25. 00 40. 00 30.94 9.06

40. 00 40. 00 38.26 1.74

50. 00 40. 00 43.49 -3.49 65.00 50.00 51.57 - 1.57 C-12

II-CAPSULE U LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 IHeat: C3500-2 Orientation: LT Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

80. 00 55.00 59. 56 -4. 56 100.00 70. 00 69.43 .57 1 25. 00 70. 00 79. 60 -9. 60

.150. 00 100.00 87.02 12. 98 200. 00 100.00 95. 19 4. 81 250. 00 100. 00 98. 32 1. 68 Correlation Coefficient = .985 C-13

CAPSULE Y LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:13 AM Page 1 Coefficients of Curve 3 A = 51.1 B = 48.9 C=81.88 TO = 52.33 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=100.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=14.6 Deg F Temp@50 ft-lbs=50.5 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: Y Fluence: n/cmA2 300 250 n, 200 0

0 LL El 150 ca z

> 100 C.

_ I 50 n

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-75. 00 7.00 6. 37 . 63

-50. 00 15.00 9. 62 5.38

-25. 00 12.00 15.05 -3. 05

- 10. 00 17. 00 19. 72 -2.72

.00 25.00 23.51 1.49

10. 00 21.00 27. 85 -6. 85 25.00 45.00 35. 36 9.64

50. 00 45.00 49. 71 -4.71 65.00 57.00 58.61 - 1.61 c-1 4

CAPSULE Y LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B]1 Heat: C3500-2 Orientation: LT Capsule: Y Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

72. 00 70. 00 62. 63 7.37 100. 00 70. 00 76. 74 -6. 74 150. 00 96. 00 91. 76 4.24 200. 00 94. 00 97.42 -3.42 250. 00 ,1 106.00 99. 22 6.78 300. 00 105.00 99.77 5.23 Correlation Coefficient = .989 C-15

CAPSULE Y LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 02:30 PM Page 1 Coefficients of Curve 3 A = 34.43 B = 34.43 C = 77.76 TO = 45.5 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=68.9 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=46.8 Deg F Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: LT Capsule: Y Fluence: n/cmA2 200 150 0

& 100 -_

7E.

0 50 _

00

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential

-75. 00 4.00 2.97 1.03

-50. 00 11. 00 5.44 5.56

-25.00 6. 00 9.66 - 3.6 6

- 10. 00 12.00 13. 32 - 1.32

.00 18. 00 16. 30 1.70 10.00 16.00 19.72 -3.72

25. 00 30. 00 25. 55 4.45

50. 00 34.00 36.42 -2.42 65.00 42.00 42. 88 -. 88 C-16

R-CAPSULE Y LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: Y Fluerice: :n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

72. 00 47. 00 45. 72 1.28 100. 00 56. 00 55.25 . 75 150. 00 65. 00 64. 47 .5 3 200. 00 66. 00 67.58 - 1.58 250. 00 73. 00 68. 50 4.50 300. 00 65. 00 68.75 -3.75 Correlation Coefficient = .992 C-17

CAPSULE Y LOWER SHELL PLATE B8628-1 -(LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:35 AM Page 1 Coefficients of Curve 3 A = 50. B = 50. C = 67.76 TO = 77.75 D = O.OOE+00 Equation is A + B * [Tanh((T-To)!(C+DT))]

Temperature at 50% Shear = 77.8 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: Y Fluence: n/cmA2 125 100 S-75-I a) 0~ 50-25-0 - -i

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-75. 00 . 00 1.09 - 1. 09

-50. 00 5.00 2. 25 2.75

-25. 00 10.00 4. 60 5.40

.10.00 10. 00 6. 98 3.02

.00 10. 00 9. 15 . 85 10.00 10.00 11.92 -1. 92

25. 00 20. 00 17.41 2.59

50. 00 30. 00 30. 59 .59 65.00 40. 00 40. 70 - .70 C-18

CAPSULE Y LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: LT Capsule: Y Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

72. 00 45.00 45. 76 -. 76 100.00 60. 00 65. 85 -5. 85 150. 00 100. 00 89. 40 10. 60 200. 00 100. 00 97. 36 2.64 250. 00 100.00 99. 38 .62 300. 00 100.00 99. 86 .14 Correlation Coefficient = .996 C-19

CAPSULE X LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:13 AM Page 1 Coefficients of Curve 4 A = 44.1 B = 41.9 C = 75.94 TO = 64.75 D =O.0OE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=86.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=38.2 Deg F Temp@50 ft-lbs=75.6 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: X Fluence: n/cmA2 300 250 o

a- 200 0

0 L

@150 C) z 8 100

___-------- _---------- 1--  ; , . ,-------

I--.,.- --

50 ---- ---- ---- --

0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 80. 00 6. 00 4.01 1.99

-40. 00 11. 00 7. 19 3. 81

.00 18.00 15.09 2. 91 15.00 22. 00 20. 00 2.00 25.00 15. 00 23.97 -8. 97 25.00 20. 00 23.97 -3.97

35. 00 41. 00 28.48 12.52 50.00 30.00 36. 06 -6.06

50. 00 39. 00 36. 06 2.94 C-20

IL-CAPSULE X LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

75. 00 47. 00 49. 72 -2.72 100. 00 59. 00 62. 26 -3.26 125.00 73. 00 71. 77 1. 23 150.00 88. 00 77.97 10.03 200.00 76. 00 83. 69 -7.69 250.00 95.00 85.37 9.63 Correlation Coefficient = .975 C-21

CAPSULE X LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 02:30 PM Page 1 Coefficients of Curve 4 A = 32.28 B = 32.28 C = 94.48 TO = 82. D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=64.6 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=90.0 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: X Fluence: n/cmA2 200 150 E .A 0

C 0

2 100 50 A

.A n

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

- 80. 00 2.00 2.03 -. 03

-40.00 2.00 4.54 -2.54

.00 1 1. 00 9.67 1.33 15.00 14.00 12.58 1. 42 25.00 6. 00 14. 87 - 8.87 25.00 10.00 14.87 -4.87 35.00 24.00 17.42 6.58

50. 00 26. 00 21.74 4.26

50. 00 25.00 21.74 3.26 C-22

it-CAPSULE X LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

75. 00 28. 00 29. 89 - 1. 89 100.00 38. 00 38.35 -. 35 125.00 45.00 46. 03 - 1. 03 150. 00 54. 00 52. 18 1. 82 200. 00 54. 00 59. 64 -5.64 250.00 67.00 62. 76 4. 24 Correlation Coefficient = .979 C-23

CAPSULE X LOWER SHELL PLATE B8628 -1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:35 AM Page 1 Coefficients of Curve 4 A = 50. B = 50. C = 62.44 TO = 69.29 D = O.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 69.3 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: X Fluence: ndcmA2 125 100 75 Cn a)

I- 50 25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 80. 00 2. 00 .83 1.17

-40. 00 5.00 2. 93 2.07

.00 10.00 9. 80 .20 1S. 00 15. 00 14. 95 .05

25. 00 15.00 19.49 -4. 49

25. 00 20. 00 19.49 .51

35. 00 30. 00 25.01 4.99

50. 00 35.00 35. 03 -. 03

50. 00 40. 00 35.03 4.97 C-24

CAPSULE X LOWER SHELL PLATE B8628 -1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

75. 00 45. 00 54. 56 -9.56 100. 00 75. 00 72.78 2.22 125. 00 85. 00 85. 62 -. 62 150. 00 100.00 92. 99 7.01 200. 00 100.00 98.50 1.50 250. 00 100.00 99. 69 .31 Correlation Coefficient = .994 C-25

CAPSULE W LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 11:13 AM Page 1 Coefficients of Curve 5 A = 43.1 B = 40.9 C = 81.94 TO = 74.98 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=84.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=47.8 Deg F Temp@50 ft-lbs=89.0 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: W Fluence: n/cmA2 300 250 n

-, 200 1

4-.0 0

0 UL E 150 Lu z

> 100 50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-50. 00 7.00 5.90 1. 10

- 25.00 11. 00 8.76 2. 24

.00 21.00 13.51 7.49 25.00 15.00 20. 85 -5.85

40. 00 27.00 26. 63 .37

50. 00 42. 00 31. 00 11. 00 50.00 22. 00 31. 00 -9. 00 75.00 42. 00 43. 11 - 1. 11 100. 00 52. 00 55.22 -3.22 C-26

CAPSULE W LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 125.00 61. 00 65. 37 -4. 37 150.00 77. 00 72. 70 4. 30 175.00 85.00 77.45 7.55 200.00 81.00 80. 31 .69 225.00 85.00 81.95 3.05 Correlation Coefficient = .981 C-27

CAPSULE W LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/17/2004 02:30 PM Page 1 Coefficients of Curve 5 A = 34.69 B = 34.69 C = 91.2 TO = 73.83 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=69.4 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mnils=74.7 Deg F Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: LT Capsule: W Fluence: n/cmA2 200 150 C

0I-2 100 50 V ,7.v .

4.

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

- 50. 00 6. 00 4.31 1. 69

- 25. 00 8. 00 7. 13 .87 00 15.00 1 1.47 3.53

25. 00 11. 00 17.71 -6. 71

40. 00 24.00 22. 38 1. 62

50. 00 39.00 25. 83 13. 17

50. 00 17.00 25. 83 -8. 83

75. 00 30.00 35. 14 -5. 14 100. 00 45. 00 44. 38 .62 C-28

CAPSULE W LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: LT Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 125.00 52.00 52. 34 -. 34 150. 00 61.00 58.40 2. 60 175. 00 65.00 62.58 2.42 200. 00 65.00 65.28 -. 28 225.00 64.00 66. 95 -2.95 Correlation Coefficient = .973 C-29

CAPSULE W LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11117/2004 11:35 AM Page 1 Coefficients of Curve 5 A = 50. B = 50. C = 63.08 TO = 86.41 D = 0.00E+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 86.5 Plant: Vogte 2 Material: SA533B 1 Heat: C3500-2 Orientation: LT Capsule: W Fluence: n/cmA2 125 100 co U) 75 I

S.I U) 50 .7 CL r

25 0 *~~ - --

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Diffrential

-50. 00 2. 00 I. 3 1 .69

-25. 00 5. 00 2. 84 2. 16

.00 10. 00 6. 07 3.93 25.00 15.00 12. 49 2.51

40. 00 20. 00 18.67 1.33

50. 00 25.00 23.97 1.03 5 0. 00 20. 00 23.97 -3. 97 75.00 40. 00 41. 06 - 1. 06 100. 00 60. 00 60. 61 -. 61 C-30

CAPSULE W LOWER SHELL PLATE B8628-1 (LONGITUDINAL)

Page 2 Plant: Vogtle 2 Material: SA533BI Heat: C3500-2 Orientation: LT Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 125.00 75.00 77. 27 -2. 27 150. 00 90. 00 88. 25 1.75 175. 00 100.00 94. 32 5.68 200. 00 100. 00 97. 34 2. 66 225. 00 100. 00 98.78 1.22 Correlation Coefficient = .998 C-31

UNIRRADIATED LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 01:36 PM Page 1 Coefficients of Curve 1 A = 36.1 B = 33.9 C = 67.14 TO = 40.81 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=70.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=28.6 Deg F Temp@50 ft-lbs=70.1 Deg F Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: TL Capsule: UN[RR Fluence: nlcmA2 300 250

, 200 10.a 0

L 2' 150 z

8 100 50 1* - . - _

n

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-80. 00 5. 00 4. 01 .99

- 80. 00 5.00 4. 01 .99

-30. 00 16.00 9.54 6. 46

-30. 00 18.00 9.54 8.46

.00 19.00 17.71 1.29

.00 22. 00 17.71 4. 29

.00 24. 00 17.71 6. 29

30. 00 21. 00 30. 69 -9. 69

30. 00 27. 00 30. 69 -3.69 C-32

UNIRRADIATED LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

30. 00 33. 00 30. 69 2.31

60. 00 38.00 45. 54 -7.54

60. 00 38.00 45.54 -7.54

60. 00 41. 00 45.54 -4. 54 100. 00 56. 00 60. 08 -4. 08 100. 00 64.00 60. 08 3.92 100. 00 73. 00 60. 08 12. 92 120. 00 66. 00 64. 15 1. 85 120.00 74. 00 64. 15 9. 85 120.00 79.00 64. 15 14. 85 160.00 67.00 68. 11 -1. 1I1 160. 00 68. 00 68. 11 . I I 160.00 68. 00 68.11 - . I I 240. 00 63.00 69. 82 - 6. 82 240. 00 69. 00 69. 82 -. 82 300. 00 66.00 69. 97 -3. 97 300. 00 70. 00 69.97 . 03 350. 00 62. 00 69. 99 - 7.99 350. 00 65.00 69.99 -4. 99 400. 00 72. 00 70. 00 2. 00 400. 00 75.00 70. 00 5. 00 450. 00 71. 00 70. 00 1. 00 450. 00 76. 00 70. 00 6. 00 Correlation Coefficient = .968 C-33

UNIRRADIATED LOWVER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:49 PM Page 1 Coefficients of Curve 1 A = 32.67 B = 32.67 C = 72.88 TO = 38.79 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=65.3 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mnils=44.0 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 200 150 o) 0 Z;

a 100 1- 50 I 0 8 50 0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

80. 00 2. 00 2.42 -. 42

80. 00 3.00 2.42 .58

30. 00 14. 00 8.59 5.41

30. 00 14. 00 8.59 5.41

. 00 18.00 16. 76 1.24

.00 20. 00 16. 76 3.24

.00 20. 00 16. 76 3.24 30.00 21.00 28.75 -7.75 30.00 26. 00 28.75 -2. 75 C-34

1.f UNIRRADIATED LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: UNIRR Fluence: nrcmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

30. 00 31.00 28. 75 2. 25

60. 00 35. 00 41.92 -6. 92

60. 00 38. 00 41. 92 -3.92

60. 00 38.00 41.92 -3.92 100. 00 52. 00 55. 08 -3.08 100. 00 56.00 55.08 .92 100. 00 64. 00 55.08 8.92 120. 00 60. 00 58. 99 1.01 120. 00 68. 00 58. 99 9. 01 120. 00 71.00 58. 99 12.01 160. 00 58. 00 63. 08 -5.08 160. 00 64. 00 63. 08 .92 160. 00 64. 00 63. 08 .992 240. 00 60. 00 65.08 - 5.0 8 240. 00 67. 00 65.08 1.92 300. 00 68. 00 65.29 2. 71 300. 00 70. 00 65.29 4.71 350. 00 59.00 65.33 -6. 33 350. 00 62. 00 65. 33 -3.33 400. 00 65.00 65. 34 -. 34 400.00 60. 00 65. 34 -5. 34 450. 00 63.00 65. 34 -2. 34 450. 00 66. 00 65. 34 .66 Correlation Coefficient = .977 C-35

UNIRRADIATED LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:31 PM Page 1 Coefficients of Curve 1 A = 50. B = 50. C = 35.5 TO = 66.46 D =O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 66.5 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 125 100 I-to 75 U,

a, 02 50 25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

80. 00 . 00 .03 - .03

80. 00 .00 .03 -. 03

30. 00 5.00 43 4.57 30.00 5.00 .43 4.57

.00 10.00 2. 31 7.69

.00 10.00 2.31 7. 69

. 00 10. 00 2.31 7. 69 30.00 25.00 11. 36 13. 64

30. 00 10.00 11.36 - 1.36 C-36

UNIRRADIATED LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

30. 00 10.00 11.36 - 1. 36

60. 00 35. 00 40. 99 -5. 99

60. 00 40. 00 40. 99 -. 99

60. 00 35. 00 40. 99 -5. 99 100. 00 80. 00 86. 87 -6. 87 100. 00 95. 00 86. 87 8.13 100. 00 95. 00 86. 87 8.13 120. 00 95.00 95. 33 - .33 120. 00 100. 00 95. 33 4.67 120. 00 100. 00 95. 33 4.67 160. 00 100.00 99.49 .51 160.00 100.00 99.49 .51 160. 00 100.00 99.49 .51 240. 00 100. 00 99. 99 .01 240. 00 100. 00 99. 99 .01 300. 00 100.00 100. 00 . 00 300. 00 100. 00 100. 00 .00 350. 00 100. 00 100.00 . 00 350. 00 100. 00 100.00 . 00 400. 00 100. 00 1 00. 00 .00 400. 00 100.00 100.00 .00 450. 00 100.00 100.00 .00 450.00 100. 00 100.00 .00 Correlation Coefficient = .995 C-37

CAPSULE U LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 01:36 PM Page 1 Coefficients of Curve 2 A = 40.6 B = 38.4 C = 114.67 TO = 53.93 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=79.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=21.5 Deg F Temp@50 ft-lbs=82.6 Deg F Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: TL Capsule: U Fluence: n/cmA2 300 250 1, 200 0

0 LL E- 150 II I- I- - -

z

> 100 C.)

50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-75.00 6.00 9. 53 -3.53

-50. 00 12.00 12.98 -. 98

-25.00 17.00 17. 68 -. 68

.00 23. 00 23.77 -. 77

25. 00 36.00 31.11 4. 89

35. 00 38.00 34. 32 3.68

50. 00 40. 00 39.29 .71 65.00 45. 00 44.30 .70

80. 00 43. 00 49. 18 -6. 18 C-38

- X CAPSULE U LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 100. 00 50.00 55.25 -5.25 120.00 66. 00 60.56 5.44 150. 00 65.00 66. 89 - 1. 89 200. 00 74. 00 73.43 .57 275.00 82. 00 77.41 4. 59 375. 00 81.00 78. 72 2. 28 Correlation Coefficient = .990 C-39

CAPSULE U LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:49 PM Page 1 Coefficients of Curve 2 A = 28.55 B = 28.55 C = 97.06 TO = 30.7 D = O.OOE+00 Equation is A + B .* [Tanh((T-To)/(C+DT))]

Upper Shelf LE.=57.1 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mnils=53.1 Deg F Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: TL Capsule: U Fluence: nIcmA2 200 150 .4.

0 E

C 0

a 50 00

-~ - I

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed LE. Differential

-75. 00 4.00 5. 81 - 1.81

-50. 00 10. 00 9. 10 .90

-25. 00 12.00 13. 76 - 1. 76

.00 22.00 19. 81 2. 19

25. 00 30.00 26. 88 3. 12

35. 00 29.00 29. 81 -. 81

50. 00 34.00 34. 15 -. 15 65.00 38.00 38.24 -. 24

80. 00 38.00 41. 92 -3. 92 C-40

CAPSULE U LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533BI Heat: C3500-2 Orientation: TL Capsule: U Flueiice: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 100. 00 42. 00 46. 05 -4. 05 120. 00 55. 00 49. 27 5.73 150.00 52. 00 52. 60 -. 60 200. 00 61. 00 55.41 5.59 275.00 55. 00 56. 73 - 1.73 375. 00 54. 00 57. 05 -3.05 Correlation Coefficient = .985 C-41

CAPSULE U LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:31 PM Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 82.49 TO = 65.43 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 65.5 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: TL Capsule: U Fluence: n/cmA2 125 100 co a) 75 CD, a,

CD IL. 50 25 0 l

-300 -200 -100 0 100 200 300 400 500 600

, Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

75. 00 5.00 3.21 1.79 50.00 10. 00 5.74 4.26

25. 00 10.00 10.04 - :04

.00 15.00 16. 99 - 1.9 9

25. 00 30. 00 27.28 2.72

35. 00 35.00 32. 35 2.65

50. 00 40. 00 40.75 -. 75

65. 00 45. 00 49.74 -4.74 80.00 60. 00 58.74 1.26 C-42

1.

CAPSULE U LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 100. 00 65.00 69. 81 -4.81 120. 00 80. 00 78. 97 1.03 150. 00 95.00 88. 60 6.40 200. 00 1 00. 00 96. 31 3.69 275. 00 100.00 99. 38 .62 375. 00 100. 00 99.95 .05 Correlation Coefficient = .996 C-43

CAPSULE Y LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 01:36 PM Page 1 Coefficients of Curve 3 A = 37.6 B = 35.4 C = 96.69 TO = 51.57 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=73.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=30.5 Deg F Temp@50 ft-lbs=87.0 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: Y Fluence: n/cmA2 300 250 tn

=, 200 10-0 0

0 LL El 150 a) z

>0100 50 0 I.. .  ; - T

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVFN Computed CVN Differential

-75. 00 11. 00 7.01 3.99

-50. 00 9.00 9.92 -. 92

-25.00 22. 00 14.26 7.74

.00 24. 00 20.33 3. 67

10. 00 19. 00 23.26 -4.26 25.00 25.00 28. 11 -3. 11

40. 00 27.00 33. 39 -6.39

50. 00 40. 00 37. 03 2. 97 65.00 43. 00 42.49 .51 C-44

CAPSULE Y LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: Y Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

72. 00 45. 00 44. 97 .03 100. 00 52. 00 53.98 - 1. 98 150. 00 70. 00 64. 82 5. 18 200. 00 74. 00 69. 86 4. 14 250. 00 73. 00 71. 85 1. 15 300. 00 76. 00 72. 59 3.41 Correlation Coefficient = .987 C-45

CAPSULE Y LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:49 PM Page 1 Coefficients of Curve 3 A = 31.92 B = 31.92 C = 104.1 TO = 52.77 D = O.O0E+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=63.8 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mnils=62.9 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: Y Fluence: n/cmA2 200 150 W

E C

50 ua 0 ..........

16.

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

-75. 00 6. 00 5. 05 95

-50. 00 5. 00 7.78 - 2 78

- 25. 00 15. 00 11.70 3. 30

.00 18. 00 16.99 I1. 01

10. 00 19. 00 19. 49 49

25. 00 20. 00 23. 60 - 3. 60

40. 00 27. 00 28. 02 - 1. 02

50. 00 33. 00 31. 07 1. 93 65.00 38. 00 35. 65 2. 35 C-46

1I-CAPSULE Y LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: Y Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

72. 00 36.00 37. 75 - 1.75 100. 00 46. 00 45.48 .52 150. 00 56. 00 55. 30 .70 200. 00 59. 00 60. 27 - 1.27 250. 00 60.00 62. 42 -2. 42 300. 00 66. 00 63. 29 2.71 Correlation Coefficient = .994 C-47

CAPSULE Y LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:31 PM Page 1 Coefficients of Curve 3 A=50. B=50.C=74.35 TO=83. D=O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 83.0 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: Y Fluence: n/cmA2 125 100 a) 75-Cn V

I.

a) a-25- 500 30 ....-.... 1

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-75.00 5.00 1.41 3.59

-50.00 5.00 2.72 2.28

-25. 00 10.00 5. 19 4. 81

.00 15.00 9. 69 5.31

10. 00 15.00 12.31 2. 69 25.00 20.00 17. 36 2.64

40. 00 20.00 23.93 -3.93

50. 00 30. 00 29. 16 .84 65.00 35.00 38. 13 - 3. 13 C-48

a-CAPSULE Y LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: Y Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

72. 00 45. 00 42. 66 2.34 100. 00 50. 00 61. 24 - 11. 24 150. 00 100. 00 85. 84 14. 16 200. 00 100. 00 95. 88 4.12 250. 00 100. 00 98. 89 1.11 300.00 100.00 99. 71 .29 Correlation Coefficient = .990 C-49

CAP SULE X LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 01:36 PM Page 1 Coefficients of Curve 4 A = 33.6 B = 31.4 C = 79.36 TO = 67.47 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=65.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp @30 ft-lbs=58.4 Deg F Temp@50 ft-lbs=l 13.5 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: X Fluence: n/cmA2 300 250 W

- 200 o

14-.

LL 50

> 100 50 El10

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-90. 00 4.00 3.36 .64

-50. 00 15.00 5.29 9.71

.00 13.00 11.90 1. 10 15.00 13.00 15.42 - 2. 42 25.00 23. 00 18.24 4.76

35. 00 14.00 21.43 -7. 43

50. 00 26.00 26. 80 - 80 65.00 28. 00 32. 62 -4. 62 75.00 38.00 36.57 1.43 C-SO

CAPSULE X LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: TL Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

85. 00 42. 00 40.43 1.57 100. 00 53. 00 45. 80 7.20 150. 00 53.00 58. 03 -5. 03 200. 00 64. 00 62. 85 1. 15 250. 00 64. 00 64. 38 - . 38 275. 00 67.00 64. 67 2. 33 Correlation Coefficient = .978 C-51

CAPSULE X LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:49 PM Page 1 Coefficients of Curve 4 A = 26.2 B = 26.2 C = 74.38 TO = 68.23 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=52.4 Lower Shelf L.E.=.O(Fixed)

Temp.@L.E. 35 mils=94.3 Deg F Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: TL Capsule: X Fluence: n/cmA2 200 150 E

0 EL100 50 I A' n

-300

.1____________ &

0 "21 AX 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

-90. 00 .00 .73 -. 73

-50. 00 7.00 2. 09 4.91

.00 7.00 7.21 - . 21 15.00 8.00 10.11 -2. 11

25. 00 17.00 12.48 4.52

35. 00 10.00 15.22 -5. 22

50. 00 19.00 19.90 -. 90

65. 00 26.00 25.06 . 94 75.00 30. 00 28.58 1.42 C-52

CAPSULE X LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

85. 00 32.00 32. 01 -. 01 100.00 38.00 36.76 1. 24 150. 00 44.00 47. 16 3. 16 200. 00 54. 00 50. 92 3.08 250. 00 53.00 52.01 .99 275. 00 50. 00 52.20 2. 20 Correlation Coefficient = .989 C-53

CAPSULE X LOWER SHELL PLATE B8628-2 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:31 PM Page 1 Coefficients of Curve 4 A = 50. B = 50. C = 53.99 TO = 66.11 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 66.2 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: TL Capsule: X Fluence: nI/cmA2 125 100 L-a) 75

-C CD, a)

IL 50 25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 90. 00 2. 00 .31 1.69

-50. 00 5.00 1. 34 3.66

.00 10. 00 7. 95 2.05 15.00 10. 00 13. 09 - 3. 09 25.00 20. 00 17. 90 2. 10 35.00 15. 00 24. 01 -9. 01 50.00 40. 00 35.51 4.49 65.00 45.00 48. 98 -3. 98 75.00 65.00 58. 16 6.84 C-54

CAPSULE X LOWER SHELL PLATE B8628-2 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

85. 00 70.00 66. 82 3. 18 1 0 0. 00 75.00 77. 83 -2. 83 150. 00 85.00 95.72 - 10. 72 200. 00 1 00. 00 99. 30 .70 250. 00 1 00. 00 99. 89 .11 275. 00 100.00 99. 96 .04 Correlation Coefficient = .992 C-55

CAPSULE W LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 01/18/2005 03:14 PM Page 1 Coefficients of Curve 1 A = 35.6 B = 33.4 C = 93.76 TO = 89.91 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=69.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=74.1 Deg F Temp@50 ft-lbs=133.2 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: W Fluence: n/cmA2 300 250 u,

, 200 a

0 0

IL

150 a,

w z

> 100 50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-75.00 5. 00 4. 12 .88

- 25.00 8.00 7.50 .50

.00 10. 00 10.76 .76 25.00 21.00 15.58 5. 42

50. 00 26. 00 22. 18 3. 82

75. 00 29. 00 30.33 - 1.33

75. 00 24. 00 30. 33 -6. 33 100. 00 40. 00 39. 18 . 82 125. 00 42. 00 47.55 -5.55 C-56

tL-CAPSULE W LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 150. 00 60. 00 54. 49 5.51 200. 00 61. 00 63. 18 - 2.18 225. 00 72. 00 65. 46 6. 54 250. 00 74. 00 66. 87 7. 13 275. 00 61. 00 67. 74 -6. 74 275. 00 70. 00 67. 74 2. 26 Correlation Coefficient = .983 C-57

CAPSULE W LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:50 PM Page 1 Coefficients of Curve 5 A = 27.92 B = 27.92 C = 95.34 TO = 72.36 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=55.8 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=97.1 Deg F Plant: Vogle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: W Fluence: n/cmA2 200 I

150 C

0 E 100 1..

-0 50 C7 - -V -

V 1

'7, V V-I

.71

-7 17 I

- -.- V- - 11.17 0 I . . II

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

-75. 00 4.00 2.43 1.57

- 25. 00 5.00 6.41 - 1.41

.00 10. 00 10. 04 - .04

25. 00 18.00 15.09 2. 91

50. 00 23.00 21.49 1.51 75.00 28.00 28.69 - . 69

75. 00 23.00 28. 69 -5. 69 1 00. 00 37. 00 35. 80 1.20 125.00 42. 00 41. 94 .06 C-58

1.l CAPSULE W LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 150. 00 52. 00 46. 68 5.32 200. 00 45.00 52. 25 -7. 25 225.00 56. 00 53. 66 2. 34 250. 00 61.00 54. 53 6.47 275. 00 53. 00 55. 06 -2. 06 275. 00 52. 00 55. 06 -3. 06 Correlation Coefficient = .982 c-59

CAPSULE W LOWER SHELL PLATE B8628-1 (TRANSVERSE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/18/2004 03:31 PM Page I Coefficients of Curve 5 A = 50. B = 50. C = 64.89 TO = 1003 D =O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 100.4 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: W Fluence: n/cmA2 125 100 V-V. .-.- - -

I V "

I I

I M 75 II CD M.7 I

C, I V I 0~ 50 I

i I

I I

I V

I 25 1:7 t

V .- 1 ,

0 I I

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-75. 00 2.00 .45 1.55

- 25. 00 5.00 2. 06 2.94

.00 10.00 4.35 5.65 25.00 15.00 8.94 6.06

50. 00 20. 00 17.50 2.50 75.00 30. 00 31. 43 -1.43

75. 00 25.00 31. 43 -6.43 1 00. 00 50.00 49. 77 .23 125. 00 65.00 68. 16 -3. 16 C-60

CAPSULE W LOWER SHELL PLATE B8628-1 (TRANSVERSE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: TL Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 150. 00 90. 00 82. 22 7.78 200. 00 95. 00 95.58 -. 58 225.00 100. 00 97.90 2. 10 250. 00 100. 00 99. 02 .98 275. 00 100. 00 99. 54 .46 275. 00 100. 00 99. 54 .46 Correlation Coefficient = .996 C-61

UNIRRADIATED (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 01:20 PM Page 1 Coefficients of Curve 1 A = 47.1 B = 44.9 C = 65.02 TO = 6.8 D = O.OOE+OO Equation is A'+ B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=92.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-19.2 Deg F Temp@50 ft-lbs=1 1.1 Deg F Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: UNIRR Fluence: n/cmn2 300 250 o

8, 200 1

0 0

U- '1

%150 C)

UJ z

> 100 50 I_ _ _

0o _ _ _ _ _ _ _ _ I_ _I_ i 1 S X 1 ,1a~o, S0 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 100. 00 5.00 5.44 44

- 100. 00 7.00 5.44 1.56

- 100. 00 7.00 5.44 1.56

- 60. 00 11. 00 12.40 - 1. 40

- 60. 00 11. 00 12.40 - 1.40

- 60. 00 27. 00 12.40 14. 60

-30. 00 8.00 24.09 - 16. 09

-30. 00 9.00 24. 09 -15. 09

-30. 00 20. 00 24.09 -4. 09 C-62

UNIRRADIATED (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: UNTRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 20. 00 15.00 29. 57 14.57

- 20.00 38.00 29. 57 8.43

- 20.00 49. 00 29. 57 19. 43

. 00 35.00 42. 42 -7. 42

. 00 44. 00 42. 42 1.58

. 00 57. 00 42. 42 14. 58

30. 00 54. 00 62. 47 - 8.47

30. 00 65.00 62. 47 2. 53

30. 00 75.00 62.47 12.53

80. 00 75.00 83. 45 - 8. 45

80. 00 79.00 83. 45 -4. 45

80. 00 84.00 83. 45 .55 120.00 86. 00 89. 32 -3. 32 120. 00 88. 00 89. 32 - 1. 32 120. 00 89. 00 89. 32 -. 32 160.00 90. 00 91.20 - 1.20 160. 00 90.00 91.20 - 1. 20 160. 00 94.00 91.20 2. 80 240.00 92. 00 91. 93 .07 240. 00 92.00 91. 93 .07 300. 00 92.00 91. 99 .01 300. 00 92. 00 91. 99 .01 Correlation Coefficient = .971 C-63

UNIRRADIATED (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 04:15 PM Page 1 Coefficients of Curve 1 A = 40.21 B = 40.21 C = 68.68 TO = 7.85 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=80.4 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 nils=-1.0 Deg F Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 200 150 on E

9; 0

r.

E 100 6

50 0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 100. 00 1. 00 3.33 -2. 33 100. 00 3. 00 3.33 - . 33 100. 00 3.00 3.33 - . 33

- 60. 00 9. 00 9.79 -. 79

- 60. 00 7.00 9.79 -2. 79

- 60. 00 22. 00 9.79 12.21

-30. 00 9. 00 20. 05 - 1 1. 05

-30. 00 10. 00 20. 05 - 10. 05

-30. 00 16.00 20.05 -4. 05 C-64

UNIRRADIATED (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

-20. 00 11. 00 24. 74 - 13.74

- 20.00 34. 00 24. 74 9. 26

- 20. 00 39. 00 24.74 14. 26

. 00 30.00 35. 63 -5. 63

.00 38.00 35. 63 2. 37

.00 45.00 35. 63 9. 37 30.00 46. 00 52.74 -6.74 30.00 57. 00 52. 74 4. 26

30. 00 62. 00 52. 74 9. 26

80. 00 64.00 71. 65 -7.65

80. 00 68. 00 71. 65 -3.65

80. 00 72. 00 71.65 .35 120. 00 74. 00 77.46 -3.46 120.00 75. 00 77.46 -2.46 120.00 78. 00 77. 46 .54 160.00 81.00 79.47 1.53 160.00 78.00 79.47 - 1. 47 160.00 82. 00 79.47 2. 53 240. 00 81. 00 80. 32 .68 240. 00 83. 00 80. 32 2. 68 300.00 82.00 80.40 1. 60 300. 00 83.00 80.40 2. 60 Correlation Coefficient = .977 C-65

UNIRRADIATED (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 03:49 PM Page 1 Coefficients of Curve I A = 50. B = 50. C = 61.01 TO = 28.04 D = O.00E+0O Equation is A + B * [Tanh((T-To)/(C+DT)))

Temperature at 50% Shear = 28.1 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: UNIRR Fluence: n/cm42 125 100 I-.

to 75

0. 50 25 0 4-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 100. 00 .00 1.48 - 1. 48

- 100. 00 .00 1. 48 - 1.48

- 100. 00 .00 1.48 - 1. 48

- 60. 00 5.00 5.28 - .28

- 60. 00 5.00 5.28 - .28

- 60. 00 10.00 5.28 4.72

-30. 00 10. 00 12.98 -2. 98

-30. 00 15.00 12.98 2. 02

-30. 00 10. 00 12.98 -2. 98 C-66

AL UNIRRADIATED (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 20. 00 15. 00 17. 15 - 2. 15

- 20. 00 20. 00 17. 15 2. 85

- 20. 00 25. 00 17. 15 7. 85

. 00 25. 00 28.51 -3.51

. 00 20. 00 28.51 -8. 51

.00 35. 00 28.51 6. 49

30. 00 35.00 51. 60 - 16. 60

30. 00 55.00 51. 60 3.40

30. 00 65.00 51. 60 13.40

80. 00 80. 00 84. 60 -4.60

80. 00 85.00 84. 60 .40

80. 00 90. 00 84. 60 5.40 120.00 95.00 95. 32 -. 32 120. 00 95. 00 95. 32 -. 32 120. 00 95.00 95. 32 -. 32 160. 00 100.00 98.70 1. 30 160. 00 100.00 98. 70 1. 30 160. 00 1 00. 00 98. 70 1. 30 240. 00 100.00 99. 90 . 10 240. 00 100.00 99. 90 . 10 300. 00 100. 00 99. 99 .01 300. 00 100. 00 99. 99 .01 Correlation Coefficient = .992 C-67

CAPSULE U (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 01:20 PM Page 1 Coefficients of Curve 2 A = 50.1 B = 47.9 C = 82.01 TO =.14 D = O.OOE+00 Equation is A + B* [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=98.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-36.5 Deg F Temp@50 ft-lbs=.0 Deg F Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: U Fluence: nlcmA2 300 250 uW

-, 200 1

0 0

UL El 150 z

8 100 50 0 *.=

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-75.00 7.00 15.42 - 8.42

-50. 00 14. 00 23. 99 -9. 99

- 25.00 20. 00 35. 86 - 15. 86

- 20. 00 58.00 38.57 19.43

- 10. 00 54.00 44. 21 9.79

.00 55.00 50. 02 4.98

10. 00 63.00 55. 83 7. 17 25.00 57.00 64. 19 - 7. 19

40. 00 64.00 71.71 -7.71 C-68

CAPSULE U (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

60. 00 82. 00 79. 94 2. 06

80. 00 84.00 86. 04 -2. 04 100. 00 83.00 90. 29 -7. 29 150. 00 96.00 95.58 . 42 200. 00 95. 00 97. 27 -2. 27 275. 00 104. 00 97. 88 6. 12 Correlation Coefficient = .952 C-69

CAPSULE U (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 04:15 PM Page 1 Coefficients of Curve 2 A = 36.28 B = 36.28 C = 82.97 TO = 2.59 D = O.OOE+00 Equation is A + B * [Tanh((T-To)l(C+DT))]

Upper Shelf L.E.=72.6 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=-.3 Deg F Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: U Fluence: n/cmA2 200 150 0

E 100 r- 50 9

50 00

- 0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _--tr ------ - _ _ _ _ _ _ _ _ _ _ _ _ _

0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

-75. 00 3.00 9.69 -6. 69

-50. 00 9.00 15. 94 - 6.94

- 25. 00 19.00 24.64 -5. 64

- 20. 00 38.00 26. 64 11. 36

- 10. 00 38.00 30. 81 7. 19

.00 39. 00 35. 14 3. 86

10. 00 40. 00 39.51 .49

25. 00 39. 00 45. 84 -6. 84 40.00 48.00 51.61 -3.61 C-70

CAPSULE U (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

60. 00 62. 00 58.01 3.99

80. 00 61.00 62. 83 - 1. 83' 100. 00 61. 00 66. 22 -5.22 150. 00 73.00 70.53 2.47 200. 00 71.00 71.93 - .93 275.00 76.00 72. 45 3.55 Correlation Coefficient = .969 C-71

CAPSULE U (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 03:49 PM Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 59.67 TO = -4.16 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = -4.1 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: U Fluence: n/cmA2 125 100 Ca 75 s

(n I-U CD

0. 50 25 0 -

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-75. 00 5. 00 8.52 -3. 52

-50. 00 10. 00 17.71 -7. 71

- 25. 00 15. 00 33.21 - 18.21

- 20. 00 55. 00 37.03 17.97

- 10. 00 55.00 45. 12 9. 88

.00 55. 00 53.48 1.52

10. 00 65.00 61.65 3.35

25. 00 60. 00 72. 66 - 12.66

40. 00 85.00 81.46 3.54 C-72

CAPSULE U (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

60. 00 90. 00 89.57 . 43

80. 00 90. 00 94. 38 -4. 38 1 00. 00 90. 00 97.04 -7. 04 150. 00 100.00 99. 43 .57 200. 00 100.00 99. 89 .11 275. 00 100. 00 99. 99 .01 Correlation Coefficient = .965 C-73

CAPSULE Y (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 01:20 PM Page 1 Coefficients of Curve 3 A = 44.1 B = 41.9 C = 66.07 TO = 22.56 D = 0.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=86.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-.5 Deg F Temp@50 ft-lbs=32.0 Deg F Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: Y Fluence: n/cm^n2 300 250 n

- 200 a

0 0

El 150 C.

LU z

>' 100

._ . _ . .. . ° . . . ................... _

50 ..

_ G ._ -........ -' °-1 °,,

0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-75.00 7.00 6.36 .64

-50. 00 10.00 10. 59 - .59

-25. 00 12.00 18.26 - 6. 26

- 10. 00 33. 00 24.98 8.02

.00 34.00 30. 32 3.68

10. 00 16.00 36.23 - 20.23 15.00 41.00 39.33 1.67 25.00 60. 00 45. 65 14. 35

50. 00 61.00 60. 57 .43 C-74

CAPSULE Y (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: Y Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

72. 00 68. 00 70. 67 -2. 67 100. 00 78. 00 78. 67 -. 67 150. 00 76.00 84.27 - 8.27 200. 00 85.00 85. 61 -. 61 250. 00 83.00 85. 91 -2. 91 300. 00 89.00 85. 98 3.02 Correlation Coefficient = .967 C-75

CAPSULE Y (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 04:15 PM Page 1 Coefficients of Curve 3 A = 35.51 B = 35.51 C = 67.92 TO = 17.15 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=7 1.0 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mnils=16.2 Deg F Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: Y Fluence: n/cmA2 200 150 In r-50 50 16

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input L.E. Computed LE. Differential

-75. 00 6.00 4.42 1.58

-50. 00 8. 00 8.64 - . 64

-25. 00 10.00 15.93 -5.93

- 10.00 28.00 22. 03 597

.00 28. 00 26. 73 1.27

10. 00 17. 00 31.79 - 14.79 15.00 33.00 34. 39 -1.39

25. 00 58.00 39. 60 18.40

50. 00 51. 00 51. 46 - .46 C-76

CAPSULE Y (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: Y Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

72. 00 52. 00 59.24 -7. 24 100. 00 66.00 65. 33 . 67 150. 00 67.00 69. 63 -2. 63 200. 00 68. 00 70. 70 -2. 70 250. 00 72. 00 70. 95 1. 05 300. 00 77. 00 71.01 5. 99 Correlation Coefficient = .958 C-77

CAPSULE Y (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 03:49 PM Page 1 Coefficients of Curve 3 A = 50. B = 50. C = 69.74 TO = 27.24 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 27.3 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: Y Fluence: n/cmA2 125 100 (a

75 w

50 Q,

4 A'-T---t

.Z 1111-1..

25 a

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-75.00 5.00 5.06 - .06

-50.00 10. 00 9. 84 .16

-25.00 10. 00 18. 27 - 8.27

- 10. 00 20. 00 25.58 -5.58

.00 45. 00 31. 40 13. 60

10. 00 35. 00 37. 88 -2.88 15.00 40. 00 '41.31 - 1.31 25.00 50. 00 48. 39 1.61

50. 00 70. 00 65. 76 4.24 C-78

CAPSULE Y (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: Y Fluence: nkcmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

72. 00 75.00 78. 31 - 3. 31 100. 00 85. 00 88. 96 -3. 96 150. 00 95. 00 97. 13 - 2. 1 3 200. 00 100. 00 99. 30 .70 250. 00 100. 00 99. 83 .17 300. 00 100. 00 99. 96 .04 Correlation Coefficient = .990 C-79

CAPSULE X (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 01:20 PM Page 1 Coefficients of Curve 4 A = 44.1 B = 41.9 C = 68.71 TO = 24.7 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=87.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=.7 Deg F Temp@50 ft-lbs=34.5 Deg F Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: X Fluence: nlcMA2 300 250 in

-. 200 0a 0

U-cm 150 IL-z

>100 50 50 ----

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-90. 00 4.00 5.07 - 1. 07

-50. 00 8.00 10. 76 -2.76

- 25. 00 23.00 18. 17 4. 83

- 15. 00 18.00 22. 27 -4.27

.00 25.00 29.66 -4.66

.00 46.00 29. 66 16. 34 10.00 42.00 35.27 6.73 15.00 45.00 38.23 6. 77

30. 00 17.00 47.33 30. 33 C-80

t.

CAPSULE X (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

50. 00 57. 00 58. 87 - 1. 87 75.00 82. 00 70. 26 11. 74 100. 00 85. 00 77.58 7.42 150. 00 82. 00 83. 87 - 1. 87 200. 00 85.00 85.49 -. 49 250. 00 94. 00 85. 88 8. 12 Correlation Coefficient = .941 C-81

CAPSULE X (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 04:15 PM Page 1 Coefficients of Curve 4 A = 35.61 B = 35.61 C = 63.83 TO = 29.18 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=71.2 Lower Shelf L.E.=.0(Fixed)

Temp. @LE. 35 mils=28.1 Deg F Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: X Fluence: n/cmA2 200 150 E

(n C

0 E 100

-0 A , . E-- , ----- -------- .-------------------------

q 50 50

, .. -S'<. ,

0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential

-90. 00 2. 00 1. 66 .34

-50.00 2. 00 5.50 -3.50

- 25.00 14. 00 11. 02 2.98

- 15.00 11. 00 14.27 -3.27

.00 18.00 20.38 -2.38

.00 33.00 20.38 12.62

10. 00 31. 00 25.22 5. 78 15.00 32. 00 27. 83 4. 17

30. 00 14. 00 36. 07 - 22. 07 C-82

CAPSULE X (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input']L.E. Computed L.E. Differential

50. 00 45. Co046. 83 - 1. 83 75.00 67. C00 57.53 9. 47 100. 00 70. CD064. 24 5.76 1.50. 00 67. C0 669.64 -2. 64 200. 00 66. a0 70. 89 -4.89 250. 00 72. C30 771.15 .85 Correlation Coefficient = .953 C-83

CAPSULE X (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 03:50 PM Page 1 Coefficients of Curve 4 A = 50. B = 50. C = 63.06 TO = 29.69 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 29.7 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: X Fluence: n/cMA2 125 100

.-.- A 4

M (n 75 rz E

IL, a! 50 25 A A' 0 - - -. - -

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-90. 00 10.00 2.20 7.80

-50. 00 1 0. 00 7.40 2. 60

- 25. 00 15.00 15.00 .00

- 15.00 15.00 19.51 -4. 51

.00 25.00 28.06 -3. 06

.00 35. 00 28. 06 6.94 10.00 30.00 34. 88 -4. 88 15.00 50. 00 38.56 1 1. 44

30. 00 40. 00 50. 25 - 10. 2 5 C-84

CAPSULE X (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: X Fluence: n/cmr2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

50. 00 65.00 65.57 - . 57 75.00 80. 00 80. 80 -. 80 100. 00 100. 00 90. 29 9.71 150.00 95. 00 97. 85 -2. 85 200. 00 100. 00 99. 55 . 45 250. 00 100. 00 99. 91 .09 Correlation Coefficient = .986 C-85

CAPSULE W (WELD)

CVGRAPIF 50.2 Hyperbolic Tangent Curve Printed on 01/18/2005 03:13 PM Page 1 Coefficients of Curve 1 A = 44.6 B = 42.4 C = 96.14 TO = 46.66 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=87.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=12.2 Deg F Temp@50 ft-lbs=59.0 Deg F Plant: Vogtle 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: W Fluence: n/cmA2 300 250 W

,. 200 0a 0

LL

150 CD lU z

8 100 50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-50. 00 5. 00 12.21 - 7. 2 1

- 25.00 14. 00 17. 79 - 3. 7 9

. 00 36. 00 25.50 10.50

. 00 31. 00 25. 50 5. 50

25. 00 22.00 35.21 -13. 21

50. 00 38.00 46. 07 - 8. 07

75. 00 71.00 56.75 14.25 75.00 64.00 56.75 7. 25 1 00. 00 64. 00 65. 98 - 1. 98 C-86

I - -- 4-11 CAPSULE W (WELD)

Page 2 Plant: Vogtle 2 Material: SMAW . fat: 87005 Orientation: NA Capsule: W Fhience: n/cmA2

.. Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 140.00 71.00 76.36 - 5.36 175.00 73.00 81.51 -8.51 200.00 77.00 83.65 - 6.65 225.00 88.00 84.97 3.03 250.00 79.00 85.78 -6.78 250.00 93.00 85.78 7.22 Correlation Coefficient = .956 C-87

CAPSULE W-(WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 04:15 PM Page 1 Coefficients of Curve 5 A = 34.98 B = 34.98 C = 103.68 TO = 44.94 D = O.OOE+OO Equation is A + B * [Tanh((T-To)I(C+DT))]

Upper Shelf L.E.=70.0 Lower Shelf L.E.=.0(Fixed)

Temp.@L.E. 35 mils=45.0 Deg F Plant: VOGTLE 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: W Fluence: n/cmA2 200 150 r-E 100 CD o , -. - V - _ __ _

50

1. ~ _ V 0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential

- 50. 00 5 . 00 9. 66 -4.66

- 25. 00 1. 00 14.41 - 3.41 00 28. 00 20. 70 7.30 00 25. 00 20.70 4. 30

25. 00 22. 00 28. 34 -6. 34

50. 00 34. 00 36. 69 -2.69

75. 00 47. 00 44. 85 2. 15

75. 00 49. 00 44. 85 4. 15 100. 00 52. 00 51.99 .01 C-88

CAPSULE W (WELD)

Page 2 Plant: VOGTLE 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 140. 00 57. 00 60. 32 -3. 32 175. 00 63.00 64. 70 - 1. 70 200. 00 61.00 66. 62 -5. 62 225.00 74. 00 67. 86 6. 14 250. 00 67.00 68. 65 - 1. 65 250. 00 72. 00 68. 65 3. 35 Correlation Coefficient = .980 C-89

CAPSULE W (WELD)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/19/2004 03:50 PM Page 1 Coefficients of Curve 5 A = 50. B = 50. C = 85.44 TO = 74.41 D = 0.0OE+0O Equation is A + B * (Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 74.5 Plant: VOGTLE 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: W Fluence: n/cmA2 125 100 w

In 75 4-1 0)

CL (0

a.

20so L

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-50. 00 5.00 5. 16 - . 16

- 25.00 5.00 8.89 -3. 89

.00 15.00 14.91 .09

.00 20.00 14.91 5.09

25. 00 25.00 23.93 1.07 50.00 30. 00 36.09 - 6.09 75.00 55. 00 50. 35 4.65

75. 00 50. 00 50. 35 -. 35 100. 00 65.00 64.54 .46 C-90

CAPSULE W (WELD)

Page 2 Plant: VOGTLE 2 Material: SMAW Heat: 87005 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 140. 00 80. 00 82. 28 -2. 28 175. 00 90. 00 91. 33 - 1. 33 200. 00 95. 00 94. 98 .02 225. 00 100. 00 97. 14 2. 86 250. 00 1 00. 00 98. 39 1.61 250. 00 100. 00 98.39 1.61 Correlation Coefficient = .997 C-91

UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:17 AM Page 1 Coefficients of Curve 1 A = 54.1 B = 51.9 C = 73.87 TO = -46.61 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=I106.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temnp@30 ft-lbs=-83.7 Deg F Ternp@50 ft-lbs=-52.4 Deg F Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 300 250 (I

- 200 Ia 0

0 U.

2 150 z

> 100 50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 180. 00 7.00 4.93 2. 07

- 180.00 9.00 4.93 4.07

- 120. 00 13. 00 14.72 -1.72

- 120. 00 16. 00 14.72 1.28

- 120.00 19. 00 14.72 4.28

- 100. 00 14.00 22.00 - 8.00

- 100. 00 30. 00 22.00 8.00

- 100.00 35. 00 22.00 13.00

- 80. 00 28.00 32. 12 - 4. 12 C-92

I l UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 80. 00 43. 00 32. 12 10. 88

- 80. 00 52. 00 32. 12 19. 88

- 60. 00 26. 00 44. 80 -18. 80

-60. 00 34. 00 44. 80 - 10. 80

-60. 00 40. 00 44. 80 -4. 80 30.00 52. 00 65.58 13.58

-30.00 60. 00 65.58 5.58

30. 00 67.00 65. 58 1.42

.00 80. 00 83. 10 -3. 10

.00 85. 00 83. 10 1.90

.00 97. 00 83. 10 13.90

30. 00 96. 00 94.41 1.59 30.00 99.00 94.41 4. 59

30. 00 109. 00 94.41 14.59

80. 00 96. 00 102. 74 -6.74

80. 00 102. 00 102. 74 -. 74

80. 00 114. 00 102. 74 11.26 120.00 100. 00 104. 87 4.87 120.00 102. 00 104. 87 -2. 87 120.00 122. 00 104. 87 17. 13 160.00 96. 00 105. 62 -9. 62 160.00 110.00 105. 62 4.38 160. 00 I 1 9. 00 105. 62 13.38 210.00 96. 00 105.90 -9. 90 210. 00 124. 00 105. 90 18. 10 Correlation Coefficient = .968 C-93

UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 12:25 PM Page 1 Coefficients of Curve 1 A = 36.21 B = 36.21 C = 74.44 TO = -44.47 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=72.4 Lower Shelf L.E.=.O(Fixed)

Temp. @L.E. 35 mils=-46.9 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 200 150 c,

0 E 100 5-50 0 '

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential

- 180.00 4.00 1. 85 2. 15

- 180. 00 3.00 1. 85 1. 15

- 120. 00 5.00 8.41 -3. 41

- 120.00 9.00 8.41 .59

- 120.00 11. 00 8.41 2. 59

- 100. 00 5.00 13. 30 -8. 30

- 100. 00 18.00 13.30 4. 70

- 100. 00 22.00 13.30 8.70

- 80. 00 18.00 20. 13 -2. 13 C-94

UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

- 80. 00 25.00 20. 13 4. 87

- 80. 00 32. 00 20. 13 11.87

- 60. 00 19. 00 28. 77 -9. 77

- 60. 00 21. 00 28. 77 -7.77

-60. 00 29. 00 28. 77 .23

-30. 00 37. 00 43. 17 - 6. 17

-30. 00 43. 00 43. 17 -. 17

-30. 00 44. 00 43. 17 .83 00 52. 00 55. 60 -3. 60 00 50. 00 55.60 -5. 60 00 66. 00 55. 60 10.40

30. 00 68. 00 63. 80 4. 20

30. 00 66. 00 63. 80 2. 20

30. 00 73.00 63. 80 9. 20

80. 00 72. 00 69.96 2.04

80. 00 65.00 69. 96 -4.96

80. 00 72. 00 69. 96 2. 04 120. 00 64. 00 71.57 -7.57 120. 00 64. 00 71.57 -7.57 120. 00 78. 00 71.57 6. 43 160. 00 73. 00 72. 13 .- 87 160. 00 71.00 72. 13 1.13 160. 00 72. 00 72. 13 210. 00 72. 00 72. 35 - . 35 210. 00 73. 00 72. 35 .65 Correlation Coefficient = .978 C-95

UNIRRADIATED (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:35 AM Page 1 Coefficients of Curve 1 A = 50. B = 50. C = 53.04 TO = -34.64 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = -34.6 Plant: Vogtle 2 Material: SA533B1. Heat: C3500-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 125 -

100 0 -

I-to 75 ._ __

CD a)

D1.1 50 25 0

00

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-180.00 . 00 .41 - .41

- 180. 00 . 00 . 41 -. 41

- 120. 00 5.00 3. 85 1. 15

- 120. 00 5.00 3. 85 1. 15

- 120. 00 5. 00 3. 85 1. 15

- 100. 00 5.00 7. 84 -2. 84

- 100. 00 5.00 7. 84 -2. 84

-100. 00 10.00 7.84 2. 16

-80. 00 10.00 15.31 -5. 31 C-96

UNIRRADIATED (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: UNIRR Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 80. 00 20. 00 15.31 4. 69

-80. 00 25.00 15.31 9. 69

- 60. 00 20. 00 27.77 -7. 77

-. 60. 00 25.00 27. 77 -2. 77

- 60. 00 35. 00 27. 77 7.23

-30. 00 60. 00 54. 36 5. 64

-30. 00 45.00 54. 36 -9. 36

-30. 00 60. 00 54. 36 5. 64

.00 70. 00 78. 69 -8. 69

.00 60. 00 78. 69 - 18. 69 00 90.00 78.69 11.31

30. 00 100.00 91.96 8. 04

30. 00 1 00. 0 0 91.96 8. 04

30. 00 100. 00 91.96 8. 04

80. 00 100. 00 98. 69 1. 31

80. 00 100. 00 98. 69 1. 31

80. 00 100. 00 98. 69 1. 31 120. 00 100. 00 99. 71 . 29 120.00 100. 00 99.71 . 29 120. 00 100. 00 99.71 . 29 160. 00 1 0 0. 00 99. 94 .06 160. 00 100.00 99.94 .06 160. 00 100. 00 99. 94 .06 210. 00 100. 00 99. 99 .01 210.00 100. 00 99.99 .01 Correlation Coefficient = .990 C-97

CAPSULE U (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:17 AM Page 1

.Coefficients of Curve 2 A = 62.1 B = 59.9 C = 70.83 TO = -65.7 D = O.OOE+O0 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=122.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-108.0 Deg F Temp@50 ft-lbs=-80.2 Deg F Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: NA Capsule: U Fluence: n/cmA2 300 250 cm

- 200 1

0 0

U-El 150 z

> 100 50 O30

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 150. 00 17.00 12.35 4. 65 125.00 22.00 21.11 .89 I 10. 00 32.00 28. 86 3. 14 1 00. 00 51. 00 35. 17 15. 83

- 80. 00 40. 00 50. 17 - 10. 17

-75. 00 39.00 54.28 - 15.28

-50. 00 52.00 75. 17 - 23. 17

.40. 00 99. 00 82. 93 16. 07

- 25.00 112.00 93. 18 18. 82 C-98

CAPSULE U (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: NA Capsule: U Flueince n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

-25. 00 112.00 93. 18 18. 82

.00 83.00 105. 80 - 22. 80

25. 00 108.00 113.41 -5.41

75. 00 125.00 119. 79 5. 21 110. 00 128. 00 121. 17 6. 83 150. 00 126. 00 121. 73 4.27 Correlation Coefficient = .941 C-99

CAPSULE U (HEAT AFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 12:25 PM Page 1 Coefficients of Curve 2 A = 32.95 B = 32.95 C = 57.44 TO = -71.33 D = O.0OE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=65.9 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=-67.7 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: U Fluence: n/cmA2 200 150 +

E

.2 C

100 2

0 z

0I 0 I 01 9~/ 0 Er-

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed LE. Differential 150. 00 7.00 4.00 3.00 125. 00 11. 00 8.81 2. 19 110. 00 17.00 13.61 3.39 100. 00 25.00 17.75 7.25

- 80. 00 19.00 28. 02 -9. 02

-75. 00 23. 00 30. 85 -7. 85

-50. 00 35. 00 44. 65 -9. 65

-40. 00 67. 00 49. 33 17. 67

- 25. 00 60. 00 54. 95 5.05 C-100

It CAPSULE U (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

- 25. 00 60. 00 54. 95 5. 05

.00 49.00 60. 83 -11. 83 25.00 62.00 63.68 - 1. 68 75.00 70. 00 65. 50 4. 50 110.00 69.00 65.78 3. 22 150. 00 60. 00 65. 87 -5. 87 Correlation Coefficient = .941 C-101

CAPSULE U (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:35 AM

- Page 1 Coefficients of Curve 2 A = 50. B = 50. C = 62.09 TO = -74.49 D = O.OOE+OO Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = -74.4 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: U Fluence: nlcmA2 125 100 X =a~~t'r': I a.- I 11 co 75 I, a-0~ 50 25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 150. 00 10. 00 8.08 1.92 125.00 15. 00 16.43 -1.43 110.00 25. 00 24. 17 .83 100. 00 45.00 30.54 14.46

- 80. 00 40.00 45.58 -5.58

-75.00 40. 00 49. 59 9. 59

-50. 00 50. 00 68.76 - 18.76

-40. 00 90. 00 75. 23 14.77

- 25. 00 95. 00 83. 12 11.88 C-102

CAPSULE U (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: U Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

-25.00 90. 00 83. 12 6. 88

.00 80. 00 91. 68 - 11. 68 25.00 100. 00 96. 10 3.90 75.00 100. 00 99. 20 . 80 110.00 I 100.00 99. 74 .26 150. 00 100. 00 99. 93 .07 Correlation Coefficient = .961 C-103

CAPSULE Y (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:17 AM Page 1 Coefficients of Curve 3 A = 58.1 B = 55.9 C = 73.59 TO = -53.18 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=1 14.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-93.8 Deg F Temp@50 ft-lbs=-63.9 Deg F Plant Vogtle 2 Material: SA533BI Heat: C3500-2 Orientation: NA Capsule: Y Fluence: n/cmA2 JUU 250 0

, 200 1-0 0

L.

%150 I-z

> 100 50 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 150. 00 20. 00 9.71 10.29

- 125. 00 16.00 16. 10 -. 10

-100. 00 29.00 26. 67 2.33

- 85.00 26. 00 35. 33 -9.33

-75.00 37. 00 42. 00 -5. 00

- 60.00 54. 00 52. 94 1.06

-50. 00 68.00 60.52 7.48

- 25.00 79.00 78.52 .48

.00 93. 00 92. 68 .32 C-104

CAPSULE Y (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: Y Fluence: n/cMA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 25.00 100. 00 102. 07 -2. 07 72.00 108. 00 110. 40 -2. 40 100. 00 117.00 112. 29 4.71 125.00 106. 00 113.13 -7. 13 175.00 118.00 113.77 4. 23 200. 00 135.00 113.89 21.11 Correlation Coefficient = .983 C-105

CAPSULE Y (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 12:25 PM Page I Coefficients of Curve 3 A 35.29 B = 35.29 C = 78.8 TO = -52.82 D = O.00E+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=70.6 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=-53.4 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: Y Fluence: nrcm^2 200 150 o

2 100 O~.....'.....*..............

50

,,,, ,, 1-----ap$F . lIC.

0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential 150. 00 7.00 5.52 1.48 125. 00 12. 00 9.74 2.26 100. 00 21. 00 16. 37 4.63

- 85. 00 13.00 21. 63 -8.63

- 75. 00 22.00 25.61 -3.61

- 60. 00 38.00 32. 08 5.92

- 50. 00 37.00 36.55 .45

- 25. 00 47.00 47.25 -2.25 00 53.00 55.94 -2.94 C-1 06

CAPSULE Y (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B I Heat: C3500-2 Orientation: NA Capsule: Y Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential 25.00 67.00 61.98 5. 02

72. 00 64. 00 67. 73 -3. 73 100. 00 71.00 69. 15 1. 85 125.00 70. 00 69. 81 .19 175. 00 67.00 70. 36 -3. 36 200. 00 73. 00 70. 46 2.54 Correlation Coefficient = .987 C-107

CAPSULE Y (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:35 AM Page 1 Coefficients of Curve 3 A = 50. B = 50. C = 34.94 TO = -49.36 D = O.OOE+0O Equation is -A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = -49.3 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: Y Fluence: n/cmA2 125 100 M 75 Ce W

CD 1-1 50 25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 150. 00 5. 00 .31 4.69

- 125. 00 10. 00 1.30 8.70

- 1 00. 00 10. 00 5.22 4.78

- 85. 00 10. 00 11.51 - 1.51

-75. 00 20. 00 18.73 1.27

- 60. 00 30. 00 35.23 -5. 23

-50. 00 50. 00 49.08 .92

-25. 00 85. 00 80. 13 4. 87

.00 90. 00 94.40 - 4. 40 C-108

CAPSULE Y (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: Y Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 25.00 100.00 98. 60 1.40 72.00 100.00 99.90 .10 100. 00 100.00 99. 98 . 02 125. 00 100. 00 100.00 .00 175. 00 100.00 100. 00 . 00 200. 00 100. 00 100. 00 .00 Correlation Coefficient = .997 C-109

CAPSULE X (HAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:18 AM Page 1 Coefficients of Curve 4 A = 50.6 B = 48.4 C = 74.79 TO = -52.28 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=99.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-86.2 Deg F Temp@50 ft-lbs=-53.2 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: X Fluence: nlcm^2 300 250 (0

- 200 a

0 0

U-2 150 z

8 100 50 o ..

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential 180.00 3.00 5.28 -2.28 140. 00 12.00 10. 66 1.34 I100. 00 24. 00 23. 32 .68

-75.00 52. 00 36. 33 15. 67

-50. 00 33. 00 52.08 19. 08

- 25.00 72.00 67. 5 1 4.49

- 25.00 63.00 67.51 -4.51

- 15. 00 65. 00 72.91 -7.91

.00 84. 00 79. 82 4. 18 C-1 10

CAPSULE X (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

10. 00 101.00 83. 61 17.39

40. 00 81. 00 91.44 - 10. 44

75. 00 107.00 95. 89 11. 11 125.00 98.00 98. 16 - . 16 150. 00 112. 00 98. 57 13.43 175. 00 80.00 98. 78 - 18. 78 Correlation Coefficient = .945 C-111

CAPSULE X (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 12:25 PM Page 1 Coefficients of Curve 4 A = 34.72 B = 34.72 C = 81.9 TO = -36.15 D = O.OOE+0O Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=69.4 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=-35.4 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: X Fluence: n/cmA2 200 150 0

100 50 0

C A

.00 A,,f' c*A

. ... ~~----- !.

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential 180. 00 .0 0 2.01 -2.01 140. 00 2.00 5.09 -3.09 100. 00 14. 00 12.07 1.93

-75.00 29.00 19.38 9. 62

-50. 00 20. 00 28. 90 -8.90

- 25. 00 44.00 39.42 4. 58

- 25. 00 33. 00 39.42 -6.42

- 15.00 42. 00 43.49 - 1.49

.00 53.00 49. 12 3. 88 C-112

CAPSULE X (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

10. 00 55. 00 52. 45 2. 55

40. 00 54. 00 60. 08 -6. 08

75. 00 73. 00 65. 12 7. 88 125. 00 68. 00 68. 11 -. 11 150. 00 72. 00 68.71 3.29 175. 00 62.00 69. 04 -7.04 Correlation Coefficient = .973 C-1 13

CAPSULE X (HAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:35 AM Page 1 Coefficients of Curve 4 A = 50. B = 50. C = 74.29 TO = -40.29 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = 40.2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: X Fluence: n/cmA2 125 100 I-.

75 co CD IL 50 25 0 4-

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 180.00 2. 00 2.27 - .27

- 140. 00 5. 00 6. 39 - 1. 39

- 100. 00 10. 00 16.70 -6.70

-75.00 45.00 28. 20 16. 80

-50. 00 35;. 00 43.50 - 8.50

- 25.00 55.00 60. 15 -5. 15

- 25.00 55. 00 60. 15 -5. 15

- 15.00 65. 00 66. 39 - 1.39

.00 85.00 74.74 10.26 C-1 14

CAPSULE X (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: X Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential 10.00 90. 00 79.48 10. 52

40. 00 75.00 89.68 - 14. 68 75.00 100. 00 95.71 4.29 125. 00 100.00 98. 85 1.15 150. 00 100. 00 99.41 .59 175.00 100. 00 99. 70 .30 Correlation Coefficient = .974 c-115

CAPSULE W (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:18 AM Page 1 Coefficients of Curve 5 A = 51.1 B = 48.9 C = 53.34 TO = -55.88 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf Energy=100.0(Fixed) Lower Shelf Energy=2.2(Fixed)

Temp@30 ft-lbs=-80.5 Deg F Temp@50 ft-lbs=-57.0 Deg F Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: W Fluence: ncm^A2 300 250 tn 8, 200 0

CD a,

Lu z

100 50 0 4=--

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

- 175. 00 3.00 3.31 -. 31

- 125.00 17.00 9.01 7.99

-90. 00 31. 00 23.49 7.51

-75.00 43.00 34.28 8.72

-75.00 17.00 34.28 - 17.28

-50. 00 57.00 56.46 .54

-50. 00 57.00 56.46 .54

-25.00 67.00 76.62 -9.62

.00 101.00 89.28 11. 72 C-1 16

CAPSULE W (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: NA Capsule: W Fluence: n/cmr2 Charpy V-Notch Data Temperature Input CVN Computed CVN Differential

. 00 92. 00 89. 28 2. 72

25. 00 98. 00 95.50 2. 50

50. 00 99. 00 98. 19 .81 75.00 105.00 99. 28 5.72 125. 00 107.00 99. 89 7. 11 150. 00 93.00 99. 96 -6. 96 Correlation Coefficient = .977 C-1 17

CAPSULE W (HEAT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 12:25 PM Page 1 Coefficients of Curve 5 A = 34.01 B = 34.01 C = 62.8 TO = -48.33 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Upper Shelf L.E.=68.0 Lower Shelf L.E.=.0(Fixed)

Temp. @L.E. 35 mils=46.5 Deg F Plant:Vogtle2 Material:SA533BI Heat: C3500-2 Orientation: NA Capsule: W Fluence: n/cmA2 200 150 "3

0 E 100 6

I4..

-I-50o I-.

0

-300 0 300 600 Temperature in Deg F Charpy V-Notch Data Temperature Input LE. Computed L.E. Differential

-175.00 2. 00 1.18 .82

- 125.00 8.00 5.45 2. 55

-90. 00 19.00 14. 26 4.74

-75.00 25.00 20. 38 4.62

-75. 00 12.00 20. 38 -8.38

-50. 00 32.00 33. 11 -1. 11

-50. 00 34.00 33. 11 .89

-25.00 36. 00 46. 09 - 10. 09

.00 71. 00 56.00 15.00 C-118

CAPSULE W (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B 1 Heat: C3500-2 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input L.E. Computed L.E. Differential

. 00 59. 00 56. 00 3.00 25.00 58.00 62. 02 -4.02

50. 00 60.00 65. 18 -5. 18

75. 00 65.00 66. 71 - 1.71 125.00 68. 00 67. 75 . 25 150. 00 70. 00 67. 90 2. 10 Correlation Coefficient = .969 C-1 19

CAPSULE W (AT AFFECTED ZONE)

CVGRAPH 5.0.2 Hyperbolic Tangent Curve Printed on 11/22/2004 11:36 AM Page 1 Coefficients of Curve 5 A = 50. B = 50. C = 59.52 TO = -42.89 D = O.OOE+00 Equation is A + B * [Tanh((T-To)/(C+DT))]

Temperature at 50% Shear = -42.8 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: W Fluence: nlcm^2 125 100 75 CD, co a-L.1 50 25 0

-300 -200 -100 0 100 200 300 400 500 600 Temperature in Deg F Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

- 175.00 2.00 1. 17 . 83

- 125.00 5.00 5. 96 -. 96

-90. 00 15.00 17. 04 -2.04

-75.00 20. 00 25. 37 -5.37

-75.00 15.00 25. 37 - 10. 37

-50.00 55.00 44. 05 10. 95

-50.00 60. 00 44. 05 15.95

-25.00 50. 00 64. 59 - 14.59

.00 90. 00 80. 86 9. 14 C-120

CAPSULE W (HEAT AFFECTED ZONE)

Page 2 Plant: Vogtle 2 Material: SA533B1 Heat: C3500-2 Orientation: NA Capsule: W Fluence: n/cmA2 Charpy V-Notch Data Temperature Input Percent Shear Computed Percent Shear Differential

.00 70.00 80. 86 - 10. 8 6 25.00 100.00 90.73 9.27 50.00 85.00 95.78 - 10. 78 75.00 95.00 98. 13 -3. 13 125. 00 100. 00 99. 65 .35 150. 00 100. 00 99. 85 .15 Correlation Coefficient = .971 C-121

WCAP-16382 D-0 WCAP-16382 D-O APPENDIX D VOGTLE UNIT 2 SURVEILLANCE PROGRAM CREDIBILITY EVALUATION Appendix D

WCAP-16382 D-1 D.1 WCAP-16382 INTRODUCTION:

Regulatory Guide 1.99, Revision 2, describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels. Position C.2 of Regulatory Guide 1.99, Revision 2, describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data. The methods of Position C.2 can only be applied when two or more credible surveillance data sets becomes available from the reactor in question.

To date there have been four surveillance capsules removed from the Vogtle Electric Generating Plant Unit 2 reactor vessel. To use these surveillance data sets, they must be shown to be credible. In ;

accordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that must be met for the surveillance data to be judged credible.

The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the Vogtle Electric Generating Plant Unit 2 reactor vessel surveillance data and determine if the Vogtle Electric Generating Plant Unit 2 surveillance data is credible.

EVALUATION:

CRITERION 1: Materialsin the capsules should be thosejudged most likely to be controllingwith regardto radiationembrittlements.

The beltline region of the reactor vessel is defined in Appendix G to 10CFR Part 50; "Frature Toughness Requirements", as follows:

"the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage."

The Vogtle Electric Generating Plant Unit 2 reactor vessel consists of the following beltline region materials:

- Intermediate shell plates R4-1, R4-2 and R4-3

- Lower shell plates B8825-1, R8-1 and B8628-1

- The intermediate shell longitudinal weld seams 101-124A,B,C, lower shell longitudinal weld seams 101-142A,B,C were all fabricated with weld wire heat number 87005, Linde 0091 Flux, Lot 0145.

- The intermediate to lower shell girth weld seam 101-171 was fabricated with weld wire heat number 87005, Linde 124 Flux, Lot 1061.

Appendix D

WCAP-16382 D-2 D-2 WCAP-1 6382 The Vogtle Unit 2 surveillance program utilizes longitudinal, transverse test specimens from lower shell plate B8628-1. The surveillance weld metal was fabricated with weld wire heat number 87005, Flux Type Linde 124 Lot Number 1061.

At the time when the surveillance program material was selected it was believed that copper and phosphorus were the elements most important to embrittlement of reactor vessel steels. Lower shell plate B8628-1 had the highest initial RTNDT and one of the lowest initial USE values of all plate materials in the beltline region. In addition, lower shell plate B8628-1 had approximately the same copper and phosphorous content of the other beltline plate materials. Hence, based on the highest initial RTNDT and one of the lowest initial USE of all plate materials, the lower shell plate B8628-1 was chosen for the surveillance program. The girth weld, on the other hand, has the same heat as all the beltline welds but a different flux. The girth weld had a lower initial RTNDT of the two flux types. However, both welds had low initial RTNDT values and the same copper/phosphorus content. The initial USE of the girth weld used in the surveillance program was 50 to 60 ft-lbs lower than the weld wire & flux used in the longitudinal weld seams. Hence, the girth weld was selected based on the lower USE value.

Based on the above discussion and the methodology in use at the time the program was developed, the Vogtle Unit 2 surveillance material meets the intent of this criterion.

CRITERION 2: Scatter in the plots of Charpy energy versus temperaturefor the irradiatedand unirradiatedconditions should be small enough to permit the determination of the 30ft-lb temperature and upper shelfenergy unambiguously.

Plots of the Charpy energy versus temperature for the unirradiated and irradiated condition are presented in Section 5 and Appendix C of this Report.

Based on engineering judgment, the scatter in the data presented in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy of the Vogtle Electric Generating Plant Unit 2 surveillance materials unambiguously. Therefore, the Vogtle Electric Generating Plant Unit 2 surveillance program meets the intent of this criterion.

CRITERION 3: When there are two or more sets ofsurveillancedatafrom one reactor, the scatter of ARTNDT values about a best-fit line drawn as describedin Regulatory Position2.1 normally should be less than 28 7Ffor welds and 17 Tfor base metal Even ifthefluence range is large (tuvo or more orders ofmagnitude), the scattershould not exceed twice those values. Even ifthe datafails this criterionfor use in shift calculations, they may be crediblefor determining decrease in upper sheIfenergy if the upper shelfcan be clearly determined, following the definitiongiven in ASTME185-82.

The functional form of the least squares method as described in Regulatory Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of these ARTNDT values about this line is less than 281F for welds and less than 171F for the plate.

Appendix D

.,- i _;

v 7{-,

WCAP-16382 D-3 WCAP-1 6382 D-3 Following is the calculation of the best-fit line as described in Regulatory Position 2.1 of Regulatory Guide 1.99, Revision 2. In addition, the recommended NRC methods for determining credibility will be followed. The NRC methods were presented to industry at a meeting held by the NRC on February 12 and 13, 1998. At this meeting the NRC presented five cases. Of the five cases, Case I ("Surveillance data available from plant but no other source") most closely represents the situation listed above for Vogtle Unit 2 surveillance weld metal and plate materials.

TABLE D-I Calculation of Chemistry Factors using Vogtle Unit 2 Surveillance Capsule Data Material Capsule Capsule f<*) FF(b) ARTNDT(C) FF*ARTNDT FF2 Lower Shell U 0.356 0.715 2.0 1.43 0.511 Y 1.12 1.03 5.8 5.97 1.06 Plate -B8628-1 X 1.78 1.16 29.4 34.10 1.35 (Longitudinal)

W 2.98 1.29 39.0 50.31 1.66 Lower Shell U 0.356 0.715 0.0) 0.00 0.511 Y 1.12 1.03 1.9 1.96 1.06 Plate B8628-1 X 1.78 1.16 29.8 34.57 1.35 (Transverse) 4.

W 2.98 1.29 45.5 58.70 1.66 SUM: 187.04 9.162 CFB 86 2s.1 = MIFF

• RTNDT) + J;( FF2 ) = (187.04) + (9.162) = 20.41F Surveillance Weld U 0.356 0.715 0.0(d) 0.00 0.511 Material Y 1.12 1.03 18.7 19.3 1.06 X 1.78 1.16 19.9 23.1 1.35 W 2.98 1.29 31.4 40.5 1.66 SUM: 82.9 4.581 CFs.,,.Wd =(FF

• RTNDT) + ( FF 2) = (82.9) + (4.581) = 18.10 F Notes:

(a) f = fluence. See Section 6, [x 10'9 n/cm 2, E> 1.0 MeVI.

(b) FF = fluence factor (c) ARTNDT values are the measured 30 ft-lb shift values taken from Appendix C, herein [IF].

(d) Actual values for ARTNDT are -7.1 (Plate) and -17.3 (Weld). This physically should not occur, therefore for conservatism a value of zero will be used.

Appendix D

WCAP-16382 Do D-4 WCAP-16382 The scatter of ARTNDT values about the functional form of a best-fit line drawn as described in Regulatory Position 2.1 is presented in Table D-2.

Table D-2 Vogtle Unit 2 Surveillance Capsule Data Scatter about the Best-Fit Line for Surveillance Forging Materials.

Table D-2 indicates that one measured plate ARTNDT value is below the lower bound la of -17'F and one measured plate ARTNDT value is above the upper bound I a of 171F. Both are less the 2.2 IF from the upper and lower limits. From a statistical point of view, +/-la (170F) would be expected to encompass 68% of the data. In this case 80% is within the scatter band of +/- cr. The fact that two plate data points are out by 2.20 F or less can be attributed to several factors, such as 1)the inherent uncertainty in the Charpy test data, 2) the use of a plotting program versus hand drawn plots using engineering judgment, 3)

Symmetric plots versus asymmetric plots, and/or rounding errors.

Looking at the data in Table D-2, all the measured plate ARTNDT values are below or within the upper bound Ia of 17'F except for one. The one data point is above Ia by only 2.21F. Hence based on the evaluation above, the plate data meets the intent of this criterion.

As for the surveillance weld, all the scatter is within the acceptable range for credible data.

Appendix D

1. i WCAP-16382 D-5 CRITERION 4: The irradiationtemperature of the Charpy specimens in the capsule should match the vessel wall temperatureat the cladding/basemetal interface within +/-250F The capsule specimens are located in the reactor between the core barrel and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the neutron pads.

The location of the specimens with respect to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperature will not differ by more than 251F. Hence, this criterion is met.

CRITERION 5: The surveillancedatafor the correlationmonitor materialin the capsule shouldfall within the scatter band of the data basefor that material.

The Vogtle Electric Generating Plant Unit 2 surveillance program does not contain correlation monitor material. Therefore, this criterion is not applicable to the Vogtle Electric Generating Plant Unit 2 surveillance program.

CONCLUSION:

Based on the preceding responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B and 10CFR 50.61, the Vogtle Electric Generating Plant Unit 2 surveillance data is Credible.

Appendix D